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Category:Letter
MONTHYEARML24302A2622024-11-0101 November 2024 Letter to CA SHPO Regarding DCPP Dseis ML24302A1922024-11-0101 November 2024 Ltr to G. Frausto Coastal Band of Chumash Indians Re DCPP Dseis ML24302A1952024-11-0101 November 2024 Ltr to M. Olivas Tucker Ytt Re DCPP Dseis ML24302A1912024-11-0101 November 2024 Ltr to C. Mcdarment Tule River Tribe Re DCPP Dseis ML24302A1942024-11-0101 November 2024 Ltr to K. Kahn Santa Ynez Band of Chumash Indians Re DCPP Dseis ML24302A1962024-11-0101 November 2024 Ltr to SLO County Chumash Indians Re DCPP Dseis ML24302A1932024-11-0101 November 2024 Letter to G. Pierce Salinan Tribe of Monterey, SLO Re DCPP Dseis ML24302A1972024-11-0101 November 2024 Letter to V. Sage Walker Northern Chumash Tribal Council Re DCPP Dseis ML24302A2612024-11-0101 November 2024 Letter to Achp Re DCPP Dseis ML24275A0622024-10-30030 October 2024 NRC to NMFS Request Initiate Formal Endangered Species Act Consultation and Abbreviated Essential Fish Habitat for Proposed License Renewal of DCP Plant Units 1, 2 IR 05000275/20240032024-10-30030 October 2024 Integrated Inspection Report 05000275/2024003 and 05000323/2024003 and Independent Spent Fuel Storage Installation Report 07200026/2024001 ML24269A0122024-10-29029 October 2024 OEDO-24-00083 2.206 Petition Diablo Canyon Seismic CDF - Response to Petitioner Letter ML24284A3122024-10-28028 October 2024 Ltr to P Ting, Diablo Canyon Nuclear Power Plant Units 1 and 2 Notice of Avail of Draft Supplement 62 to the GEIS for Lic Renew of Nuclear Plants ML24284A3112024-10-28028 October 2024 Ltr to a Peck, Diablo Canyon Nuclear Power Plant Units 1 and 2 Notice of Avail of Draft Supplement 62 to the GEIS for Lic Renew of Nuclear Plants IR 05000275/20240132024-10-28028 October 2024 – License Renewal Report 05000275/2024013 and 05000323/2024013 DCL-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 ML24261B9492024-10-24024 October 2024 Issuance of Amendment Nos. 246 and 248 Revision to Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) IR 05000275/20244042024-10-23023 October 2024 Security Baseline Inspection Report 05000275/2024404 and 05000323/2024404 ML24277A0292024-10-18018 October 2024 NRC to Fws Req. for Concurrence W. Endangered Species Act Determinations for Diablo Canyon Power Plant Units 1,2, ISFSI Proposed License Renewals in San Luis Obispo Co., CA 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 IR 05000275/20253012024-10-0303 October 2024 Notification of NRC Initial Operator Licensing Examination 05000275/2025301; 05000323/2025301 ML24240A0222024-09-20020 September 2024 Letter to A. Peck Environmental Impact Statement Scoping Summary Report for Diablo Canyon Nuclear Power Plant Units 1 and 2 ML24260A1222024-09-14014 September 2024 14 Sept 2024 Ltr - California Coastal Commission to Pg&E, Incomplete Consistency Certification for Requested Nuclear Regulatory Commission License Renewal for Diablo Canyon Power Plant 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) ML24262A2462024-09-11011 September 2024 10 CFR 2.206 - Diablo Canyon Units 1 and 2 Seismic - Petitioner Response to Acknowledgement Letter - 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 ML24205A0662024-08-27027 August 2024 OEDO-24-00083 - 10 CFR 2.206 - Ack Letter - Diablo Canyon Units 1 and 2 Seismic Core Damage Frequency - IR 05000275/20240052024-08-22022 August 2024 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2024005 and 05000323/2024005) 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 IR 05000275/20240022024-08-0606 August 2024 Integrated Inspection Report 05000275/2024002 and 05000323/2024002 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 ML24187A1352024-07-16016 July 2024 Letter to Paula Gerfen - Diablo Canyon Units 1 and 2 - Summary of June 2024 Audit Related to the License Renewal Application Severe Accident Mitigation Alternatives Review IR 05000275/20240142024-07-11011 July 2024 Age-Related Degradation Inspection Report 05000275/2024014 and 05000323/2024014 IR 05000275/20244012024-07-0808 July 2024 Security Baseline Inspection Report 05000275/2024401 and 05000323/2024401 (Full Report) IR 05000323/20240112024-07-0303 July 2024 License Renewal Phase Report 05000323/2024011 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 ML24155A2182024-06-18018 June 2024 OEDO-23-00350-NRR - (LTR-23-0228-1) - Closure Letter - 10 CFR 2.206 Petition from Mothers for Peace and Friends of the Earth Regarding Diablo Canyon ML24129A1762024-06-14014 June 2024 National Historic Preservation Act Section 106 Consultation – Results of Identification and Evaluation (Docket Number: 72-026) ML24200A2052024-06-0707 June 2024 Fws to NRC, List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project for Diablo Canyon License Renewal ML24099A2192024-05-29029 May 2024 Issuance of Amendment Nos. 245 and 247 Revision to TSs to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24117A0132024-05-20020 May 2024 Letter to Paula Gerfen-Diablo Canyon Units 1 and 2-Regulatory Audit Regarding Severe Accident Mitigation Alternatives for the License Renewal Application 2024-09-09
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NUCLEAR UTILITY GROUP ADAMS Accession no. ML22271A885
ON EQUIPMENT QUALIFICATION
WINSTON & STRAWN LLP 1901 L STREET, N.W.
WASHINGTON, D.C. 20036-3506
TELEPHONE (202) 282-5737 September 27, 2022
VIA: U.S. Mail and email:
Vincent G. Gaddy, Chief Engineering Branch 1, Region 4 Division of Operating Reactor Safety 1600 East Lamar Boulevard Arlington, Texas 76011-4511
Re: NUGEQs Concern with Generic Implications and Request for Clarification Stemming from the Classification of Performance Deficiency under Diablo Canyon TEAMS IR-2022011 as a 10 C.F.R. § 50.49(e)(1) Non-Cited Violation (NCV)
Dear Mr. Gaddy:
The Nuclear Utility Group on Equipment Qualification (NUGEQ or Group)1 hereby submits this letter as a result of the Groups review of the Green Finding and NCV levied against Pacific Gas & Electric/Diablo Canyon on August 9, 2022. Specifically, in Inspection Report 05000275/2022-011 and 05000323/2022-011, inspectors identified a performance deficiency associated with a violation of 10 C.F.R. § 50.49(e)(1). The performance deficiency was triggered by the licensees2 failure to include the most severe temperature at the 480 VAC switchgear, and the 125 VDC battery charger/inverter rooms resulting from a postulated design basis tornado event in the electric equipment qualification program. 3 As noted in the inspection report, the inspectors expressed the view that the increase in room temperature caused by the design basis tornado event meant that the 480 VAC switchgear rooms and the 125 VDC battery charger/inverter rooms were no longer mild environments when compared to normal room temperature limits.
As a result, inspectors further expressed the view that the electric equipment in those rooms would need to be qualified to remain functional for the anticipated temperatures during the duration of a design basis tornado event. The inspectors concluded that [s]ince the licensees
1 The Group represents approximately 75% of the operating nuclear power plants in the United States. The Group was founded in 1981, as the NRC staff was evaluating and planning the ultimate promulgation of 10 CFR 50.49, Environmental qualification of electric equipment important to safety for nuclear power plants.
2 PG&E is not a current member of the Group.
3 ML22215A284 Vincent G. Gaddy September 27, 2022 Page 2
electric equipment qualification program was not based upon the time-dependent temperature in those rooms resulting from the most severe design basis event[,] the licensee was in violation of 10 CFR 50.49. It appears that the basis for the vi olation stems from the staffs position that the application of the conditions resulting from a design basis event (DBE) (in this case a tornado, e.g., a natural phenomenon) are coincident to the conditions from a design basis accident (DBA),
which are addressed under § 50.49(e).
The Group takes no formal position on the merits of whether the licensee should or should not respond to the performance deficiency. From a generic perspective, however, the Group is concerned with the implications of the analysis and conclusions memorialized in the IR with respect to future inspections that could impact our Group members. In particular, section 50.49(e)(1) specifically requires an EQ program to include and be based on the time-dependent temperature and pressure at the location of the el ectric equipment important to safety for the most severe design basis accident (DBA4) during or following which this equipment is required to remain functional. Since DBAs are a subset of DBEs, these terms have different meanings and are not interchangeable. In effect, the violation basis of the Green finding incorrectly expands the applicability of § 50.49(e)(1) beyond design basis accidents to include natural phenomena or external events, such as a tornado, which is contrary to the specific exclusion of those conditions from 10 C.F.R. 50.49. See 10 CFR § 50.49(c).
The NRC has been clear on this distinction since the promulgation § 50.49 in 1983. In fact, this issue was raised and addressed during public comments on the rule. The NRCs response resulted in the exclusion of natural phenomena and external events as specifically delineated in the Statement of Considerations.5 The exclusion of natural phenomena or external events such as tornados from the scope of EQ programs is also reflected in Chapter 3.11 of NUREG-0800 as well as in RG 1.89 Revision 1.6
The postulated temperature conditions within the 480 VAC switchgear rooms or the 125 VDC battery charger/inverter rooms from a tornado are not within the scope of the EQ final rule since a tornado is a natural phenomenon. These conditions are addressed external to an EQ program, consistent with GDC-2 and GDC-4. As such, § 50.49 is not applicable to environmental conditions from tornados. The converse interpretation delineated in the Diablo Canyon IR is
4 Design basis accidents are a subset of design basis events as defined by 10 CFR 50.49(b)(1)(ii).
5 [T]he Commission has concluded that protection of electric equipment important to safety against other natural phenomena and external events should not be within the scope of this rule. See 48 Fed. Reg. 2,731 (01/21/1983).
6 Reviews to determine compliance with related requirements for (1) dynamic and seismic qualification of electrical and mechanical equipment, (2) protection of electric and mechanical equipment against other natural phenomena and external events are described in other SRP sections. See NUREG-0800, 3.11 Environmental Qualification of Mechanical and Electric Equipment, at p. 3.11-2. See also, RG 1.89, Rev. 1, Section A: Section 50.49 does not include requirements for protection of electric equipment against other natural phenomena and external events, and equipment located in a mild environment.
Vincent G. Gaddy September 27, 2022 Page 3
erroneous and would pose significant generic implications on existing EQ programs if so applied.
Request for Clarification
Given the generic implications of the NCV cited to § 50.49(e)(1), the Group requests Staff clarification that §50.49 EQ programs must include or be based on the time-dependent temperature and pressure conditions for the most severe design basis accident during or following which this [electrical] equipment important to safety is required to remain functional, but that the temperat ure conditions resulting from external events, such as tornados, are addressed external to electric equipment qualification programs, consistent with the provisions of 10 CFR 50.49(c) and 50.49(e)(1).
We request this letter and any subsequent communications be placed into the public Agencywide Documents Access and Management System. We look forward to opportunities to discuss this issue with you at your convenience.
Respectfully,
William A. Horin Partner, Winston & Strawn LLP Counsel to NUGEQ
cc (via email):
R. Kopriva, R-IV/DORS/EB1 Ron.Kopriva@nrc.gov J. Braisted, R-IV/DORS/EB1 Jonathan.Braisted@nrc.gov M. Gray, R-I/DORS/EB1 Mel.Gray@nrc.gov Glenn Dentel, R-I/DORS/EB2 Glenn.Dentel@nrc.gov James Baptist, R-II/DRS/EB1 James.Baptist@nrc.gov Karla Stoedter, R-III/DRS/EB2 Karla.Stoedter@nrc.gov Richard Skokowski, R-III/DRS/EB3 Richard.Skokowski@nrc.gov
Vincent G. Gaddy September 27, 2022 Page 4
Nicholas Taylor, R-IV/DORS/EB2 Nick.Taylor@nrc.gov Matt McConnell, NRR/ELTB/DEX Matthew.McConnell@nrc.gov