PWRRM January 2010

pwrrm@retaqs.com

15 participants
11 discussions

Use of Spreadsheets for Surveillances
by Gore, Duane 03 May '10

03 May '10

We at STP use spreadsheets to perform surveillance calculations. The results are then independently verified by a second engineer using an independently generated spreadsheet. Neither spreadsheet has been formally verified per our station Software Quality Assurance procedure. In cases where the results are used without further verification, we do properly QA the spreadsheets (usually in the cases where other groups use the spreadsheets). Our QA department is of the opinion that at least one of these spreadsheets used for surveillances must by fully verified and documented per our station Software Quality Assurance procedure. It would help my case if I could cite other Rae's practices with regards to the use of spreadsheets. What is the practice at your plant? Thank you, Duane Gore Supervisor, Reactor Engineering STPNOC (361) 972-8909

8 8

Electronic Benchmarking - Fuel Handling Issues
by WILLETT, JOSEPH E 15 Feb '10

15 Feb '10

We apologize for the lengthy list, but we're trying get the year started off right and wrap-up from a late fall outage. Fort Calhoun Station Reactor Engineering is looking to benchmark a few items 1) Do your stations fuel handling machines require fall protection? a. If yes, what measures are taken? Netting, harnesses, etc. b. If using netting, where is it attached? c. If using fall protection, where are the tie-offs? 2) What are you requirements for fuel movement in the Spent Fuel Pool? a. Continuous communications with Control Room? If yes, SRO, RO., Other. b. Do you require oversight on the spent fuel handling machine (SRO, RO, Other)? c. Is your procedure Continuous Use, Information Use or Reference Use? d. Do you utilize Vendors? If so, what additional oversight is required? 3) What type of underwater lights do you use for normal Spent Fuel Pool Lighting? a. Style: drop light or mounted b. Vendor: c. How many: d. Spacing: e. Ballasts: above water or submerged? 4) What type of underwater lights do you use for normal Reactor Cavity Lighting? a. Style: drop light or mounted b. Vendor: c. How many: d. Spacing: e. Ballasts: above water or submerged? 5) What type of underwater lights do you use for supplemental lighting? If Necessary. a. If so what would require the additional lighting? b. Style: drop light or mounted c. Vendor: d. How many: e. Spacing: f. Ballasts: above water or submerged? J. E. Willett ---------------------------------------------------- Joseph E. Willett, P.E. Principal Reactor Engineer-Fuel Nuclear Operations Division E-mail: jwillett(a)oppd.com<mailto:jwillett@oppd.com> Omaha Public Power District Phone: (402) 533-7213 Fort Calhoun Station Pager: (402) 561-3899 9610 Power Lane FAX: (402) 533-6747 Blair, NE 68008 Mail Station: FC-1-1 Plant ---------------------------------------------------- -------- This e-mail contains Omaha Public Power District's confidential and proprietary information and is for use only by the intended recipient. Unless explicitly stated otherwise, this e-mail is not a contract offer, amendment, nor acceptance. If you are not the intended recipient you are notified that disclosing, copying, distributing or taking any action in reliance on the contents of this information is strictly prohibited.

3 2

Measured power and uncertanties
by Adina K Lafrance 10 Feb '10

10 Feb '10

Surry is trying to answer a question this morning regarding power level indications and uncertainties. We are stating that within a certain confidence level, that the calorimetric calculation will produce a reactor power output (at RTP) from 98.8 to 101.2% with the rightly calibrated process instrumentation in the calorimetric program (App K). Half the time the operating power will be above 100%, half the time it will be below 100%. The opposing opinion is that if we have a 1.2% RTP uncertainty that we operate at or below 98.8% so as to not exceed RTP. The uncertainties in question relate to the plant computer-none of the redundant indications indicate higher than RTP (most notably delta Ts). It is also noted that we were told that no other site operates the way we are with regard to uncertainties. Can you please tell us how your site operates with regard to uncertainties and your RTP? Thank you in advance. Adina LaFrance The significant problems we face cannot be solved at the same level of thinking we were at when we created them. -Albert Einstein Nuclear Analysis & Fuel Reactor Engineer Surry Power Station Email: Adina.K.LaFrance(a)Dom.com<mailto:Adina.K.LaFrance@Dom.com> Phone: 757-365-2658 Pager #: 4290 CONFIDENTIALITY NOTICE: This electronic message contains information which may be legally confidential and or privileged and does not in any case represent a firm ENERGY COMMODITY bid or offer relating thereto which binds the sender without an additional express written confirmation to that effect. The information is intended solely for the individual or entity named above and access by anyone else is unauthorized. If you are not the intended recipient, any disclosure, copying, distribution, or use of the contents of this information is prohibited and may be unlawful. If you have received this electronic transmission in error, please reply immediately to the sender that you have received the message in error, and delete it. Thank you.

5 4

PWR RM PI Significance Level for "Designed Runbacks"
by Sanders, Gene Jr 25 Jan '10

25 Jan '10

Ref.: PWR RM PI document, Rev.1 (Draft 8-10-09) Attach. 3, "Significance Level 3 Event Examples", ex. 3.9 and Attach. 4, "Significance Level 4 Event Examples", ex. 4.6. 3.9 Unplanned Reactivity Change Caused by Equipment Problem or Personnel Error Reactor Power Change > 0.5% RTP When >5% RTP Reactivity Change > x pcm When < 5% RTP 4.9 Unplanned Reactivity Change Caused by Equipment Problem or Personnel Error Reactor Power Change < 0.5% RTP When >5% RTP Reactivity Change < x pcm When < 5% RTP Are the above examples to be applied to "Design Runbacks"? Even though a plant runback was/is incorporated into a given plant's control design, are these occurrences to be considered an "Unplanned Reactivity Change / Reactor Power Change"? For example, at Oconee, a loss of the Operator Aid Computer (OAC) Core Thermal Power (CTP) Signal to the Integrated Control System (ICS) will cause the ICS to control the plant to a CTP calculated by the ICS, which typically results in a real power reduction, "by design", of ~0.75% RTP. If this occurrence / scenario is considered to be "Unplanned", then a "Significance Level 3 Event" appears to be required, even though the significance of such an Event pales in comparison to other Level 3 Event Examples. Is this what was / is intended for design runbacks? Thanks in advance for your response, T E (Gene) Sanders ONS Rx Engineering 864.873.3377

1 0

Survey Response from North Anna Power Station
by Bobby Speckine 20 Jan '10

20 Jan '10

The responses from NAPS are below in RED. Bobby Speckine Fuel Handling Supervisor NAPS 540-894-2507 From: pwrrm(a)retaqs.com [mailto:pwrrm@retaqs.com] On Behalf Of WILLETT, JOSEPH E Sent: Wednesday, January 13, 2010 9:29 AM To: pwrrm(a)retaqs.com Cc: BUSSEY, TIMOTHY J Subject: [Pwrrm] Electronic Benchmarking - Fuel Handling Issues We apologize for the lengthy list, but we're trying get the year started off right and wrap-up from a late fall outage. Fort Calhoun Station Reactor Engineering is looking to benchmark a few items 1. Do your stations fuel handling machines require fall protection? [Stanley, William S (TMI)] Yes, while getting on or off the bridge. Don't need fall protection once actually on the bridge, unless there is a need to climb off the normal walking paths (to check brakes and cables, for example). (NAPS) We use fall protection around the cavity area when the water level is greater than 10 ft down from the operating deck. If the water level is less than 10 ft below the deck life vests are required. Once on the crane (behind the handrails) fall protection is not required. a. If yes, what measures are taken? Netting, harnesses, etc.[Stanley, William S (TMI)] Life vests or climbing harnesses may be used to get to the bridge. No nets (NAPS) We do not use any nets. Harness tie offs are provided from cables along the S/G bio walls with retractable lanyards. b. If using netting, where is it attached?[Stanley, William S (TMI)] N/A (NAPS) N/A c. If using fall protection, where are the tie-offs?[Stanley, William S (TMI)] Tie-off for the climbing harness is a cable along the walkway to the bridge. When climbing on the bridge, tie-off is to bridge structure. (NAPS) See 1a above. 1. What are you requirements for fuel movement in the Spent Fuel Pool? d. Continuous communications with Control Room? If yes, SRO, RO., Other.[Stanley, William S (TMI)] Fuel movement in SFP requires initial approval by the Control Room, but NOT continuous communication during movement. During refueling (offload/reload), the SF bridge crew is in continuous communication w/ the FH SRO, who is stationed in the Reactor Building on the Main Fuel Handling Bridge, and the Control Room (RO) who is directing the move sequence. (NAPS) We are required to maintain constant communications with the MCR from the Manipulator Crane in containment during fuel movement. The FB is also in constant communication with the MCR and containment. The SRO in containment is also in constant communication with the MCR. We do not use an SRO in the FB however we do have a FB supervisor who is also in the communication loop. e. Do you require oversight on the spent fuel handling machine (SRO, RO, Other)?[Stanley, William S (TMI)] For "isolated" SFP operations, SRO supervises movements. (NAPS) We utilize the SRO's and fuel advisors (vendors) as "spotters". The fuel moves are directed from the MCR and tracked using Fuel Handling Reports (move sheets) by all station operators. The SRO's and FB supervisors are the independent verifiers for these moves. f. Is your procedure Continuous Use, Information Use or Reference Use?[Stanley, William S (TMI)] Continuous use. (NAPS) Our controlling procedure for all Refueling activities is continuous use. Our operating procedures (crane, FH tools, etc) are reference use. g. Do you utilize Vendors? If so, what additional oversight is required?[Stanley, William S (TMI)] During refueling outages, bridges are operated by mix of vendor and company personnel (company personnel are part of the Reactor Services group, who travel from plant to plant for outages). Company personnel provide oversight. (NAPS) All of our equipment and fuel handling activities are done by site personnel (Ops Support). We do use Stearns Rogers crane techs and fuel advisors. These folks are under the direction of the Ops Support group and we provide any vendor oversight required. 1. What type of underwater lights do you use for normal Spent Fuel Pool Lighting? h. Style: drop light or mounted[Stanley, William S (TMI)] Mounted on the wall (NAPS) Mounted lights along the SFP wall. Drop lights if additional lighting is needed. i. Vendor:[Stanley, William S (TMI)] ROS (NAPS) Mounted lights are ROS HP 1000. Drop lights are Master-Lee 2000 watt j. How many:[Stanley, William S (TMI)] Enough to see all fuel assemblies in the SFP (NAPS) We use 3 single head lights + 2 double head inspection lights at the exit of each transfer canal + 1 single head light at the upender end of each transfer canal + 1 single head light in the cask pit area. Drop lights as needed. k. Spacing:[Stanley, William S (TMI)] about 25 feet apart (NAPS) About 25-30 feet apart l. Ballasts: above water or submerged?[Stanley, William S (TMI)] Submerged (NAPS) Submerged 1. What type of underwater lights do you use for normal Reactor Cavity Lighting? m. Style: drop light or mounted[Stanley, William S (TMI)] Temporary mounted lights above core, drop lights at the bottom of the core resting on the core plate. (NAPS) We have wall mounted lights along the cavity wall. We use drop lights in vessel. n. Vendor:[Stanley, William S (TMI)] Unknown (NAPS) ROS HP 1000, Master-Lee 2000 watt drop lights o. How many:[Stanley, William S (TMI)] Two mounted above, one or two in the bottom (NAPS) Cavity 8, Transfer Canal 1. Drop lights are used as needed. We also have ROS HP 1000 core plate lights that are used during core re-load. p. Spacing:[Stanley, William S (TMI)] Mounted lights above core are 180 deg apart (NAPS) Placed as needed. These lights are movable. q. Ballasts: above water or submerged?[Stanley, William S (TMI)] submerged. (NAPS) Above water 1. What type of underwater lights do you use for supplemental lighting? If Necessary. r. If so what would require the additional lighting? (NAPS) Drop lights are used for lighting the top of the core during off-load and also used during on-load to illuminate the tops of the baffles. Additional lighting is also used during any video inspections (FOSAR, etc) if the camera lights do not provide adequate lighting. s. Style: drop light or mounted[Stanley, William S (TMI)] on underwater camera poles (NAPS) Drop lights (Master-Lee 2000 watt or pencil lights 500 watt for below the core plate. t. Vendor:[Stanley, William S (TMI)] (camera) (NAPS) See 5s above u. How many:[Stanley, William S (TMI)] typically dual light (NAPS) As needed v. Spacing: (NAPS) As needed w. Ballasts: above water or submerged?[Stanley, William S (TMI)] submerged. (NAPS) Our drop lights do not have any ballasts. Our core plate lights do have above water ballasts. J. E. Willett ---------------------------------------------------- Joseph E. Willett, P.E. Principal Reactor Engineer-Fuel Nuclear Operations Division E-mail: jwillett(a)oppd.com<mailto:jwillett@oppd.com> Omaha Public Power District Phone: (402) 533-7213 Fort Calhoun Station Pager: (402) 561-3899 9610 Power Lane FAX: (402) 533-6747 Blair, NE 68008 Mail Station: FC-1-1 Plant ---------------------------------------------------- -------- CONFIDENTIALITY NOTICE: This electronic message contains information which may be legally confidential and or privileged and does not in any case represent a firm ENERGY COMMODITY bid or offer relating thereto which binds the sender without an additional express written confirmation to that effect. The information is intended solely for the individual or entity named above and access by anyone else is unauthorized. If you are not the intended recipient, any disclosure, copying, distribution, or use of the contents of this information is prohibited and may be unlawful. If you have received this electronic transmission in error, please reply immediately to the sender that you have received the message in error, and delete it. Thank you.

1 0

Negative Margin to FqN transient Limit.
by Adina K Lafrance 15 Jan '10

15 Jan '10

Our Fleet RM Team would like to know how other sites would classify/grade the following event: During the initial power escalation following a refueling outage, QPTR alarms required a flux map to verify quadrant power tilt and allow for new currents to be installed to clear the alarm. Originally, the hot channel factors surveillance was to be performed at 73% (the next scheduled flux map) but was performed at ~50%. If the 50% map had passed all acceptance criteria, the 73% map would not have been required and all restrictions based on hot channel factors would have been removed all the way to full power; other hold points would have still been required. The power ascension procedure states that the acceptance criteria for the Intermediate Power (40% to 75%) map to be the technical specification on hot channel factors, which references the COLR limit: "Once after each refueling prior to exceeding 75% RATED POWER and every 31 effective full power days thereafter" the FQN transient needs to be confirmed within limits. During the power ascension, it was decided to confirm the FQN transient using the 50% map to allow for power to be increased >75%. FQN transient was determined to be outside the COLR limits, which caused the entry into the TS action statement. The calculated margin was -1.701% based on a measured value with uncertainties of 5.085 compared to the limit of 5.00. As a result, the following actions were required: -Reduce the AFD limits greater than or equal to 1% for each 1% that the FqN transient exceeds its limits within 4 hours after this determination has been made. -Similarly reduce the Power Range Neutron Flux-High Trip Setpoints and Overpower delta-T Trip Setpoints within 72 hours by greater than or equal to 1% that maximum allowable power of the axial flux difference limits is reduced. A WO was made for I&C to make adjustments to the Power Range Neutron Flux-High Trip Setpoints and OPDT Trip Setpoints as specified above. Prior to completing the WO, the flux map at 73% power determined that there was no need to Reduce Overpower Delta T trip setpoints and the WO was canceled. It was noted that the ~50% map was not originally planned and would not have been performed except for the QPTR alarms-instead the 73% would have been performed. 1) How would your site classify the above event in reactivity management space (precursor, incident, event...)? 2) What is the justification for the grading (the example or statement from your procedure with your grading requirements)? Thank you in advance. Adina LaFrance The significant problems we face cannot be solved at the same level of thinking we were at when we created them. -Albert Einstein Nuclear Analysis & Fuel Reactor Engineer Surry Power Station Email: Adina.K.LaFrance(a)Dom.com<mailto:Adina.K.LaFrance@Dom.com> Phone: 757-365-2658 Pager #: 4290 CONFIDENTIALITY NOTICE: This electronic message contains information which may be legally confidential and or privileged and does not in any case represent a firm ENERGY COMMODITY bid or offer relating thereto which binds the sender without an additional express written confirmation to that effect. The information is intended solely for the individual or entity named above and access by anyone else is unauthorized. If you are not the intended recipient, any disclosure, copying, distribution, or use of the contents of this information is prohibited and may be unlawful. If you have received this electronic transmission in error, please reply immediately to the sender that you have received the message in error, and delete it. Thank you.

2 1

Fw: Electronic Benchmarking - Fuel Handling Issues
by ddgoff＠aep.com 14 Jan '10

14 Jan '10

1. Do your stations fuel handling machines require fall protection? One side of the manipulator crane requires fall protection prior to flood up of the refueling cavity. After flood up, a life vest is acceptable. a. If yes, what measures are taken? Netting, harnesses, etc. b. If using netting, where is it attached? c. If using fall protection, where are the tie-offs? There is a cable running the width of the bridge. 2. What are you requirements for fuel movement in the Spent Fuel Pool? Continuous communication capability between the control room and the spent fuel pool bridge, spent fuel pool area supervisor, and fuel transfer system operator. d. Continuous communications with Control Room? If yes, SRO, RO., Other. e. Do you require oversight on the spent fuel handling machine (SRO, RO, Other)? Spent Fuel Pool Area Supervisor. f. Is your procedure Continuous Use, Information Use or Reference Use? The core shuffle physics data sheet is continuous. The rest is reference. g. Do you utilize Vendors? Yes. If so, what additional oversight is required? SRO in containment, Spent Fuel Pool Area Supervisor (reporting to the SRO) at the pool 3. What type of underwater lights do you use for normal Spent Fuel Pool Lighting? ROS h. Style: drop light or mounted Mounted i. Vendor: ROS j. How many: 9 k. Spacing: about 25 feet max. l. Ballasts: above water or submerged? submerged 4. What type of underwater lights do you use for normal Reactor Cavity Lighting? m. Style: drop light or mounted Mounted n. Vendor: Hydro Vision o. How many: 6 p. Spacing: varies q. Ballasts: above water or submerged? N/A 5. What type of underwater lights do you use for supplemental lighting? If Necessary. r. If so what would require the additional lighting? s. Style: drop light or mounted Drop Lights t. Vendor: Master-Lee u. How many: As required v. Spacing: As required w. Ballasts: above water or submerged? N/A Jim Greendonner Refueling Project Manager Cook Nuclear Plant American Electric Power Nuclear Generation Group 269-466-2684

1 0

Re: [Pwrrm] Electronic Benchmarking - Fuel Handling Issues
by Jeffrey A Camp 14 Jan '10

14 Jan '10

From: Rob McAndrew (Generation - 3) Sent: Wednesday, January 13, 2010 10:25 AM To: Jeffrey A Camp (Generation - 3) Subject: FW: Electronic Benchmarking - Fuel Handling Issues From: pwrrm(a)retaqs.com [mailto:pwrrm@retaqs.com] On Behalf Of WILLETT, JOSEPH E Sent: Wednesday, January 13, 2010 9:29 AM To: pwrrm(a)retaqs.com Cc: BUSSEY, TIMOTHY J Subject: [Pwrrm] Electronic Benchmarking - Fuel Handling Issues We apologize for the lengthy list, but we're trying get the year started off right and wrap-up from a late fall outage. Fort Calhoun Station Reactor Engineering is looking to benchmark a few items 1. Do your stations fuel handling machines require fall protection? Only when walking out to the bridge if it isn't parked in it's normal loading location. You put on a life jacket or clip onto the railing wire. The life jacket comes off when you reach the bridge. a. If yes, what measures are taken? Netting, harnesses, etc. b. If using netting, where is it attached? c. If using fall protection, where are the tie-offs? 1. What are you requirements for fuel movement in the Spent Fuel Pool? No continuous communications, various Tech Spec must be verified for ventilation and heavy loads, crane checks, most procedures are continuous use with a peer checker. It depends somewhat on what the evolution is. Vendors are rarely used and only for special ops like reconstitution, not routine fuel movement. d. Continuous communications with Control Room? If yes, SRO, RO., Other. e. Do you require oversight on the spent fuel handling machine (SRO, RO, Other)? f. Is your procedure Continuous Use, Information Use or Reference Use? g. Do you utilize Vendors? If so, what additional oversight is required? 1. What type of underwater lights do you use for normal Spent Fuel Pool Lighting? Wall and drop lights. Don't know the type or vendor. h. Style: drop light or mounted i. Vendor: j. How many: k. Spacing: l. Ballasts: above water or submerged? 1. What type of underwater lights do you use for normal Reactor Cavity Lighting? Wall and drop lights. Plus temporary fixed lights on the flange. m. Style: drop light or mounted n. Vendor: o. How many: p. Spacing: q. Ballasts: above water or submerged? 1. What type of underwater lights do you use for supplemental lighting? If Necessary. Don't know. r. If so what would require the additional lighting? s. Style: drop light or mounted t. Vendor: u. How many: v. Spacing: w. Ballasts: above water or submerged? J. E. Willett ---------------------------------------------------- Joseph E. Willett, P.E. Principal Reactor Engineer-Fuel Nuclear Operations Division E-mail: jwillett(a)oppd.com<mailto:jwillett@oppd.com> Omaha Public Power District Phone: (402) 533-7213 Fort Calhoun Station Pager: (402) 561-3899 9610 Power Lane FAX: (402) 533-6747 Blair, NE 68008 Mail Station: FC-1-1 Plant ---------------------------------------------------- -------- This e-mail contains Omaha Public Power District's confidential and proprietary information and is for use only by the intended recipient. Unless explicitly stated otherwise, this e-mail is not a contract offer, amendment, nor acceptance. If you are not the intended recipient you are notified that disclosing, copying, distributing or taking any action in reliance on the contents of this information is strictly prohibited. CONFIDENTIALITY NOTICE: This electronic message contains information which may be legally confidential and or privileged and does not in any case represent a firm ENERGY COMMODITY bid or offer relating thereto which binds the sender without an additional express written confirmation to that effect. The information is intended solely for the individual or entity named above and access by anyone else is unauthorized. If you are not the intended recipient, any disclosure, copying, distribution, or use of the contents of this information is prohibited and may be unlawful. If you have received this electronic transmission in error, please reply immediately to the sender that you have received the message in error, and delete it. Thank you.

1 0

Re: [Pwrrm] Electronic Benchmarking - Fuel Handling Issues
by William.Stanley＠exeloncorp.com 13 Jan '10

13 Jan '10

Answers interleaved below. Bill Stanley TMI Reactor Engineering 717 948 8695 -----Original Message----- From: Mahgerefteh, Moussa:(GenCo-Nuc) Sent: 13 January 2010 13:59 To: Stanley, William S (TMI):(GenCo-Nuc) Subject: FW: [Pwrrm] Electronic Benchmarking - Fuel Handling Issues Mr. Stanley, Do you mind answering these questions. Moussa _____ From: pwrrm(a)retaqs.com [mailto:pwrrm@retaqs.com] On Behalf Of WILLETT, JOSEPH E Sent: Wednesday, January 13, 2010 9:29 AM To: pwrrm(a)retaqs.com Cc: BUSSEY, TIMOTHY J Subject: [Pwrrm] Electronic Benchmarking - Fuel Handling Issues We apologize for the lengthy list, but we're trying get the year started off right and wrap-up from a late fall outage. Fort Calhoun Station Reactor Engineering is looking to benchmark a few items 1. Do your stations fuel handling machines require fall protection? [Stanley, William S (TMI)] Yes, while getting on or off the bridge. Don't need fall protection once actually on the bridge, unless there is a need to climb off the normal walking paths (to check brakes and cables, for example). a. If yes, what measures are taken? Netting, harnesses, etc.[Stanley, William S (TMI)] Life vests or climbing harnesses may be used to get to the bridge. No nets b. If using netting, where is it attached?[Stanley, William S (TMI)] N/A c. If using fall protection, where are the tie-offs?[Stanley, William S (TMI)] Tie-off for the climbing harness is a cable along the walkway to the bridge. When climbing on the bridge, tie-off is to bridge structure. 2. What are you requirements for fuel movement in the Spent Fuel Pool? d. Continuous communications with Control Room? If yes, SRO, RO., Other.[Stanley, William S (TMI)] Fuel movement in SFP requires initial approval by the Control Room, but NOT continuous communication during movement. During refueling (offload/reload), the SF bridge crew is in continuous communication w/ the FH SRO, who is stationed in the Reactor Building on the Main Fuel Handling Bridge, and the Control Room (RO) who is directing the move sequence. e. Do you require oversight on the spent fuel handling machine (SRO, RO, Other)?[Stanley, William S (TMI)] For "isolated" SFP operations, SRO supervises movements. f. Is your procedure Continuous Use, Information Use or Reference Use?[Stanley, William S (TMI)] Continuous use. g. Do you utilize Vendors? If so, what additional oversight is required?[Stanley, William S (TMI)] During refueling outages, bridges are operated by mix of vendor and company personnel (company personnel are part of the Reactor Services group, who travel from plant to plant for outages). Company personnel provide oversight. 3. What type of underwater lights do you use for normal Spent Fuel Pool Lighting? h. Style: drop light or mounted[Stanley, William S (TMI)] Mounted on the wall i. Vendor:[Stanley, William S (TMI)] ROS j. How many:[Stanley, William S (TMI)] Enough to see all fuel assemblies in the SFP k. Spacing:[Stanley, William S (TMI)] about 25 feet apart l. Ballasts: above water or submerged?[Stanley, William S (TMI)] Submerged 4. What type of underwater lights do you use for normal Reactor Cavity Lighting? m. Style: drop light or mounted[Stanley, William S (TMI)] Temporary mounted lights above core, drop lights at the bottom of the core resting on the core plate. n. Vendor:[Stanley, William S (TMI)] Unknown o. How many:[Stanley, William S (TMI)] Two mounted above, one or two in the bottom p. Spacing:[Stanley, William S (TMI)] Mounted lights above core are 180 deg apart q. Ballasts: above water or submerged?[Stanley, William S (TMI)] submerged. 5. What type of underwater lights do you use for supplemental lighting? If Necessary. r. If so what would require the additional lighting? s. Style: drop light or mounted[Stanley, William S (TMI)] on underwater camera poles t. Vendor:[Stanley, William S (TMI)] (camera) u. How many:[Stanley, William S (TMI)] typically dual light v. Spacing: w. Ballasts: above water or submerged?[Stanley, William S (TMI)] submerged. J. E. Willett ---------------------------------------------------- Joseph E. Willett, P.E. Principal Reactor Engineer-Fuel Nuclear Operations Division E-mail: jwillett(a)oppd.com Omaha Public Power District Phone: (402) 533-7213 Fort Calhoun Station Pager: (402) 561-3899 9610 Power Lane FAX: (402) 533-6747 Blair, NE 68008 Mail Station: FC-1-1 Plant ---------------------------------------------------- -------- This e-mail contains Omaha Public Power District's confidential and proprietary information and is for use only by the intended recipient. Unless explicitly stated otherwise, this e-mail is not a contract offer, amendment, nor acceptance. If you are not the intended recipient you are notified that disclosing, copying, distributing or taking any action in reliance on the contents of this information is strictly prohibited. ----------------------------------------- ************************************************** This e-mail and any of its attachments may contain Exelon Corporation proprietary information, which is privileged, confidential, or subject to copyright belonging to the Exelon Corporation family of Companies. This e-mail is intended solely for the use of the individual or entity to which it is addressed. If you are not the intended recipient of this e-mail, you are hereby notified that any dissemination, distribution, copying, or action taken in relation to the contents of and attachments to this e-mail is strictly prohibited and may be unlawful. If you have received this e-mail in error, please notify the sender immediately and permanently delete the original and any copy of this e-mail and any printout. Thank You. **************************************************

1 0

William V Ferguson is out of the office.
by wvferguson＠aep.com 13 Jan '10

13 Jan '10

I will be out of the office starting 01/08/2010 and will not return until 01/18/2010. I will respond to your message when I return.

1 0

2025

2024

2023

2022

2021

2020

2019

2018

2017

2016

2015

2014

2013

2012

2011

2010

2009

2008

2007

2006

2005

PWRRM January 2010