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MONTHYEARML20253A0092020-09-0202 September 2020 NRC-2020-000291/000292 - Resp 1 - Final, Agency Records Subject to the Request Are Enclosed ML20162A0472020-06-0303 June 2020 NRC-2020-000181 - Resp 1 - Final. Agency Records Subject to the Request Are Enclosed ML19261A0962019-09-12012 September 2019 NRC-2019-000288 - Resp 1 - Final, Agency Records Subject to the Request Are Enclosed (Decommissioning Funding Status Reports & Related Information) ML19261A1172019-09-12012 September 2019 NRC-2019-000288 - Resp 1 - Final, Agency Records Subject to the Request Are Enclosed (Spot Check SONGS 2 and 3 - 2008) ML18192A3912018-07-11011 July 2018 Restated Articles of Incorporation Are Executed Pursuant to the Provisions of Section 32 of Chapter 64, Laws 1975, Being Section 51-26-7 N,M.S.A. 1953, as Amended ML18192A4032018-07-11011 July 2018 Study Case 1986 MX-S3 ML18192B8112018-07-11011 July 2018 Prospectus, Employee Stock Purchase Plan of Southern California Edison Company ML17207A1002017-07-26026 July 2017 FAQ 17-02: Palo Verde Unit 3 Scram (Final NRC Response) ML17030A3232017-01-30030 January 2017 LTR-17-0038-1-Ticket - Roy Mathew, E-mail 2.206 Petition on Palo Verde Nuclear Generating Station, Unit 3 - Issuance of Amendment Nos. 199 and 200 Revision to Technical Specification 3.8.1, AC Alternating Current Source-Operating ML17026A3122017-01-23023 January 2017 LTR-17-0038-Ticket Roy Mathew, E-mail 2.206 Petition on Palo Verde Nuclear Generating Station, Unit 3 - Issuance of Amendment Nos. 199 and 200 Revision to Technical Specification 3.8.1, AC Alternating Current Source-Operating ML16054A0072016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Final Response #2, Records Already Publicly Available ML16054A0132016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed. Part 5 of 8 ML16054A0122016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed. Part 4 of 8 ML16054A0102016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed. Part 2 of 8 ML16054A0092016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed. Part 8 of 8 ML16054A0152016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed. Part 7 of 8 ML16054A0082016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed. Part 1 of 8 ML16054A0142016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed. Part 6 of 8 ML16054A0112016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed. Part 3 of 8 ML15252A1112015-09-11011 September 2015 Newspaper Notice, Exigent License Amendment Request to Amend Technical Specification Surveillance Requirement 3.1.5.3 for Control Element Assembly 88 for the Remainder of Cycle 19 ML15014A1602015-01-14014 January 2015 Attachment 2 - NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML15014A1532015-01-14014 January 2015 Attachment 1- NEI Comments on NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML15027A1232014-12-19019 December 2014 Technical Specification (TS) Bases Revision 61, Replacement Pages and Insertion Instructions ML13273A2282013-09-27027 September 2013 FOIA/PA-2013-0329 - Resp - 1 - Final. Group a, Records Already Publicly Available. ML13015A2562012-12-17017 December 2012 Draft Submittal February 2013 FLEX Integrated Plan - Palo Verde ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML1127100332011-09-28028 September 2011 ROP Tabletop Examples and Results ML1027102822010-09-27027 September 2010 Draft Supplemental Information Required ML1019304602010-03-25025 March 2010 List of Historical Leaks and Spills at Us Commercial Nuclear Power Plants ML0906500232009-03-0606 March 2009 Safety Culture Policy Statement (Safety & Security) Comments ML0814805442008-05-23023 May 2008 Comments on Draft IP95003, IMC0305 and Lesson Learned Recommendations ML0808000362008-03-13013 March 2008 List of Attendees, 03/13/2008 Summary of Meeting with Eight Operating Nuclear Power Plant Licensees to Discuss Emerging Metallurgical Issues Certain Welds in Reactor Coolant System for Pressurized-Water Reactors ML0811305312008-02-15015 February 2008 Post Reg. Conference Reference Material - Simulator Review of JPM EP009-CR-001. ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions ML0729205572007-10-17017 October 2007 EA-07-162, Arizona Public Service Company, Confirmatory Order Modifying License (Effective Immediately) Office of Investigations Report No. 4-2007-009, Consent and Hearing Waiver Form ML0729205382007-10-16016 October 2007 IA-07-039, Mr. Mark Sharp, Confirmatory Order, NRC Office of Investigation Report No. 4-2007-009, Consent and Hearing Waiver Form ML0726303192007-09-14014 September 2007 P. Paquin Ltr Amendment to Certificate of Compliance No. 6574 for the Model No. 3-82B Package (TAC L24116)/ Register User List ML0726301142007-09-14014 September 2007 / P. Paquin Ltr Amendment to Certificate of Compliance No. 9208 for the Model No. 10-142B Package (TAC L24117)/S121170 ML0634705992006-12-14014 December 2006 Plant Service List ML0627201202006-09-29029 September 2006 Management Directive 8.3 Evaluation for Palo Verde Nuclear Generating Station (PV 06-19) ML0626503122006-09-0101 September 2006 Liquid Radiation Release Lessons Learned Task Force Final Report (Enclosure) ML0532204562005-11-15015 November 2005 Table Titled Palo Verde Unit 2 - June 14, 2004 Loss of Offsite Power Event - June 24, 2004 (8:04am) ML0532504172005-11-15015 November 2005 Preliminary Issue List, with Handwritten Notes ML0532504152005-11-15015 November 2005 Preliminary Issue List ML0532501252005-11-15015 November 2005 AIT Status ML0532204572005-11-15015 November 2005 Table Titled Palo Verde Unit 2 - June 14, 2004 Loss of Offsite Power Event - June 25, 2004 (9:49) ML0531300702005-11-0202 November 2005 Fault Description Document ML0531300792005-11-0202 November 2005 Loop Risk Assessment ML0613105192005-08-0101 August 2005 PV-08-2005-Outline Comments ML1015400272005-04-27027 April 2005 APS 2005a Palo Verde Nuclear Generating Station 2004 Air Emissions Inventory. PVNGS (1-1-PV-241) 2020-09-02
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UNIT 1 LETDOWN/NC FSL-613 ISSUE NC flow switch NCN-FSL-613 senses low NC flow, or essentially no NC flow, through the heat exchanger and sends an isolation signal to CVCS system valve CH-523. The purpose of the signal is to isolate CH system flow upon a complete loss of NC system flow and prevent un-cooled letdown process fluid from flowing downstream of the letdown heat exchanger. The CH system components of particular concern are the CH purification ion exchangers. Three redundant non-safety related means for protection of the ion exchangers are provided:
- 1) by divert valve CH-520 which receives a signal from CHT-224 on high CH temperature to bypass flow around the ion exchangers.
- 2) CHT-224 also sends an isolation signal to the letdown back pressure control valves, CH-201P and CH-201Q, on high CH temperature when these valves are
- being controlled in AUTO.
- 3) closure of CH-523 on low/no NC flow to the letdown heat exchanger Over the past several years, Unit 1 has experienced CVCS letdown isolation events initiated by NC flow switch NCN-FSL-613. The isolation events have occurred during the cooler months when the NC fluid temperature is low and the NC letdown heat exchanger outlet valve is controlling near its closed position. In addition, there are indications that the NCN-FSL-613 flow switch is isolating at flow rates above the required setpoint of 39 gpm. The combination of these two conditions results in inadvertent isolation of letdown flow due to the generation of the isolation signal to valve CH-523. T-Mod 2594804 was installed to address the inadvertent letdown isolation events. This T-Mod installed a "jumper" around the NC flow switch such that the isolation signal would not be sent to valve CH-523. The T-Mod recognized that two of the original three redundant means existed to isolate CH flow on high temperature via the divert signal to CH-520 and the isolation signal to CH-201P/Q. However, the T-Mod did not explicitly address the fact that CH-201P/Q must be in AUTO mode to receive the isolation signal.
During the LOOP event, the NC system pumps lost power and NC flow through the letdown heat exchanger ceased. No isolation signal was received by CH-523 due to the T-Mod installed "jumper" on the NCN-FSL-613 switch. The NQR control system for CH-201P/Q briefly lost power and then powered up again on backup power. However, the control system automatically reverts to manual control when it initially powers up from a loss of power condition. Since CH-201P/Q were operating in manual mode, not AUTO, the valves did not receive the AUTO mode only isolation interlock from CHT-224. Therefore, letdown flow was not isolated. However, valve CH-520 did receive the divert signal from CHT-224 and the hot CH flow stream was by-passed around the purification ion exchangers. Subsequent review has concluded that no significant degradation was experienced by any other CH system piping/components located downstream of the letdown heat exchanger.
Letdown did not isolate automatically in Unit 1 during the LOOP event because 1) the T-mod removed one of the 3 original means to protect the ion exchangers and 2) per design, the loss of power caused the CH-201 P/Q controller to revert to manual control. It must
UNIT 1 LETDOWN/NC FSL-613 ISSUE be noted that the loss of power causing the CH-201 P/Q controller to revert to manual control exists with or without the T-mod on FSL-613.
The evaluation/justification for the T-mod around FSL-613 did not explicitly address or acknowledge the design of the CH-201 P/Q controller upon loss of power. It simply acknowledged that redundant means for isolation of letdown/protection of the ion exchangers continued to exist even with the removal of the FSL-613 auto closure of CH-523. All of the interlocks are non-safety related. Since the UFSAR description of these interlocks does not explicitly address how the CH-201 P/Q controller behaves in a loss of power scenario, it is not unreasonable that the T-mod evaluation did not evaluate explicitly how the two remaining means for letdown isolation/ion exchanger protection would behave under various scenarios such as a loss of power. Since all of the interlocks are non-safety related, there are several failures and scenarios that would result in a failure to automatically isolate letdown. Operators are trained during control room simulations to respond to plant events given a variety of equipment failures and scenarios. During the LOOP event, the Operators in Unit 1 correctly responded to the high temperature condition at the outlet of the letdown heat exchanger by manually isolating letdown.