PWRRM January 2007

pwrrm@retaqs.com

6 participants
5 discussions

Re: [Respvr] Question on Power Range NI Replacement
by Bob_Tomonto＠fpl.com 31 Jan '07

31 Jan '07

Michael, We often have to replace power range detectors during refueling outages. Turkey Point has a history of water leakage into the excore detector wells resulting in degradation to the excore detectors. We recently changed to titanium housed detectors on the intermediate range and power range detectors to improve the lifetime (more corrosion resistant). Procedurally we require the Power Range High Flux Trip setpoint to be set at 55% and only after acceptable NIS Calibration of all the detectors (as developed from a flux map at 48%), do we reset the high flux trip setpoint to 108%. If I can be of any help, please do not hesitate to call me at (305) 246-7327. Bob Tomonto FPL Turkey Point Reactor Engineering Michael_Fanguy@do m.com To: respvr(a)keffective.com, pwrrm(a)keffective.com Sent by: cc: Robert_A._Wright(a)dom.com respvr-bounces@re Subject: [Respvr] Question on Power Range NI Replacement taqs.com 01/31/2007 07:38 AM Please respond to "RE Supervisors" This email is being sent out for North Anna Reactor Engineering. North Anna (3 loop Westinghouse) is planning to replace a PRNI in their next outage. The question is do other utilities put any special measure in place for startup due to the new detector? Are your Hi Flux Trips extremely low? Is the startup performed with the NI channel in TRIP? Any feedback would be appreciated. Please send your responses to Robert_A._Wright(a)dom.com. Nuclear Analysis & Fuel Lead Reactor Engineer Surry Power Station Email: Michael_Fanguy(a)Dom.com Phone: 757-365-2155 Pager #: 3453 ----------------------------------------- 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. _______________________________________________ Respvr mailing list Respvr(a)retaqs.com http://www.keffective.com/mailman/listinfo/respvr

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Question on Power Range NI Replacement
by Michael_Fanguy＠dom.com 31 Jan '07

31 Jan '07

This email is being sent out for North Anna Reactor Engineering. North Anna (3 loop Westinghouse) is planning to replace a PRNI in their next outage. The question is do other utilities put any special measure in place for startup due to the new detector? Are your Hi Flux Trips extremely low? Is the startup performed with the NI channel in TRIP? Any feedback would be appreciated. Please send your responses to Robert_A._Wright(a)dom.com. Nuclear Analysis & Fuel Lead Reactor Engineer Surry Power Station Email: Michael_Fanguy(a)Dom.com Phone: 757-365-2155 Pager #: 3453 ----------------------------------------- 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.

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FW: [Pwrrm] Reactor Power Control, Expectaions and Performance
by BELL, WILLIAM H 15 Jan '07

15 Jan '07

Joseph: The following is the V. C. Summer Station response to your questions: 1) What are other plants goals/expectations for maintaining power level? (=/- MW or goal); How easy is it to maintain? Is there a band within which you operate? The attached file Ops @ the Licensed Limit.doc contains the guidance our operators use for maintaining reactor power as close to the licensed limit (2900 MWT) as practicable. I have also included a 24 hour plot of data that illustrates our reactor power and feedwater flow rate. As you will see we typically have minute to minute swings in feedwater flow rate based calculated reactor power in the range of 3 to 5 MWT. 2) How is your secondary calculation performed? (Averaging Inputs, Instantaneous values, combination) Is it a module or program on you plant computer or is it an off-line routine? Our calorimetric power calculation is feedwater flow rate based. Our new plant process computer now performs this calculation once a second. However, many of the inputs are one minute average values of one second instantaneous values. The one minute averaging is a holdover from our old (slow) computer that we have had no reason to change. The calculation does not need to be performed at a one second rate but we do it anyway because our new computer can easily handle it. 3) Are your temperature and flow transmitters set specifically for this calculation? (dampening or bias settings) All of the instruments that provide input to the calorimetric are calibrated once every 18 months. Most also undergo quarterly Op tests. However, the instruments themselves have no special dampening or bias settings. All averaging is done by the plant computer. 4) Are any of your control loops (Feedwater) used in the secondary calorimetric calculation? Our feedwater flow rate transmitters used by the calorimetric computer program also provide protection and control functions as well. The steam generator level control system uses these transmitters as does our reactor protection system. 5) Have you had any issues related to power swings or related to your secondary calorimetric? Yes. As you can see in the attached plot of power and feedwater flow rate we occasionally encounter spikes in feed flow in our A loop. We are currently trying to understand the cause of these spikes but so far the solution eludes us. Bill Bell Chemical Engineer Reactor Engineering V. C. Summer Station 803-345-4389 ________________________________ From: pwrrm-bounces(a)retaqs.com [mailto:pwrrm-bounces@retaqs.com] On Behalf Of WILLETT, JOSEPH E Sent: Wednesday, January 10, 2007 4:01 PM To: pwrrm(a)retaqs.com Cc: BLESSIE, WILLIAM J Subject: [Pwrrm] Reactor Power Control, Expectaions and Performance Fort Calhoun Station is currently experiencing 3-5 MWth swings (peak-to-peak) in a one hour period to on our secondary calorimetric calculation. This last outage we replaced both S/Gs and refurbished our FW regulation valves. Prior to this outage our swings were normally 1 MW over 4 hour period. We attempt to keep power at a corporate goal of 1498 MWth (1500 MWth is our rated power level). We do not see these swings on the NI or Delta-T power indications that follow the secondary calorimetric swings. We have not implemented Appendix K using ultrasonic flow measurement for feedwater as of yet. Our Question(s) 1) What are other plants goals/expectations for maintaining power level? (=/- MW or goal); How easy is it to maintain? Is there a band within which you operate? 2) How is your secondary calculation performed? (Averaging Inputs, Instantaneous values, combination) Is it a module or program on you plant computer or is it an off-line routine? 3) Are your temperature and flow transmitters set specifically for this calculation? (dampening or bias settings) 4) Are any of your control loops (Feedwater) used in the secondary calorimetric calculation? 5) Have you had any issues related to power swings or related to your secondary calorimetric? J. E. Willett "Only those who will risk going too far can possibly find out how far one can go." T.S. Eliot (1888-1965) ---------------------------------------------------- Joseph E. Willett, P.E. Principal Reactor Engineer, Nuclear Operations E-mail: jwillett(a)oppd.com <mailto:jwillett@oppd.com%20> OR Joseph_Willett(a)hotmail.com <mailto:jwillett@uswest.net%20> Omaha Public Power District Phone: (402) 533-7213 P.O. Box 399 Pager: (402) 561-3899 Ft. Calhoun, NE 68023-0390 FAX: (402) 533-6747 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. _______________________________________________ PWRRM mailing list PWRRM(a)retaqs.com http://www.keffective.com/mailman/listinfo/pwrrm

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Reactor Power Control, Expectaions and Performance
by WILLETT, JOSEPH E 11 Jan '07

11 Jan '07

Fort Calhoun Station is currently experiencing 3-5 MWth swings (peak-to-peak) in a one hour period to on our secondary calorimetric calculation. This last outage we replaced both S/Gs and refurbished our FW regulation valves. Prior to this outage our swings were normally 1 MW over 4 hour period. We attempt to keep power at a corporate goal of 1498 MWth (1500 MWth is our rated power level). We do not see these swings on the NI or Delta-T power indications that follow the secondary calorimetric swings. We have not implemented Appendix K using ultrasonic flow measurement for feedwater as of yet. Our Question(s) 1) What are other plants goals/expectations for maintaining power level? (=/- MW or goal); How easy is it to maintain? Is there a band within which you operate? 2) How is your secondary calculation performed? (Averaging Inputs, Instantaneous values, combination) Is it a module or program on you plant computer or is it an off-line routine? 3) Are your temperature and flow transmitters set specifically for this calculation? (dampening or bias settings) 4) Are any of your control loops (Feedwater) used in the secondary calorimetric calculation? 5) Have you had any issues related to power swings or related to your secondary calorimetric? J. E. Willett "Only those who will risk going too far can possibly find out how far one can go." T.S. Eliot (1888-1965) ---------------------------------------------------- Joseph E. Willett, P.E. Principal Reactor Engineer, Nuclear Operations E-mail: jwillett(a)oppd.com <mailto:jwillett@oppd.com%20> OR Joseph_Willett(a)hotmail.com <mailto:jwillett@uswest.net%20> Omaha Public Power District Phone: (402) 533-7213 P.O. Box 399 Pager: (402) 561-3899 Ft. Calhoun, NE 68023-0390 FAX: (402) 533-6747 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.

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RE: [Pwrrm] Reactor Power Control, Expectaions and Performance
by ALDAY, CLINT L 11 Jan '07

11 Jan '07

1. 99.98%. We find it very easy to operate there and normally maintain based on a twenty minute smoothed value (automatically calculated by COLSS). 2. Combination. We use COLSS (Core Operating Limits Supervisory System) which calculates secondary calorimetric every thirty seconds and primary calorimetric every second. Turbine first stage pressure power is also updated once per second. 3. Don't know. 4. No. 5. No. Clint Alday Waterford 3 -----Original Message----- From: pwrrm-bounces(a)retaqs.com [mailto:pwrrm-bounces@retaqs.com] On Behalf Of WILLETT, JOSEPH E Sent: Wednesday, January 10, 2007 3:01 PM To: pwrrm(a)retaqs.com Cc: BLESSIE, WILLIAM J Subject: [Pwrrm] Reactor Power Control, Expectaions and Performance Fort Calhoun Station is currently experiencing 3-5 MWth swings (peak-to-peak) in a one hour period to on our secondary calorimetric calculation. This last outage we replaced both S/Gs and refurbished our FW regulation valves. Prior to this outage our swings were normally 1 MW over 4 hour period. We attempt to keep power at a corporate goal of 1498 MWth (1500 MWth is our rated power level). We do not see these swings on the NI or Delta-T power indications that follow the secondary calorimetric swings. We have not implemented Appendix K using ultrasonic flow measurement for feedwater as of yet. Our Question(s) 1) What are other plants goals/expectations for maintaining power level? (=/- MW or goal); How easy is it to maintain? Is there a band within which you operate? 2) How is your secondary calculation performed? (Averaging Inputs, Instantaneous values, combination) Is it a module or program on you plant computer or is it an off-line routine? 3) Are your temperature and flow transmitters set specifically for this calculation? (dampening or bias settings) 4) Are any of your control loops (Feedwater) used in the secondary calorimetric calculation? 5) Have you had any issues related to power swings or related to your secondary calorimetric? J. E. Willett "Only those who will risk going too far can possibly find out how far one can go." T.S. Eliot (1888-1965) ---------------------------------------------------- Joseph E. Willett, P.E. Principal Reactor Engineer, Nuclear Operations E-mail: jwillett(a)oppd.com <mailto:jwillett@oppd.com%20> OR Joseph_Willett(a)hotmail.com <mailto:jwillett@uswest.net%20> Omaha Public Power District Phone: (402) 533-7213 P.O. Box 399 Pager: (402) 561-3899 Ft. Calhoun, NE 68023-0390 FAX: (402) 533-6747 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.

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PWRRM January 2007