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MONTHYEARML0704400462007-02-0808 February 2007 Proposed Change Number (PCN) - 574 Degraded Voltage Setpoints Project stage: Request ML0715502562007-06-13013 June 2007 Request for Additional Information on the Proposed License Amendment on Degraded Voltage Setpoints (TAC Nos. MD4419 & MD4420) Project stage: RAI ML0720606512007-07-24024 July 2007 Response to Request for Additional Information on the Proposed License Amendment on Degraded Voltage Setpoints Project stage: Response to RAI ML0725502112007-09-24024 September 2007 Request for Additional Information on the Proposed Amendment to Revise Degraded Voltage Instrumentation (Tac Nos. MD4419 and MD4420) Project stage: RAI ML0728900322007-10-18018 October 2007 Request for Additional Information on the Proposed License Amendment on Degraded Voltage Setpoints Project stage: RAI ML0733005592007-11-15015 November 2007 Response to Requests for Additional Information on the Proposed Amendment for Degraded Voltage Setpoints, Proposed Change Number (PCN) 574 Project stage: Response to RAI ML0805203722008-02-19019 February 2008 Response to Request for Additional Information on the Proposed Amendment for Degraded Voltage Setpoints, Proposed Change Number (PCN) 574 Project stage: Response to RAI ML0805906032008-03-18018 March 2008 Technical Specifications, Revise TS Surveillance Requirements 3.3.7.3.a and 3.8.1 Degraded Voltage Function Values Project stage: Other ML0805905282008-03-18018 March 2008 License Amendment, Revise Technical Specification Surveillance Requirements 3.3.7.3.a and 3.8.1 Degraded Voltage Function Values Project stage: Other 2007-06-13
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Category:Letter
MONTHYEARML24022A1492024-01-17017 January 2024 Independent Spent Fuel Storage Installation, Revision 4 to the Physical Security Plan IR 05000361/20230062023-11-29029 November 2023 NRC Inspection Report 05000361/2023-006 and 05000362/2023-006 ML23333A0682023-11-22022 November 2023 (SONGS) Units 1, 2, 3 and Independent Spent Fuel Storage Installation - Notification of Change in Nuclear Officer IR 05000361/20230052023-10-11011 October 2023 NRC Inspection Report 05000361/2023005 and 05000362/2023005 ML23276A5942023-09-28028 September 2023 and Independent Spent Fuel Storage Installation - Supplement to Decommissioning Funding Status Reports ML23268A0922023-09-20020 September 2023 Generation Station, Units 1, 2 and 3, and the Independent Spent Fuel Storage Facility (ISFSI) - Re-Registration of Dry Fuel Storage Casks for Amended Certificate of Compliance No. 1040 IR 05000361/20230012023-09-13013 September 2023 NRC Inspection Report 05000361 2023-001 and 05000362 2023-004 ML23240A5372023-08-18018 August 2023 Confirmatory Survey Activities Summary and Results for the Unit 2 and 3 Intake Structures at the San Onofre Nuclear Generating Station San Clemente CA ML23129A1802023-06-14014 June 2023 Cover Letter to State of CA on Draft EA Regarding San Onofre ISFSI Updated DFPs IR 05000361/20230032023-05-31031 May 2023 NRC Inspection Report 05000361/2023003 and 05000362/2023003 IR 05000361/20230022023-05-23023 May 2023 NRC Inspection Report 05000361/2023-002 and 05000362/2023-002 ML23137A1032023-05-11011 May 2023 (Songs), Units 1, 2 and 3, and Independent Spent Fuel Storage Installation - 2022 Annual Radiological Environmental Operating Report ML23123A0932023-04-28028 April 2023 (Songs), Units 1, 2 and 3, Submittal of Annual Radioactive Effluent Release Report - 2022 ML23230A0882023-04-10010 April 2023 Independent Spent Fuel Storage Installation - Decommissioning Quality Assurance Plan ML23094A1272023-03-29029 March 2023 Independent Spent Fuel Storage Installation - 10 CFR 50.82(a)(8)(v and VII) and 10 CFR 72.30(c) Decommissioning Funding Status Report 2021 ML23094A1332023-03-29029 March 2023 Nuclear Property Insurance ML23062A1172023-02-28028 February 2023 Generation Station Units 1, 2 and 3, Annual Radioactive Effluent Release Report for Independent Spent Fuel Storage Installation - 2022 ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23059A2812023-02-22022 February 2023 (Songs), Units 1, 2 and 3, 2022 Annual Turtle Incidental Take Report ML23046A3792023-02-22022 February 2023 NRC Inspection Report 050-00361/2023-001 and 050-00362/2023-001 ML23045A2022023-02-0909 February 2023 Submittal of Annual Corporate Financial Reports for San Onofre Nuclear Generating Station (SONGS) Units 2 and 3 for Fy Ending June 30, 2022 ML22287A1352023-01-0505 January 2023 Issuance of Exemption from Title 10 of the Code of Federal Regulations Part 72.106(B), Independent Spent Fuel Storage Installation Controlled Area Boundary (L-2021-LLE-0056) ML22348A0622023-01-0404 January 2023 NRC to SCE, Transmittal of the National Marine Fisheries Service'S December 12, 2022, Letter of Concurrence for Decommissioning of San Onofre Nuclear Generating Statiion, Units 2 and 3 IR 05000206/20220062022-12-15015 December 2022 NRC Inspection Report 05000206/2022006, 05000361/2022-006, and 05000362/2022-006 ML22347A2122022-12-12012 December 2022 NMFS to NRC, Endangered Species Act Section 7(a)(2) Concurrence Letter for Decommissioning of the San Onofre Nuclear Generating Station ML22340A6652022-12-0505 December 2022 Letter from John Fassell, Chief; 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JSOUTHERN CALIFORNIA EDISON'An EDISON INTERNATIONAL*
Company Ross T. Ridenoure VP and Site Manager San Onofre Nuclear Generating Station February 19, 2008 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Reference:
Docket Nos. 50-361 and 50-362 Response to Request for Additional Information on the Proposed Amendment for Degraded Voltage Setpoints, Proposed Change Number (PCN) 574 (TAC Nos. MD4419 and MD4420)San Onofre Nuclear Generating Station, Units 2 and 3 February 8, 2007 letter from B. Katz (SCE) to Document Control Desk (NRC),
Subject:
San Onofre Nuclear Generating Station Units 2 and 3, Docket Nos. 50-361 and 50-362, Proposed Change Number (PCN)-574, Degraded Voltage Setpoints
Dear Sir or Madam:
By letter dated February 8, 2007 Southern California Edison (SCE) submitted the referenced Proposed Change Number (PCN)-574, Degraded Voltage Setpoints.
In a telephone conversation on January 8, 2008, NRC staff requested additional information regarding the submittal.
The NRC staff questions and the SCE responses are contained in the enclosure.
The only commitment contained herein is to the action stated in the response to NRC Question 2 in the enclosure.
If you have any questions or require additional information, please contact Ms. Linda T.Conklin at (949) 368-9443.Sincerely,
Enclosure:
As Stated Mail Drop D45 P.O. Box 128 San Clemente, CA 92672 949-368-6255 PAX 86255 Fax: 949-368-6183 Ross.Ridenoure@sce.com Document Control Desk February 19, 2008 cc: E. E. Collins, Regional Administrator, NRC Region IV N. Kalyanam, NRC Project Manager, San Onofre Units 2 and 3 C. C. Osterholtz, NRC Senior Resident Inspector, San Onofre Units 2 and 3 S. Y. Hsu, California Department of Public Health, Radiological Health Branch ENCLOSURE NRC QUESTION I a. Please explain why you have assumed an undervoltage relay drift of 0.45% in setpoint calculation E4C-130 ECN A47480, compared to the 0.1% approved by the NRC in 2005. This is a significant increase when the total loop uncertainty (TLU)is 0.7%.b. In calculation E4C-130 ECN A47480 you stated that after six months of operation with the new relay settings, you will evaluate the As-Left and As-Found values to determine the correct drift. Please document the details of field testing experience for selecting 0.45% drift.SCE RESPONSE The change in the assumed undervoltage relay drift from 0.1% to 0.45% is based on a drift analysis performed using more than 80 data points taken at intervals ranging from one to eight months. Details are provided in SCE document "ABBN27 Relay Drift Report." NRC QUESTION 2 The licensee's plant procedures should meet the requirements specified in Notes I and 2 of the September 7, 2005 NRC letter to the Nuclear Energy Institute Setpoint Methods Task Force, including the clarifications provided in Section 4 of the letter.SCE RESPONSE SCE commits to the following:
If the as-found relay setpoint is conservative with respect to the Allowable Value but outside its predefined as-found acceptance criteria band, then the relay shall be evaluated to verify that it is functioning as required before returning the relay to service.If the as-found relay setpoint is not conservative with respect to the Allowable Value, the relay shall be declared inoperable.
The relay setpoint shall be reset to a value that is within the as-left tolerance of the nominal relay setpoint; otherwise, the relay shall be declared inoperable.
If the as-found trip setpoint (TSP) is found to be non-conservative with respect to the allowable value (AV) specified in the Technical Specifications (TSs), the relay shall be declared inoperable and the associated TS action statement followed.If the as-found TSP is found to be conservative with respect to the AV, and outside the as-found predefined acceptance criteria band, but SCE is able to determine that the relay is functioning as required and can be reset to within the setting tolerance of the limiting TSP, or a value more conservative than the limiting TSP, then the relay may be Page 1 of 2 considered operable.
If it cannot be determined that the relay is functioning as required, it shall be declared inoperable and the associated TS actions followed.If the as-found TSP is outside the as-found predefined acceptance criteria band, the condition shall be entered into the corrective action program for further evaluation.
NRC QUESTION 3 Please confirm that the calculation results and recommendations are designed to minimize the occurrence of a class 1E bus transfer from off-site power to the emergency diesel generator when adequate grid voltage is available.
SCE RESPONSE SCE confirms that the results and recommendations of SCE calculation E4C-1 30 are designed to minimize the occurrence of a class 1 E bus transfer from off-site power to the emergency diesel generator when adequate grid voltage is available.
NRC QUESTION 4 Please provide the basis for the setting tolerance of + 0.05 Vac for adjusting the undervoltage relay setpoint.SCE RESPONSE The setting tolerance of + 0.05 Vac is based on plant experience with these relays.NRC QUESTION 5 Please confirm that the redesign work on the 120 volt AC systems referred to in your February 8, 2007 license amendment request is complete.SCE RESPONSE The redesign work on the 120 volt AC systems referenced in our February 8, 2007 submittal was to: "Increase 120 VAC power feeder size to 120 VAC panel 2L541 from MCC Panel 2Q039 by replacing the feeder cable from #12 AWG to #8 AWG for reducing voltage drop in the feeder circuit." This work has been completed under Engineering Change Package 060401140-96.
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