|
---|
Category:Fire Protection Plan
[Table view] Category:Letter type:DCL
MONTHYEARDCL-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-24-070, 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-24-010, Nuclear Material Transaction Report for New Fuel2024-01-29029 January 2024 Nuclear Material Transaction Report for New Fuel DCL-24-009, Nuclear Material Transaction Report for New Fuel2024-01-17017 January 2024 Nuclear Material Transaction Report for New Fuel 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-24-004, 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 DCL-23-092, Material Status Report for the Period Ending August 31, 20232023-09-28028 September 2023 Material Status Report for the Period Ending August 31, 2023 DCL-23-077, 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 Reactors2023-09-27027 September 2023 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 Reactors DCL-23-083, Upcoming Meeting with Nuclear Security and Incident Response Staff2023-09-13013 September 2023 Upcoming Meeting with Nuclear Security and Incident Response Staff DCL-23-078, Nuclear Material Transaction Report for New Fuel2023-09-0606 September 2023 Nuclear Material Transaction Report for New Fuel DCL-23-070, Withdrawal of Request Regarding Senior Reactor Operator License Application2023-08-16016 August 2023 Withdrawal of Request Regarding Senior Reactor Operator License Application DCL-23-068, Nuclear Material Transaction Report for New Fuel2023-08-0909 August 2023 Nuclear Material Transaction Report for New Fuel DCL-23-066, Nuclear Material Transaction Report for New Fuel2023-08-0303 August 2023 Nuclear Material Transaction Report for New Fuel DCL-23-065, Letter DCL-23-065 Request That Exam Material Be Withheld from Public Disclosure2023-07-27027 July 2023 Letter DCL-23-065 Request That Exam Material Be Withheld from Public Disclosure DCL-23-064, Nuclear Material Transaction Report for New Fuel2023-07-26026 July 2023 Nuclear Material Transaction Report for New Fuel DCL-23-054, 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 4b2023-07-13013 July 2023 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-23-055, Nuclear Material Transaction Report for New Fuel2023-07-0606 July 2023 Nuclear Material Transaction Report for New Fuel DCL-23-042, Independent Spent Fuel Storage Installation, Submittal of Quality Assurance Program Description, Revision 02023-05-24024 May 2023 Independent Spent Fuel Storage Installation, Submittal of Quality Assurance Program Description, Revision 0 DCL-23-032, Independent Spent Fuel Storage Installation Docket No. 72-27, Materials License Number SNM-2514 Humboldt Bay Independent Spent Fuel Storage Installation - NRC Requested Notification of Withdrawal from Voluntary Program2023-05-22022 May 2023 Independent Spent Fuel Storage Installation Docket No. 72-27, Materials License Number SNM-2514 Humboldt Bay Independent Spent Fuel Storage Installation - NRC Requested Notification of Withdrawal from Voluntary Program DCL-23-041, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 20222023-05-22022 May 2023 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2022 DCL-23-038, Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule2023-05-15015 May 2023 Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule DCL-23-025, 2022 Annual Radioactive Effluent Release Report2023-05-0101 May 2023 2022 Annual Radioactive Effluent Release Report DCL-23-036, 2022 Annual Radiological Environmental Operating Report2023-05-0101 May 2023 2022 Annual Radiological Environmental Operating Report DCL-23-034, 2022 Annual Nonradiological Environmental Operating Report2023-05-0101 May 2023 2022 Annual Nonradiological Environmental Operating Report DCL-2023-512, Submittal of Receiving Water Monitoring Program 2022 Annual Report2023-04-27027 April 2023 Submittal of Receiving Water Monitoring Program 2022 Annual Report DCL-23-028, Technical Specification Bases, Revision 142023-04-24024 April 2023 Technical Specification Bases, Revision 14 DCL-23-035, Response to Request for Additional Information on Request Regarding Senior Reactor Operator License Application2023-04-24024 April 2023 Response to Request for Additional Information on Request Regarding Senior Reactor Operator License Application DCL-2023-511, Report on Discharge Monitoring for the First Quarter of 20232023-04-20020 April 2023 Report on Discharge Monitoring for the First Quarter of 2023 DCL-23-031, Submittal of Annual Report of Occupational Radiation Exposure for 20222023-04-19019 April 2023 Submittal of Annual Report of Occupational Radiation Exposure for 2022 2024-08-08
[Table view] |
Text
Pacific Gas and Electric Company M a y 3 0 ,2 01 3 PG&E Letter DCL-13-060
.U.S. Nuclear Regulatory Commission ATTN: Docu ment 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 B arry S. Allen Site Vice President Diablo Canyon Power Plant Mail Code 104/6 P. O. Box 56 Avila Beach, CA 93424 805.545.4888 Internal: 691. 4888 Fax: 805.545.6445 Correction of Information Provided to NRC Inspectors During the 2012 Triennial Fire Protection Inspection
Reference:
NRC Inspection Report, "DIABLO CANYON POWER PLANT, UNITS 1 AND 2 -NRC TRIENNIAL FIRE INSPECTION REPORT (05000275/2012008; 0500032312012008)
AND EXERCISE OF ENFORCEMENT DISCRETION,"* dated February 7,2013. (ADAMS Accession No. ML 13038A714)
In the above referenced NRC inspection report, NRC inspectors documented their findings from the 2012 Triennial Fire Protection Inspection at Diablo Canyon Power Plant (DCPP). One violation referenced incorrect information inadvertently provided by Pacific Gas and Electric Company (PG&E) staff during the inspection. The enclosure to this letter identifies that information, corrects it, and requests the NRC to correct the inspection report. DCPP personnel discussed this information with the lead inspector over the phone on May 7, 2013. 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 Mr. Tom Baldwin at (805) 545-4720.
Sincerely, Barry i. Allen M EM6/4418/SAPN 50559636-2 Enclosure cc: cc/encl: Diablo Distribution Thomas R. Hipschman, NRC Senior Resident Inspector Arthur T. Howell, III, NRC Region IV John M. Mateychick, NRC Region IV Inspector James T. Polickoski, NRR Project Manager A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Wolf Creek Enclosure PG&E Letter DCL-13-060 Page 1 of 2 Correction of Information Provided to the NRC PG&E's Error Description From October 22, 2012, through November 8, 2012, the NRC conducted the 2012 Triennial Fire Protection Inspection at Diablo Canyon Power Plant (DCPP). On October 22, 2013, the inspectors asked about the amount of time available to operators to prevent the reactor coolant system (RCS) from going "solid" if RCS letdown spuriously actuates.
Pacific Gas and Electric (PG&E) personnel responded as follows: The most limiting event for rapidly filling the pressurizer to a water-solid condition is analyzed in the DCPP Updated Final Safety Analysis Report (UFSAR), Section 15.2.15, "Spurious Operation of the Safety Injection System at Power." This accident analysis conservatively assumes that a safety injection (SI) signal is spuriously generated while operating at 100 percent power, the Emergency Core Cooling System actuates, RCS letdown isolates, and offsite power is lost. On October 25, 2013, PG&E further clarified this response with respect to operator action times, but repeated the above paragraph regarding the analysis and UFSAR assumptions.
Subsequently, during efforts to verify DCPP's licensing bases, PG&E's Licensing Bases Verification Project (LBVP) staff asked for clarification of the assumptions used in UFSAR Section 15.2.15. Upon further review, plant staff recognized that the information provided to the NRC during the fire protection inspection was in error. Specifically, neither the accident analysis, nor the UFSAR assume that offsite power is lost during spurious operation of the SI system. NRC Use of the Incorrect Information On page 12 of NRC Inspection Report (IR) 05000275/2012008; 05000323/2012008, Section 1 R05.05.b.1 correctly states: The team identified a violation of Technical Specification 5.4.1.d for the failure to implement and maintain adequate written procedures covering fire protection program implementation.
Specifically, the team identified five examples (with a total of eight fire scenarios) where the licensee failed to maintain an alternative shutdown procedure that ensured operators could safely shutdown the plant in the event of a control room or cable spreading room fire. This violation has been screened and determined to warrant enforcement discretion in accordance with the NRC Enforcement Policy, Section 9.1, "Enforcement Discretion for Certain Fire Protection Issues (10 CFR 50.48)," and Inspection Manual Chapter 0305.
Enclosure PG&E Letter DCL-13-060 Page 2 of2 In Example 4, "Potential Overfilling of the Pressurizer," paragraph 3, on page 15 of the NRC's IR, the NRC included information consistent with what PG&E had provided by stating: The licensee examined the spurious actuation of the safety injection system in the Final Safety Analysis Report Section 15.2.15. The licensee's analysis assumed the safety injection signal occurred at 100 percent power, the emergency core cooling system actuated, letdown isolated, and offsite power was lost. The licensee concluded that operators had 8.5 minutes to control charging prior to the pressurizer reaching a water solid condition.
This statement in Example 4 was erroneous because it reiterated the assumption that offsite power was lost when, in fact, neither the accident analysis, nor the UFSAR assume that offsite power is lost during spurious operation of the SI system. Impact of the Incorrect Information The error (Le., assuming offsite power was lost) did not correctly convey data found in DCPP's accident analysis and its UFSAR. The NRC repeated this error in its IR; however, this incorrect information was not required for the NRC to evaluate and conclude that a violation of Technical Specification 5.4.1.d had occurred.
All analysis results and UFSAR representations continue to be correct. PG&E's characterization of those analysis results and UFSAR representations were in error regarding the assumption of loss of offsite power. Hence, the findings in the report remain correct; however, the statement in the report regarding the misrepresentation should be corrected.
Requested Corrections to the Inspection Report PG&E believes that it is in the best interests of the NRC and PG&E to ensure that statements made in inspection reports are correct, notwithstanding the absence of an immediate material impact. Therefore, consistent with the above information, PG&E requests the NRC to correct the following statement in NRC IR 05000275/2012008; 05000323/2012008, Section 1 R05.05.b.1, Example 4 as shown: The licensee examined the spurious actuation of the safety injection system in the Final Safety Analysis Report Section 15.2.15. The licensee's analysis assumed the safety injection signal occurred at 100 percent power, the emergency core cooling system actuated, and letdown isolated, and offsite pO'l/ef vias lost. The licensee concluded that operators had 8.5 minutes to control charging prior to the pressurizer reaching a water-solid condition.