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Category:Letter type:DCL
MONTHYEARDCL-24-103, Pg&Es Voluntary Submittal of Information Related to 10 CFR 2.206 Petition Regarding Seismic Core Damage Frequency for DCPP, Units 1 and 22024-10-24024 October 2024 Pg&Es Voluntary Submittal of Information Related to 10 CFR 2.206 Petition Regarding Seismic Core Damage Frequency for DCPP, Units 1 and 2 DCL-24-092, Supplement and Annual Update License Renewal Application, Amendment 12024-10-14014 October 2024 Supplement and Annual Update License Renewal Application, Amendment 1 DCL-24-098, Material Status Report for the Period Ending August 31, 20242024-10-0909 October 2024 Material Status Report for the Period Ending August 31, 2024 DCL-24-091, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation2024-10-0303 October 2024 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation DCL-24-087, License Renewal - Historic and Cultural Resources Reference Documents (Redacted)2024-09-12012 September 2024 License Renewal - Historic and Cultural Resources Reference Documents (Redacted) DCL-24-083, CFR Part 21 Notification: Commercially Dedicated Snubber Valve Not Properly Heat Treated2024-09-0909 September 2024 CFR Part 21 Notification: Commercially Dedicated Snubber Valve Not Properly Heat Treated DCL-24-078, Pre-Notice of Disbursement from Decommissioning Trust2024-09-0303 September 2024 Pre-Notice of Disbursement from Decommissioning Trust DCL-24-082, Decommissioning Draft Biological Assessment and Draft Essential Fish Habitat Assessment2024-08-28028 August 2024 Decommissioning Draft Biological Assessment and Draft Essential Fish Habitat Assessment DCL-24-077, Responses to NRC Requests for Additional Information on Diablo Canyon Power License Renewal Application Severe Accident2024-08-15015 August 2024 Responses to NRC Requests for Additional Information on Diablo Canyon Power License Renewal Application Severe Accident DCL-24-075, Response to Request for Additional Information for License Amendment Request 23-02, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power React2024-08-0808 August 2024 Response to Request for Additional Information for License Amendment Request 23-02, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power React DCL-24-079, DC-2024-07 Post Exam Comments Analysis2024-08-0202 August 2024 DC-2024-07 Post Exam Comments Analysis DCL-24-070, License Amendment Request 24-03 Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2024-07-31031 July 2024 License Amendment Request 24-03 Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies DCL-24-071, Core Operating Limits Report for Unit 2 Cycle 252024-07-22022 July 2024 Core Operating Limits Report for Unit 2 Cycle 25 DCL-2024-523, Submittal of Report on Discharge Self-Monitoring2024-07-18018 July 2024 Submittal of Report on Discharge Self-Monitoring DCL-2024-527, Sea Turtle Stranding Report (Loggerhead Sea Turtle) Diablo Canyon Power Plant2024-07-0101 July 2024 Sea Turtle Stranding Report (Loggerhead Sea Turtle) Diablo Canyon Power Plant DCL-24-066, Request to Extend the Nrg Approval of Alternative for Use of Full Structural Weld Overlay, REP-RHR-SWOL2024-06-27027 June 2024 Request to Extend the Nrg Approval of Alternative for Use of Full Structural Weld Overlay, REP-RHR-SWOL DCL-24-052, Responses to NRC Requests for Additional Information on the Diablo Canyon Power Plant License Renewal Application Environmental Report2024-05-16016 May 2024 Responses to NRC Requests for Additional Information on the Diablo Canyon Power Plant License Renewal Application Environmental Report DCL-24-051, One Hundred Eighty Day Steam Generator Report for Twenty-Fourth Refueling Outage2024-05-0808 May 2024 One Hundred Eighty Day Steam Generator Report for Twenty-Fourth Refueling Outage DCL-24-049, 2023 Annual Radiological Environmental Operating Report2024-05-0101 May 2024 2023 Annual Radiological Environmental Operating Report DCL-24-047, 2023 Annual Non-radiological Environmental Operating Report2024-05-0101 May 2024 2023 Annual Non-radiological Environmental Operating Report DCL-24-048, O CFR 50.59 and 1 O CFR 72.48 Summary Report for the Period of January 1, 2022, Through December 31, 20232024-04-30030 April 2024 O CFR 50.59 and 1 O CFR 72.48 Summary Report for the Period of January 1, 2022, Through December 31, 2023 DCL-24-027, 2023 Annual Radioactive Effluent Release Report2024-04-28028 April 2024 2023 Annual Radioactive Effluent Release Report DCL-24-045, Annual Report of Occupational Radiation Exposure for 20232024-04-24024 April 2024 Annual Report of Occupational Radiation Exposure for 2023 DCL-24-042, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-04-17017 April 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations DCL-24-022, Notification of Changes to Decommissioning Schedule2024-04-0202 April 2024 Notification of Changes to Decommissioning Schedule DCL-24-023, Revised Certification of Permanent Cessation of Power Operations2024-04-0202 April 2024 Revised Certification of Permanent Cessation of Power Operations DCL-24-031, Decommissioning Funding Report2024-03-27027 March 2024 Decommissioning Funding Report DCL-24-032, 2024 Annual Statement of Insurance for Pacific Gas and Electric Company’S Diablo Canyon Power Plant2024-03-27027 March 2024 2024 Annual Statement of Insurance for Pacific Gas and Electric Company’S Diablo Canyon Power Plant DCL-24-028, Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.0.3, Limiting Condition for Operation Applicability2024-03-21021 March 2024 Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.0.3, Limiting Condition for Operation Applicability DCL-24-018, License Amendment Request 24-01 Revision to Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2024-02-28028 February 2024 License Amendment Request 24-01 Revision to Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) DCL-2024-507, 2023 Annual Report on Discharge Self-Monitoring2024-02-27027 February 2024 2023 Annual Report on Discharge Self-Monitoring DCL-24-020, Nuclear Material Transaction Report for New Fuel2024-02-21021 February 2024 Nuclear Material Transaction Report for New Fuel DCL-24-014, Owners Activity Report for Unit 1 Twenty-Fourth Refueling Outage2024-02-12012 February 2024 Owners Activity Report for Unit 1 Twenty-Fourth Refueling Outage DCL-24-013, Nuclear Material Transaction Report for New Fuel2024-02-0707 February 2024 Nuclear Material Transaction Report for New Fuel DCL-24-010, Nuclear Material Transaction Report for New Fuel2024-01-29029 January 2024 Nuclear Material Transaction Report for New Fuel DCL-2024-502, 2023 Annual Sea Turtle Report for Diablo Canyon Power Plant (DCPP)2024-01-25025 January 2024 2023 Annual Sea Turtle Report for Diablo Canyon Power Plant (DCPP) DCL-2024-501, Sea Turtle Stranding Report (Green Sea Turtle)2024-01-24024 January 2024 Sea Turtle Stranding Report (Green Sea Turtle) DCL-2024-500, Transmittal of the 4th Quarter of 2023 Report on Discharge Self-Monitoring2024-01-18018 January 2024 Transmittal of the 4th Quarter of 2023 Report on Discharge Self-Monitoring DCL-24-008, Schedule Considerations for Review of the DCPP License Renewal Application2024-01-17017 January 2024 Schedule Considerations for Review of the DCPP License Renewal Application DCL-24-009, Nuclear Material Transaction Report for New Fuel2024-01-17017 January 2024 Nuclear Material Transaction Report for New Fuel DCL-24-004, Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2024-01-15015 January 2024 Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b DCL-23-129, Nuclear Material Transaction Report for New Fuel2023-12-27027 December 2023 Nuclear Material Transaction Report for New Fuel DCL-23-122, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-14014 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation DCL-23-128, Emergency Plan Update2023-12-13013 December 2023 Emergency Plan Update DCL-23-125, Core Operating Limits Report for Unit 1 Cycle 252023-12-0606 December 2023 Core Operating Limits Report for Unit 1 Cycle 25 DCL-23-121, Supplement to License Amendment Request 23-03, Revision to Technical Specification3.7.8, Auxiliary Saltwater System2023-11-16016 November 2023 Supplement to License Amendment Request 23-03, Revision to Technical Specification3.7.8, Auxiliary Saltwater System DCL-23-120, License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System2023-11-14014 November 2023 License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System DCL-23-118, License Renewal Application2023-11-0707 November 2023 License Renewal Application DCL-2023-520, Discharge Self-Monitoring at Diablo Canyon Power Plant (DCPP)2023-10-19019 October 2023 Discharge Self-Monitoring at Diablo Canyon Power Plant (DCPP) DCL-23-103, Independent Spent Fuel Storage Installation - Withdrawal of License Amendment Request 22-01, Request for Approval of Alternative Security Measures for Early Warning System2023-10-13013 October 2023 Independent Spent Fuel Storage Installation - Withdrawal of License Amendment Request 22-01, Request for Approval of Alternative Security Measures for Early Warning System 2024-09-09
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Pacific Gas and Electric Company Diablo Canyon Power Plant P0. Box 56 Avila Beach, CA 93424 March 11,2008 800.545.6000 PG&E Letter DCL-08-022 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Response to Request for Additional Information on License Amendment Request 07-02, "Revision to Technical Specification (TS) 3.5.4, 'Refueling Water Storage Tank (RWST)"'
Reference 1: PG&E Letter DCL-07-093, "License Amendment Request 07-02, Revision to Technical Specification (TS) 3.5.4, 'Refueling Water Storage Tank (RWST),'" dated October 2, 2007
Dear Commissioners and Staff:
By letter dated October 2, 2007 (Reference 1), Pacific Gas and Electric Company (PG&E) submitted License Amendment Request (LAR) 07-02, "Revision to Technical Specification (TS) 3.5.4, 'Refueling Water Storage Tank (RWST)."'
LAR 07-02 proposes a change to TS 3.5.4 Surveillance Requirement 3.5.4.2 to increase the minimum required borated water volume. This proposed change is required to meet commitments related to the resolution of issues raised in NRC Generic Letter.2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors," dated September 13, 2004.
By e-mail dated March 3, 2008, the NRC requested additional information required to complete the review of LAR 07-02. PG&E's response to that request is enclosed.
This information does not affect the results of the technical evaluation, or the no significant hazards consideration determination, previously transmitted in Reference 1.
PG&E makes no regulatory commitments (as defined by NEI 99-04) in this letter.
If you have any questions, or require additional information, please contact Stan Ketelsen at (805) 545-4720.
A member of the STARS (Strategic Teaming and Resource Sharing) Attiance Callaway e Comanche Peak
- South Texas Project a Wolf Creek
Document Control Desk PG&E Letter DCL-08-022 March 11,2008 Page 2 I state under penalty of perjury that the foregoing is true and correct.
Executed on March 11, 2008.
JamesN. Becker Site Vice President & Station Director tcg/4231 Enclosure cc: Gary Butner, California Department of Public Health Elmo E. Collins, NRC Region IV Michael S. Peck, NRC Senior Resident Inspector Diablo Distribution cc/enc: Alan B. Wang, Project Manager NRR 9
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Diablo Canyon e Palo Verde e South Texas Project
Enclosure PG&E Letter DCL-08-022 Response to Request for Additional Information on License Amendment Request 07-02, "Revision to Technical Specification (TS) 3.5.4,
'Refueling Water Storage Tank (RWST)'"
NRC Question 1:
The licensee, in an email dated 02/21/2008, provided a summary discussing the relationshipsbetween calculationsN-227 and STA-255, Rev. 2. In comparing the information in item 2 of page 2 of the summary with item 7.2 of Calculation STA-255, the NRC Staff noticed a potential non-conservatism in how the post-LOCA sump level is calculatedat the time of the first RHR [residualheat removal] pump taking suction from the sump. It appears to Staff that the net increase in the RWST injection volume to the sump as a result of the more accurateinstrumentation documented in calculation J-142A should be 0.5% of the RWST measured level, not 1.8% as indicatedin Calculation STA-255. Please clarify?
PG&E Response:
The minimum post-LOCA sump level of 93.6 ft to ensure adequatesubmergence of the GE sump strainers is acceptably demonstrated in STA-255 with currently installed RWST level instrumentation, and without any credit for installation of more accurate instrumentation. The purpose of Calculation STA-255, Section 7.2, was to assess the additional RWST liquid volume that would be available to reach the sump if more accurate RWST level instrumentation was installed. This available volume is not credited in the minimum required sump water level determination. The current calculation in STA-255, Section 7.2, conservatively estimated the additional margin that could be gained. The RWST level increase calculated in STA-255 is based on the 90 percent RWST level case in N-227, and the corresponding post-LOCA sump volume of 94.31 ft, which included a 2.2 percent sump volume penalty to bound instrument uncertainties. Therefore, the additional margin in sump volume that could be gained based on the smaller 1.7 percent uncertainty discussed in Section 7.3 would be 0.5 percent or 2291 gallons at 4582.63 gallon/percent. This corresponds to an increase in the current design basis post-LOCA sump level (93.6ift) at the time of the first RHR pump start to a value of:
SumpL18:31 = 93.6 ft + 2291 gal 7.4805 gal/ft3 / 11325.7 ft3 / ft
= 93162 ft NRC Question 2:
Please explain the process of aligning the RHR pump to the Safety Injection Pumps (SIPs) and Centrifugal ChargingPumps (CCPs) discussed in Section 7.3, "Sump water Level Increase During Cold Leg Switchover Process,"of CalculationSTA-255.
Specifically, explain how 900 gpm [gallons per minute] is diverted from the RWST to the 1
. I . I Enclosure PG&E Letter DCL-08-022 sump by the SIPs and the CCPs in the time periods discussed in Sections 7.3.B and 7.3. C, respectively?
PG&E Response:
Table 1 (next page) provides a sequential summary of the various flow intervals evaluated in STA-255, Section 7.3, in order to establish the relative post-LOCA sump level as the switchover from cold leg injection to cold leg recirculation occurs. The section titles identify the action taken at the end of the interval being evaluated such that the RWST flow credited to reach the sump during the interval has been determined to be accurately calculated.
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Enclosure PG&E Letter DCL-08-022 Table 1 Summary of STA-255, Section 7.3, Flow Intervals Interval Start Flows During Interval Interval Finish Sump Sump Level Level Time Action (ft) RWST Suction Sump Suction Time Action (ft) 2 CCPs - 900 gpm 7.3.B 2 SIPs - 900 gpm RHRPP # 2 2 CSPs - 6800 gpm 1 RHRPP - 2762 8804B 18:31 Started 93.6 Total - 8600 gpm gpm 19:26 Opened 93.7 1 RHRPP - 2762 7.3.C 2 CCPs - 900 gpm gpm 8804B 2 CSPs - 6800 gpm 2 SIPs - 900 gpm 8807A/B 19:26 Opened 93.7 Total - 7700 gpm Total - 3662 gpm 20:21 Opened 93.8 1 RHRPP - 2762 gpm 7.3.D 2 CCPs - 900 gpm 8807A/B 2 CSPs - 6800 gpm 2 SIPs - 900 gpm RHRPP #1 20:21 Opened 93.8 Total - 6800 gpm Total - 4562 gpm 21:46 Started 93.9 2 RHRPPs - 7769 gpm 7.3.E 2 CCPs - 900 gpm RHRPP # 1 2 CSPs - 6800 gpm 2 SIPs - 900 gpm CSPs 21:46 start 93.96 Total - 6800 gpm Total - 7769 gpm 29:17 Stopped 94.5' 3
.,1 1 4ý Enclosure PG&E Letter DCL-08-022 NRC Question 3:
The opening paragraphin Section 7.3.D of Calculation STA-255 appears to be inconsistent with the previous sections of the calculation. Specifically, explain the validity of references to valves 8807 A/B, and CCPs? Also, clarify if "20:21"referenced in the last sentence of this paragraphshould be "21:46"?
PG&E Response:
The description in the calculation will be revised to read:
"During this period, right before starting RHRP #1, the CSPs are the only pumps pumping water from the RWST into the containment sump. The sump water level just before 21:46 is:"
Also, the following description will be added at the end of Section 7.3.D:
"Once RHRP #1 is started at 21:46 taking suction from the sump, the total suction flow from the sump to the RHR pumps is 7,769 gpm per Design Input 5."
The next revision of STA-255 will incorporate these changes.
NRC Question 4:
Is there any affect on the seismic qualification of the RWST due to the proposed increase in the tank inventory?
PG&E Response:
No, the increase in tank inventory is enveloped by the volume already considered in the seismic analysis of the RWST.
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