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TAC:ME6849, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (Open) TAC:ME6850, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (Open) |
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MONTHYEARL-PI-11-037, License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8 Re Cooling Water System & 3.8.3 Re Diesel Fuel Oil2011-08-11011 August 2011 License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8 Re Cooling Water System & 3.8.3 Re Diesel Fuel Oil Project stage: Request ML1126300412011-09-16016 September 2011 Ngp Units 1 and 2 - Acceptance Review of LAR to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8 and 3.8.3 Project stage: Acceptance Review ML1200603092012-01-19019 January 2012 Request for Additional Information Related to License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8 and 3.8.3 Project stage: RAI L-PI-12-007, Response to Requests for Additional Information for License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8, Cooling Water System & 3.8.3, Diesel Fuel Oil.2012-02-21021 February 2012 Response to Requests for Additional Information for License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8, Cooling Water System & 3.8.3, Diesel Fuel Oil. Project stage: Response to RAI ML12132A3132012-05-0808 May 2012 Ngp - Draft Request for Clarification of February 21, 2012 RAI Response Concerning Diesel Fuel Oil LAR Project stage: Draft RAI ML12142A1562012-05-23023 May 2012 Request for Additional Information Related to License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8 and 3.8.3 Project stage: RAI L-PI-12-047, Supplement to License Amendment Request (LAR) to Add Diesel Fuel Oil License Bases and Revise Technical Specifications (TS) 3.7.8, Cooling Water (Cl) System and 3.8.3, Diesel Fuel Oil (TAC Nos. ME6849 and ME68501)2012-07-0909 July 2012 Supplement to License Amendment Request (LAR) to Add Diesel Fuel Oil License Bases and Revise Technical Specifications (TS) 3.7.8, Cooling Water (Cl) System and 3.8.3, Diesel Fuel Oil (TAC Nos. ME6849 and ME68501) Project stage: Supplement L-PI-12-088, Supplement to License Amendment Request (LAR) to Add Diesel Fuel Oil License Bases and Revise Technical Specifications (TS) 3.7.8, Cooling Water (Cl) System and 3.8.3, Diesel Fuel Oil (TAC Nos. ME6849 and ME6850)2012-10-0404 October 2012 Supplement to License Amendment Request (LAR) to Add Diesel Fuel Oil License Bases and Revise Technical Specifications (TS) 3.7.8, Cooling Water (Cl) System and 3.8.3, Diesel Fuel Oil (TAC Nos. ME6849 and ME6850) Project stage: Supplement ML13011A3892013-01-22022 January 2013 Request for Additional Information Related to License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8 and 3.8.3 Project stage: RAI L-PI-13-001, Supplement to License Amendment Request (LAR) to Add Diesel Fuel Oil License Bases and Revise Technical Specifications (TS) 3.7.8, Cooling Water (Cl) System and 3.8.3, Diesel Fuel Oil.2013-02-0808 February 2013 Supplement to License Amendment Request (LAR) to Add Diesel Fuel Oil License Bases and Revise Technical Specifications (TS) 3.7.8, Cooling Water (Cl) System and 3.8.3, Diesel Fuel Oil. Project stage: Supplement L-PI-13-039, Supplement to License Amendment Request (LAR) to Add Diesel Fuel Oil License Bases and Revise Technical Specifications (TS) 3.7.8, Cooling Water (Cl) System and 3.8.3, Diesel Fuel Oil.2013-04-30030 April 2013 Supplement to License Amendment Request (LAR) to Add Diesel Fuel Oil License Bases and Revise Technical Specifications (TS) 3.7.8, Cooling Water (Cl) System and 3.8.3, Diesel Fuel Oil. Project stage: Supplement ML13093A3442013-05-0909 May 2013 License Amendments for Fuel Oil System and TSTF-501 Project stage: Other ML13214A0292013-08-0202 August 2013 Correction Letter for License Amendment Nos. 207 (Unit 1) and 194 (Unit 2) Project stage: Other 2012-05-08
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Category:Letter type:L
MONTHYEARL-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report L-PI-23-010, Annual Report of Individual Monitoring2023-04-27027 April 2023 Annual Report of Individual Monitoring L-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2023-03-28028 March 2023 Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-005, CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2023-03-0303 March 2023 CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) L-PI-23-001, Day Steam Generator Tube Inspection Report2023-01-30030 January 2023 Day Steam Generator Tube Inspection Report L-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report2022-12-21021 December 2022 Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2022-12-0202 December 2022 Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-22-040, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0606 October 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-037, Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts2022-09-20020 September 2022 Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts L-PI-22-032, CFR 50.46 LOCA Annual Report2022-06-16016 June 2022 CFR 50.46 LOCA Annual Report L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles2022-06-10010 June 2022 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles L-PI-22-003, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0707 June 2022 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-024, Supplement to Application for License Amendment to Implement 24-Month Operating Cycle2022-03-0707 March 2022 Supplement to Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-047, Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 22021-12-0707 December 2021 Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 2 L-PI-21-045, Response to Request for Additional Information Cooling Water System License Amendment Request2021-11-0404 November 2021 Response to Request for Additional Information Cooling Water System License Amendment Request L-PI-21-029, Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.12021-10-0707 October 2021 Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.1 L-PI-21-006, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions2021-10-0202 October 2021 License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions L-PI-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island2021-09-30030 September 2021 Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island L-PI-21-016, Application for License Amendment to Implement 24-Month Operating Cycle2021-08-0606 August 2021 Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-027, 2020 10 CFR 50.46 LOCA Annual Report2021-06-28028 June 2021 2020 10 CFR 50.46 LOCA Annual Report L-PI-21-023, Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report2021-05-14014 May 2021 Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes2021-04-19019 April 2021 Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes L-PI-20-050, Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic2020-10-0707 October 2020 Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic L-PI-20-051, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2020-09-28028 September 2020 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ2020-09-0101 September 2020 Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 L-PI-20-035, = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule2020-07-28028 July 2020 = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule L-PI-20-023, Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)2020-06-10010 June 2020 Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI) L-PI-20-014, Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI2020-04-29029 April 2020 Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI L-PI-20-004, License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.132020-03-30030 March 2020 License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.13 L-PI-20-001, License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-12020-01-29029 January 2020 License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-1 L-PI-19-041, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2019-12-23023 December 2019 Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-19-031, License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-16016 December 2019 License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency2019-10-0707 October 2019 License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency L-PI-19-038, Submittal of Revised Pressure and Temperature Limits Report2019-09-19019 September 2019 Submittal of Revised Pressure and Temperature Limits Report L-PI-19-037, Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2019-09-16016 September 2019 Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals L-PI-19-025, Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP)2019-08-27027 August 2019 Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP) L-PI-19-029, Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For...2019-08-0505 August 2019 Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For... L-PI-19-002, 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 22019-06-13013 June 2019 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 2 L-PI-19-014, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-04-29029 April 2019 Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-PI-19-003, Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP)2019-02-0404 February 2019 Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP) L-PI-19-006, Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements2019-01-29029 January 2019 Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements L-PI-19-005, Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.692019-01-15015 January 2019 Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.69 L-PI-18-063, Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 8052018-12-0606 December 2018 Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 805 2024-01-02
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Xcel Energym L-PI-12-088 10 CFR 50.90 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 Supplement to License Amendment Request (LAR) to Add Diesel Fuel Oil License Bases and Revise Technical Specifications (TS) 3.7.8, "Cooling Water (CL) Svstem" and 3.8.3, "Diesel Fuel Oil" (TAC Nos. ME6849 AND ME68501 By letter dated August 11,2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. MLI 12240140), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), requested NRC review and approval of additional diesel fuel oil (DFO) license bases and amendments to TS 3.7.8, "Cooling Water (CL) System" and 3.8.3, "Diesel Fuel Oil" for the Prairie Island Nuclear Generating Plant (PINGP), Units Iand 2. NSPM supplemented this LAR by letters dated February 21, 2012 (ML12054A057) and July 9, 2012 (ML12192A213). By email dated August 24,2012 (ML12261A393), NRC Staff provided clarification questions on information provided in the July 9, 2012 (ML12192A213) supplement. The enclosure to this letter provides responses to the NRC Staff clarification questions. NSPM submits this supplement in accordance with the provisions of 10 CFR 50.90.
The supplemental information provided in this letter and enclosure does not impact the conclusions of the Determination of No Significant Hazards Consideration or Environmental Assessment presented in the August 11, 201 1 (MLI 12240140) submittal as supplemented February 21,2012 (ML12054A057) and July 9,2012 (ML12192A213).
In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota of this LAR supplement by transmitting a copy of this letter and enclosure to the designated State Official.
If there are any questions or if additional information is needed, please contact Mr. Dale Vincent, P.E., at 651-388-1121.
1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1 121
Document Control Desk Page 2 Summarv of Commitments This letter contains no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on OCT 0 4 2012 Joel P. ~ o r e n s e n Acting Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (1) cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC State of Minnesota
ENCLOSURE Response to Email Clarification Questions for License Amendment Request (LAR) to Add Diesel Fuel Oil License Bases and Revise Technical Specifications (TS) 3.7.8, "Cooling Water (CL) System" and 3.8.3, "Diesel Fuel Oil" (TAC Nos. ME6849 and ME6850)
This enclosure provides responses from Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), to Nuclear Regulatory Commission (NRC) clarification questions provided by email dated August 24, 2012 (ML12261A393) regarding the LAR requesting NRC review and approval of additional diesel fuel oil (DFO) license bases and amendments to TS 3.7.8, "Cooling Water (CL)
System" and TS 3.8.3, "Diesel Fuel Oil" for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2, submitted by letters dated August 11, 201 1 (MLI 12240140) as supplemented February 21,2012 (ML12054A057) and July 9,2012 (ML12192A213).
NRC Clarification Question for NSPM Response to RAI EEEB-7 Technical Specification Surveillance Requirement (SR) 3.8.1.5 requires the licensee to verify, every 31 days, that the fuel oil transfer system operates to transfer fuel oil from storage tank to day tank.
In its letter dated February 21, 2012, NSPM stated in its response to RAI [Request for Additional Information] EEEB-Id, in part:
The Unit 1 fuel oil system has the capability to transfer fuel from any storage tank to any day tank as defined in the USAR [Updated Safety Analysis Report].
However, procedures are not in place to cover the many different scenarios for transferring fuel during a 14 day flooding event. The transfer paths will be dependent on the equipment operating and fuel oil levels in the various tanks.
The flow diagrams would be utilized to perform actions not covered under established procedures or [Abnormal Operating Procedures].
Describe how NSPM demonstrates compliance with SR 3.8.1.5 for operability of all of the flow paths credited in the design basis of the plant for 14-day operation during the design basis flood.
NSPM Response to EEEB-7 Clarification Question:
SR 3.8.1.5 states, "Verify the fuel oil transfer system operates to transfer fuel oil from storage tank to the day tank." Performance of SR 3.8.1.5 demonstrates the ability of each fuel oil transfer pump to operate and transfer fuel from its associated storage tank to its associated day tank. NSPM demonstrates compliance with SR 3.8.1.5 through monthly surveillances for Diesel Fuel Oil Testing which defines Unit specific steps within Page 1 of 5
Diesel Fuel Oil RAls the sampling procedures to operate each transfer pump and verify that a level change is seen at the associated day tank. This testing meets NSPM1sunderstanding of the requirements of this SR.
NRC Clarification Question for NSPM Response to RAI EEEB-8 Provide details for each EDG [Emergency Diesel Generator] fuel oil consumption (given licensing basis such as single failure) that will demonstrate capability of the fuel oil system to support 7-day EDG operation following any event evaluated in the PlNGP licensing documents. Details shall include the bounding Unit 1 and Unit 2 fuel oil consumption values (gallons) and a summary of the methodology, key assumptions, industry standards used, the basis for the parameters used, the EDG load profile that is considered bounding, and any relevant information that NSPM has used to derive the values (gallons) that will become a baseline 7-day fuel oil storage requirement.
NSPM Response to RAI EEEB-8 Clarification Question:
Unit 1 diesel fuel oil consumption volume:
Calculated Volume The Unit 1 diesel fuel oil system provides fuel oil to both the Unit 1 EDGs ( D l and D2) and the safeguards diesel driven cooling water pumps (DDCLPs). The calculated seven-day fuel oil consumption volume for the Unit 1 diesel fuel oil system is approximately 38,940 gallons for each train of which approximately 29,100 gallons is for the EDG.
A review of the design basis accidents considered in USAR Section 14 was performed to determine the expected longest duration for the major accident loads (for example, residual heat removal pumps, safety injection pumps, containment spray pumps). This review determined that the major loads should be considered for a maximum duration of eight hours, thereafter, the loads will be reduced.
To calculate the fuel oil consumed, ANSl N195-1976 is used. The time dependant load equation is used (including the 10% margin and periodic testing required by the standard). Although the ANSl standard applies to standby diesel generator equipment, to the extent practical, the standard was also applied to the diesel driven cooling water pumps (DDCLPs), since the Unit 1 diesel fuel oil system is shared between the EDGs and DDCLPs. Thus the DDCLP consumption included a fuel oil volume for periodic testing and 10% margin.
The EDG fuel oil consumption rate curve is based on factory and pre-operational testing data. The DDCLP consumption rate is based on the factory testing data.
Page 2 of 5
Diesel Fuel Oil RAls EDG Load Profile Considered Boundinq The bounding load profile considered is 2750 kW for the first eight hours and 1700 kW for timeframes greater than eight hours. This load profile bounds the expected loads and timeframes from the calculation which determines peak loading for the Unit 1 EDGs
( D l and D2) for the large break loss of coolant accident (LOCA). The initial eight hour timeframe bounds all design basis accident timeframes to secure the major accident loads. By using the combination of this loading and the eight hour timeframe, all design basis accident scenarios for peak loading and time to reduce the loading (that is, perform the transfer to recirculation) are bounded.
Key Assumptions The following assumptions are considered for fuel oil consumption:
- A minimum fuel oil density of 6.91 Iblgal is considered for the fuel oil consumption. This is based on guidance contained in ANSIIANS 59.51-1989, Appendix C, which specifies a minimum specific gravity of 0.83. This applies to both the EDGs and the DDCLPs.
- Any consumption rate used in the calculation is increased by 5%. This is based on review of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> surveillance EDG runs. The fuel consumed during recent 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> runs was compared to the predicted consumption based on the manufacturer's and pre-operational testing consumption rates. This review noted a maximum difference of 3.9% less than actual, so a 5% factor has been used for conservatism.
- The first eight hours of EDG loading is assumed to be at the continuous rated load of 2750 kW for the Unit 1 (DllD2) EDGs, which bounds the peak expected loading for a large break LOCA of 2555.68 kW. After the initial eight hours, the loading is assumed to be 1700 kW based on bounding the expected long term loading (recirculation loading) for a large break LOCA of 1592.27 kW.
- The assumed consumption rate per kW for the first eight hours of loading is based on the factory and pre-operational testing consumption rate at approximately 2100 kW. The assumed consumption rate per kW after the initial eight hours is based on the consumption rate at factory and pre-operational testing consumption rate at approximately 1500 kW. Engine efficiency increases as engine power increases, thus the per kW consumption rate decreases as power increases.
- One performance of SR 3.8.1.3 (22500 kW for 260 minutes) at a load of 2500 kW for 90 minutes is assumed for the EDG periodic testing.
- One performance of the DDCLP surveillance procedure is assumed. Review of recent performances of this surveillance show that the test takes approximately one hour. To be conservative, a two hour timeframe is considered for this assumption.
Page 3 of 5
Diesel Fuel Oil RAls
- The use of Ultra-Low Sulphur Diesel (ULSD) fuel oil has been considered (NRC Information Notice (IN) 2006-22), but no increase in consumption is applied.
Based on testing done in response to IN 2006-22, the energy content of fuel oil received by PlNGP was similar to previous the fuel oil. Also, recent tests of the PINGP's fuel oil show the energy content is similar to previous fuel oil.
Unit 2 diesel fuel oil consumption volume:
Calculated Volume The calculated seven day fuel oil consumption volume for the Unit 2 EDGs is approximately 41,430 gallons for each train of fuel oil.
Methodology A review of the design basis accidents considered in USAR Section 14 was performed to determine the expected longest duration for the major accident loads (for example, residual heat removal pumps, safety injection pumps, containment spray pumps). This review determined that the major loads should be considered for a maximum duration of eight hours, thereafter, the loads will be reduced.
To calculate the fuel oil consumed, ANSI N195-1976 is used. The time dependant load equation is used (including the 10% margin and periodic testing required by the standard).
The EDG fuel oil consumption rate curve is based on factory testing data.
EDG Load Profile Considered Boundinq The bounding load profile considered is 3900 kW for the first eight hours and 2700 kW for timeframes greater than eight hours. This load profile bounds the expected loads and timeframes from the calculation which determines peak loading for the Unit 2 EDGs (D5 and D6) for the large break LOCA. The initial eight hour timeframe bounds all design basis accident timeframes to secure the major accident loads. By using the combination of this loading and the eight hour timeframe, all design basis accident scenarios for peak loading and time to reduce the loading (that is, perform the transfer to recirculation) are bounded.
Key Assumptions The following assumptions are considered for fuel oil consumption:
- The minimum fuel oil specific gravity considered is 0.83. The maximum fuel oil specific gravity considered is 0.89. This is based on the guidance contained in ANSIIANS 59.51-1989, Appendix C.
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Diesel Fuel Oil RAls
- The fuel oil consumption rate is assumed to be constant at 234 gramslkw-hr (prior to consideration of any increasing factors). This consumption rate corresponds to a load of 2400 kW. This bounds the minimum identified large break LOCA load of 2452.39 kW.
- The factory testing is assumed to have been done at the maximum specific gravity, but the site fuel oil is assumed to be at the minimum specific gravity.
This is applied as a consumption increase factor of approximately 7.23%
(0.8910.83).
- The first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of EDG loading is assumed to be at a load of 3900 kW for the Unit 2 (D5lD6) EDGs, which bounds the peak expected loading for a large break LOCA of 3768.73 kW. After the initial eight hours, the loading is assumed to be 2700 kW based on bounding the expected long term loading (recirculation loading) for a large break LOCA of 2561.97 kW.
- One performance of SR 3.8.1.3 (25100 kW and 55300 kW for 260 minutes) at a load of 5400 kW for 90 minutes is assumed for the EDG periodic testing.
- The use of ULSD fuel oil has been considered (NRC IN 2006-22), but no increase in consumption is applied. Based on testing done in response to IN 2006-22, the energy content of fuel oil received by PlNGP was similar to previous the fuel oil. Also, recent tests of PINGP's fuel oil show the energy content is similar to previous fuel oil.
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