|
---|
Category:- No Document Type Applies
MONTHYEARML23108A2202023-04-13013 April 2023 Attachment: Table 1 RV-1 Relief Valve Descriptions ML20196L8282020-07-14014 July 2020 Relief Request 1A4-1, Reactor Vessel (Rv) Upper Head Examinations ML20184A0112020-07-0202 July 2020 July 7, 2020, Teleconference Regarding NRC Observations on the June 24, 2020, License Amendment Request to Make a One-Time Change to Technical Specification 3.7.19, Safety Chilled Water ML16014A7352015-12-0808 December 2015 Certificate of Liability Insurance ML15014A1532015-01-14014 January 2015 Attachment 1- NEI Comments on NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML15014A1602015-01-14014 January 2015 Attachment 2 - NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML14027A7052013-12-17017 December 2013 Comanche Peak Responses to LAR 13-01 Request for Additional Information (RAI) - Round 2 ML13169A1342013-06-13013 June 2013 ISFSI - Enclosure 7 to TXX-13095 - Additional Documentation for Energy Future Holdings Corporation, and Enclosures 8, 9B, 10, 11 and 12. Part 2 of 2 ML13079A2472013-03-18018 March 2013 Discussion of NRC Requirements for Water Inventory Needed to Maintain Safety of Comanche Peak Nuclear Power Plant 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 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 ML0806704192008-03-0707 March 2008 CDBI Findings ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions 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 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 ML0634705992006-12-14014 December 2006 Plant Service List ML0702304022006-10-10010 October 2006 Description of Pictures Txu Comanche Peak Ses Report #06-0413 ML0617301642006-06-30030 June 2006 Enclosure 4: CPSES Comments on and Input to NRC Draft Trip Report ML0702303902006-04-13013 April 2006 Keeler Long DBA Testing of Coating Supplies ML0404104922004-02-20020 February 2004 Order EA-03-009 Service List ML0505404642004-02-0909 February 2004 Dynamic Web Page Printout Dated 02/09/2004 Regarding Applied Violations for Nuclear Power Plants ML0329401042003-10-0707 October 2003 Riv Backfit Status ML0325214292003-08-20020 August 2003 Westinghouse - Nuclear Safety Advisory Letter NSAL-03-6, High Net Heat Input, Dated 08/20/2003 ML0329400982003-03-27027 March 2003 Riv Backfit Status 2023-04-13
[Table view] |
Text
JULY 7, 2020, TELECONFERENCE REGARDING NRC OBSERVATIONS ON THE JUNE 24, 2020, LICENSE AMENDMENT REQUEST TO MAKE A ONE-TIME CHANGE TO TECHNICAL SPECIFICATION 3.7.19, "SAFETY CHILLED WATER" VISTRA OPERATIONS COMPANY LLC COMANCHE PEAK UNIT 1 AND 2 DOCKET NOS. 50-445 AND 50-446 By , Safety Chilled Water|letter dated June 24, 2020]] (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20176A281), Vistra Operations Company LLC (the licensee) submitted a license amendment request (LAR) for Nuclear Regulatory Commission (NRC) approval for an amendment to the facility operating license for the Comanche Peak Nuclear Power Plant, Units 1 and 2 (Comanche Peak). The proposed amendment would revise Technical Specification (TS) 3.7.19, "Safety Chilled Water," Condition A, One safety chilled water train inoperable, to add new required action A.2 with a 7-day completion time. This one-time change is to allow the replacement of the Comanche Peak Unit 2 Safety Chiller 2-06 compressor. The Nuclear Regulatory Commission (NRC) staff is conducting an acceptance review of the LAR and has identified the following observations/potential issues.
SCPB
Enclosure, Section 3.6, states that Comanche Peak would not enter the one-time extended COMPLETION TIME if severe weather is anticipated. The NRC staff notes that this is one of the recommended compensatory measures for other allowed outage time extensions (see NUREG-0800, Standard Review Plan, Branch Technical Position 8-8, Onsite (Emergency Diesel Generators) And Offsite Power Sources Allowed Outage Time Extensions).
APLC LAR Enclosure Section 3.5.3, Avoidance of Risk Significant Plant Configurations, states that the dominant impact of the above scenarios on critical safety functions is the loss of heat removal from the Steam Generators due to failure of all the auxiliary feedwater pumps (random or induced) or loss of room cooling to the motor driven pumps.
STSB