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Category:Letter
MONTHYEARIR 05000400/20230042024-01-30030 January 2024 Integrated Inspection Report 05000400/2023004 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230032023-11-0909 November 2023 Integrated Inspection Report 05000400/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230052023-08-23023 August 2023 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400/2023005) ML23234A2542023-08-22022 August 2023 RQ Inspection Notification Letter IR 05000400/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000400/2023402 IR 05000400/20230022023-07-24024 July 2023 Integrated Inspection Report 05000400/2023002 IR 05000400/20234402023-07-17017 July 2023 Special Inspection Report 05000400/2023440 and Preliminary Greater than Green Finding and Apparent Violation Cover Letter IR 05000400/20243012023-05-15015 May 2023 Notification of Licensed Operator Initial Examination 05000400/2024301 IR 05000400/20230012023-05-10010 May 2023 Integrated Inspection Report 05000400 2023001 IR 05000400/20234042023-05-0404 May 2023 Cyber Security Inspection Report 05000400/2023404 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23118A1392023-04-28028 April 2023 Submittal of Updated Final Safety Analysis Report (Amendment 65), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes IR 05000400/20234032023-04-0505 April 2023 Security Baseline Inspection Report 05000400/2023403 IR 05000400/20230102023-03-15015 March 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000400/2023010 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000400/20220062023-03-0101 March 2023 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2022006 ML23033A5272023-02-0808 February 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment No. 196 IR 05000400/20220042023-02-0707 February 2023 Integrated Inspection Report 05000400/2022004 ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000400/20220032022-11-10010 November 2022 Integrated Inspection Report 05000400/2022003 IR 05000400/20223012022-11-0202 November 2022 NRC Operator License Examination Report 05000400/2022301 ML22271A6202022-09-29029 September 2022 Notification of Shearon Harris Nuclear Power Plant Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000400/2023010 ML22258A1262022-09-14014 September 2022 NRC Operator Licensing Examination Approval 05000400/2022301 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22227A0682022-09-0202 September 2022 Alternative to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance for Certain Target Rock Solenoid Valves IR 05000400/20220052022-08-24024 August 2022 Updated Inspection Plan for Shearon Harris Nuclear Power Plant (Report 05000400/2022005) IR 05000400/20224032022-08-23023 August 2022 Security Baseline Inspection Report 05000400/2022403 ML22126A0082022-08-0909 August 2022 Issuance of Amendment No. 194 Revise Technical Specifications Related to Reactor Protection System Instrumentation P7 IR 05000400/20220022022-08-0505 August 2022 Integrated Inspection Report 05000400/2022002 ML22161B0332022-07-28028 July 2022 Issuance of Amendment No. 193 Regarding Revision of Surveillance Requirements to Remove Shutdown Limitation IR 05000400/20220112022-07-20020 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000400 2022011 IR 05000400/20224022022-06-30030 June 2022 Material Control and Accounting Program Inspection Report 05000400/2022402 (OUO Removed) IR 05000400/20220102022-06-13013 June 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000400/2022010 ML22138A4012022-05-26026 May 2022 Project Manager Reassignment ML22101A2822022-05-0606 May 2022 Regulatory Audit Summary Related to the Review of License Amendment Regarding Revising the Flood Hazard Protection Scheme IR 05000400/20220012022-05-0404 May 2022 Integrated Inspection Report 05000400/2022001 IR 05000400/20224012022-03-24024 March 2022 Security Baseline Inspection Report 05000400/2022401 ML22020A0072022-03-10010 March 2022 Issuance of Amendment No. 192 Regarding Removal of Extraneous Content and Requirements from the Renewed Facility Operating License and Technical Specifications ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 IR 05000400/20210062022-03-0202 March 2022 Annual Assessment Letter for Shearon Harris Nuclear Power Plant (Report No. 05000400/2021006) ML21351A4722022-02-10010 February 2022 Issuance of Amendment No. 190 Regarding Revision to Containment Spray Nozzle Test Frequency IR 05000400/20210042022-02-0404 February 2022 Integrated Inspection Report 05000400/2021004 ML22034A5352022-02-0202 February 2022 Notification of Licensed Operator Initial Examination 05000400/2022301 2024-01-30
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24025A1592024-01-25025 January 2024 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information - Rvi AMP and Inspection Plan (L-2023-LLL-0016) ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23082A0432023-03-23023 March 2023 002 Radiation Safety Baseline Inspection Information Request Final ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21258A3652021-09-15015 September 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000400/2021011) and Request for Information (RFI) ML21172A2432021-06-21021 June 2021 NRR E-mail Capture - Request for Additional Information - Harris RA-20-0252 - LAR to Remove Extraneous Requirements from OL and TS (L-2021-LLA-0027) ML21036A1142021-02-0505 February 2021 NRR E-mail Capture - Request for Additional Information - Harris - Relief Request RA-20-0312 - SW Pinhole Leak (L-2020-LLR-0143) ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML21032A0492021-02-0101 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet RA-20-0263 - Use of Later ASME B&Pv, XI for Repair - Replacement (L-2020-LLR-0124) ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20297A3072020-10-13013 October 2020 NRR E-mail Capture - Request for Additional Information - Shearon Harris Nuclear Power Plant, Unit 1 - RCS Flowrate Reduction/Lbloca LAR ML20274A0462020-09-29029 September 2020 Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Revision 2 ML20247J3822020-09-0303 September 2020 Request for Additional Information - Shearon Harris Nuclear Power Plant, Unit 1 - Revise TS Related to Accident Monitoring and RFO Instrumentation ML19331A4002019-11-27027 November 2019 Request for Additional Information Regarding Licensing Action to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type ML19204A2682019-07-23023 July 2019 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information for the Escw System TS AOT Extension and Removal of an Expired Note in TS Risk Informed LAR (L-2019-LLA-0025) ML19136A2712019-05-28028 May 2019 Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type ML19060A0912019-03-18018 March 2019 Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML19011A1372019-01-10010 January 2019 NRR E-mail Capture - Duke Energy Fleet RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML19007A3422018-12-21021 December 2018 NRR E-mail Capture - Duke Energy Fleet Draft RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML18332A4392018-11-28028 November 2018 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information for EAL Scheme Changes ML18337A1272018-11-28028 November 2018 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information Regarding the Rts/Esfas Trip Setpoints Modification LAR ML18264A0282018-10-0909 October 2018 RAI Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk Informed Categorization Aad Treatment of Structures, Systems and Components for Nuclear Power Reactors ML18145A1812018-06-18018 June 2018 Request for Additional Information, License Amendment Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis RA-18-0011, Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML18116A1052018-04-25025 April 2018 NRR E-mail Capture - Harris/Robinson RAIs - Change Technical Specifications to Support Performance of Core Reload Design and Safety Analyses (L-2017-LLA-0356) ML18108A7602018-04-18018 April 2018 NRR E-mail Capture - Harris/Robinson Draft RAIs - Change Technical Specifications to Support Performance of Core Reload Design and Safety Analyses (L-2017-LLA-0356) ML18058B2242018-02-26026 February 2018 Emailed Radiation Safety RFI ML18005A5482018-01-0808 January 2018 Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses (CAC No. MF9996; EPID L-2017-LLA-0303) ML17345A8772017-12-11011 December 2017 NRR E-mail Capture - Harris and Robinson Supplemental RAI - LAR to Adopt DPC-NE-3009-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis, (L-2016-LLA-0012) ML17339A0722017-12-0404 December 2017 NRR E-mail Capture - Subject: Harris and Robinson Draft Supplemental RAIs - LAR to Adopt DPC-NE-3009-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis, (L-2016-LLA-0012) ML17289A3062017-10-23023 October 2017 Shearon Harris Nuclear Plant, Unit 1 - Request for Additional Information Regarding License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements (CAC No. MF9828; EPID L-2017-LLA-0244) ML17250B0172017-09-18018 September 2017 Shearon Harris, Unit 1 - Request for Additional Information Re: License Amendment Request Proposing New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods that Exceed the LHGR Limit Detailed in RG 1.183, Table 3 (CAC No. MF9740) ML17241A0182017-08-30030 August 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Spent Fuel Storage Pool Criticality Analyses ML17192A4842017-07-11011 July 2017 NRR E-mail Capture - Duke Energy Fleet RAIs Alternative for Reactor Pressure Vessel Flange Threads Examination (MF9513 to MF9521) ML17123A1332017-05-0909 May 2017 Shearon Harris Nuclear Plant, Unit 1 - Request for Additional Information Re: License Amendment Request to Relocate Specific TS Parameters to the COLR, Remove Reference to a Plant Procedure as it Pertains to the COLR in TSs, etc. (CAC No. MF8894) ML17109A2912017-04-19019 April 2017 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Final Request for Additional Information Concerning LAR to Adopt TSTF-339, TSTF-5 and Other Administrative Changes ML16363A0112016-12-27027 December 2016 Notification of Shearon Harris Nuclear Power Plant Design Basis Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000400/2017007 ML16335A0462016-12-0606 December 2016 Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information Regarding License Amendment Request to Modify Diesel Fuel Oil Testing Surveillance Requirements (CAC No. MF7775) ML16288A0782016-10-26026 October 2016 Shearon Harris Nuclear Power Plant, Unit 1, and H.B. Robinson Steam Electric Plant, Unit No. 2 - Redacted, Request for Additional Information Re: Request to Adopt DPC-NF-2010 and DPC-NF-2011 Nuclear Design Methodology (CAC Nos. MF7693 and MF7694) ML16288A0042016-10-26026 October 2016 Shearon Harris Nuclear Plant, Unit 1 - Request For Additional Information Regarding License Amendment Request To Relocate The Explosive Gas Mixture And Liquid Holdup Tanks Technical Specifications Requirements (CAC No. MF8067) ML16223A4172016-08-0808 August 2016 Notification of Inspection and Request for Information ML16209A2642016-08-0202 August 2016 Shearon Harris Nuclear Plant, Unit 1 - Second Request For Additional Information Regarding License Amendment Request For A Temporary Change To Technical Specifications For The 'A' Emergency Service Water Pump Replacement (CAC No. MF7017) ML16028A1972016-02-0808 February 2016 Request for Additional Information Regarding License Amendment Request for a Temporary Change to Technical Specifications for the 'A' Emergency Service Water Pump Replacement ML15344A0302015-12-17017 December 2015 Request for Additional Information Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5, Thermal Hydraulic Statistical Core Design Methodology (MF5872/MF5873) ML15320A3862015-11-19019 November 2015 RAI LAR to Adopt TSTF-523 ML15314A3592015-11-10010 November 2015 Duke Energy Draft RAIs Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) ML15314A3562015-11-10010 November 2015 E-mail from J. Whited to A. Zaremba Duke Energy Draft RAIs License Amendment Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) 2024-01-25
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 11, 2009 Chris L. Burton, Vice President Shearon HNP Nuclear Power Plant Carolina Power & Light Company Post Office Box 165, Mail Zone 1 New Hill, North Carolina 27562-0165 SUB..IECT: SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT TO LOWER THE MINIMUM ALLOWED LEVEL OF THE ULTIMATE HEAT SINK MAIN RESERVOIR (TAC NO. MD8676)
Dear Mr. Burton:
By letter dated April 30, 2008, as supplemented by letter dated December 3, 2008, Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc., submitted a proposed amendment for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP).
The proposed amendment would revise Technical Specification (TS) Section 3.7.5a to restore the Ultimate Heat Sink Main Reservoir minimum level to the value allowed by the initial operating license as a result of improvements made to the Emergency Service Water system.
The change will allow continued plant operation to a Main Reservoir minimum level of 206 feet Mean Sea Level (MSL) in Mode 1-4, versus the current minimum allowed level of 215 feet MSL.
The U.S. Nuclear Regulatory Commission staff has determined that it needs additional information in order to complete its review. Kindly respond to the enclosed questions by June 30, 2009, in order to facilitate a timely completion of the staff review. Please contact me at 301-415-3178 if you have any questions on this issue, would like to participate in a conference call, or if you require additional time to submit your responses.
arlayna Vaaler, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400
Enclosure:
As stated cc w/enclosure: Distribution via ListServ
REQUEST FOR ADDITIONAL INFORMATION (RAI)
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 AMENDMENT TO LOWER THE MINIMUM ALLOWED LEVEL OF THE ULTIMATE HEAT SINK MAIN RESERVOIR DOCKET NO. 50-400
Background
The licensee submitted a License Amendment Request (LAR) to lower the minimum allowed level of the Main Reservoir of the Ultimate Heat Sink (UHS) to 206 feet. The level of the UHS when supplying water to the Service Water System (SWS) is a factor as to whether the SWS can meet the design basis stated in the Final Safety Analysis Report (FSAR) Section 9.2.1.1 b.
LAR Section 4.1, "Minimum ESW [Emergency Service Water] Flow Rates," and Section 4.2, "Minimum ESW Pressures Inside Containment," address the technical basis for revising the minimum level of the Main Reservoir to 206 feet.
RAI-1
The design basis of the SWS, as stated in FSAR Section 9.2.1.1 b, is to provide cooling water at a maximum temperature of 95 degrees Fahrenheit (OF) in order to remove essential plant heat loads by utilizing the Auxiliary Reservoir or its backup, the Main Reservoir, during emergency operation. This design basis function is performed by the ESW pumps and booster pumps.
The licensee stated in Section 4.1 of the LAR that calculation SW-0080 summarizes the minimum required flow rates for each of the components served by ESW. These flow rates are not stated in Section 4.1, nor was the explanation clear as to how the licensee will continue to meet the minimum flow rates at a Main Reservoir level of 206 feet.
Section 4.1 of the LAR states that the results of calculations SW-0080 and HNP-M/MECH-1011 show that there is positive flow margin available with a 206 feet minimum level limit in the Main Reservoir. To explain the positive flow margin, the licensee presented data from EPT-250 (A) and EPT-251 (6), recorded in 2007, and flow balance results from 2005 and 2007. The NRC staff is unclear as to how the licensee obtained the data in these tables as well as how the data in these tables show that the minimum flow requirements of the SWS are met when the Main Reservoir level is lowered to 206 feet.
Request Please answer the following questions so that the staff has the relevant information needed to make a fully informed and technically correct regulatory decision on the proposed action.
- 1. What are the minimum required flow rates to the components cooled by the ESW pumps and booster pumps to remove essential plant heat loads at a maximum service water temperature of 95°F? Please state these flow rates in the appropriate LAR section.
Enclosure
-2
- 2. Explain the EPT-250 (A) and EPT-251 (B) calculations more fully and describe what the associated data tables represent. How do the data in these tables prove that the minimum flow rates to components cooled by the ESW pumps and booster pumps will be met when the Main Reservoir level is 206 feet?
- 3. Are the "recorded gpm [gallons per minuter values actual measured flow data or are they calculated results?
- 4. How are the "limit gpm" values obtained, and what do the comparisons of "recorded gpm" and "limit gpm" mean?
- 5. The "limit gpm" values are apparently calculated for a Main Reservoir level of 206 feet. Do the results of EPT-250 (A) remain valid in that it appears that the values were obtained when lined up to the Auxiliary Reservoir at a level of 251.3 feet?
Please explain this apparent inconsistency.
- 6. Please more fully explain the meaning of "Margin [Percent]?" Does the 1596 gpm value for AH-4 of EPT-251 (B) represent the actual flow through AH-4 with a Main Reservoir level of 217.3 feet as measured by an actual flow test? Does 1368 gpm represent what the flow would have been through AH-4 if the Main Reservoir had been at 206 feet as determined by flow model and calculation? If so, would not the real flow margin be 1368 gpm/1352 gpm = a 1.2 percent margin, instead of the 16.6 percent margin listed [assuming, from calculation SW-0080, that 1352 gpm is the minimum flow required to remove the essential heat load from AH-4 with a service water temperature of 95°F at a Main Reservoir Level of 206 feet]? Please explain the basis for the 16.6 percent flow margin calculation and provide any additional information that may help the staff understand how this margin was determined.
- 7. Please correct or explain the information provided on Page 7 of the LAR: the year 2003 does not correspond to any of the data tables and is apparently a typographical error.
- 8. Please ensure that all calculations referenced in the LAR contain revision numbers.
- 9. Section 4.1 of the LAR states that "SW-0080 also assumes that the failure of breaker MCC 1B35SB is the most limiting single failure affecting the 'A' train when, in fact, the loss of an entire ESW train is the most limiting in terms of the entire ESW system." Please explain the significance and relevance of this statement in regard to lowering the Main Reservoir level to 206 feet, as well as how this assumption adds conservatism to the flow limit results of calculation SW-0080.
- 10. Explain the process by which the licensee will ensure that the minimum Main Reservoir level [proposed to be 206 feet] will continue to be satisfactory over time with respect to ESW flow rates and pressure in containment as the system degrades over time.
-3
RAI-2
FSAR Section 9.2.1, "Service Water System," states that under accident conditions, the service water booster pumps, in conjunction with the containment fan cooler orifice bypass valves, will function to maintain the service water pressure inside the coolers above the containment design pressure to prevent leaks into the SWS.
Section 4.2 of the LAR states that calculation HNP-M/MECH-1 011 demonstrates that there is positive pressure margin available with a 206 feet minimum level in the Main Reservoir. Since the ESW Pumps and the ESW Booster Pumps both contribute to ESW pressure inside containment, the figures shown in the submittal provide the minimum allowable pump differential pressures for both pumps of each train on a single graph. The NRC staff is not clear as to how the licensee generated the figures in the LAR shown on pages 10 of 23 and 11 of 23, and how these figures demonstrate that the licensee will continue to meet the minimum service water pressure requirements inside the containment coolers.
Request Please answer the following questions so that the staff has the relevant information needed to make a fully informed and technically correct regulatory decision on the proposed action.
- 1. Explain the shape of the graphs for the "A" and "B" ESW and Booster Pumps, and how the graphs prove that the required service water pressure will be available when the Main Reservoir level is at 206 feet.
- 2. Explain why 95.1 pounds per square inch (psi) is the minimum A ESW Pump differential pressure. Per the staff's understanding of the graph, why would 90 psi not be sufficient?
- 3. Explain why 50.7 psi is the minimum A ESW Booster Pump differential pressure.
Why would not 49 psi be sufficient, if the A ESW Pump differential pressure were raised?
- 4. Explain the Operations Surveillance Tests (OST) and how they are different I related to the EPT data from Section 4.1 of the LAR. In addition, provide a frequency on how often these tests are performed for each ESW pump and ESW booster pump.
- 5. How are the values of the OST 1214 and OST 1215 test windows determined and what do the test windows mean (Le., what establishes the upper limits and edges of the curves depicted? explain the surveillance requirement box and the curve derivations)?
- 6. Section 4.8, "OST Considerations," of the LAR states that the IliA' ESW Booster Pump should continue to remain above this new minimum limit." What will be the course of action if the 'A' ESW Booster Pump does not remain above the new limit?
- 4
- 7. Section 4.2 of the LAR states that the results of calculation HNP-M/MECH-1011 show that ESW pressure, not flow, currently defines the available ESW system margin. Do the differential pressure limits shown in the figures on pages 10 of 23 and 11 of 23 in the LAR reflect limits based on ESW flow or ESW pressure or both?
Please explain.
June 11, 2009 Chris L. Burton, Vice President Shearon HNP Nuclear Power Plant Carolina Power & Light Company Post Office Box 165, Mail Zone 1 New Hill, North Carolina 27562-0165
SUBJECT:
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT TO LOWER THE MINIMUM ALLOWED LEVEL OF THE ULTIMATE HEAT SINK MAIN RESERVOIR (TAC NO. MD8676)
Dear Mr. Burton:
By letter dated April 30, 2008, as supplemented by letter dated December 3, 2008, Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc., submitted a proposed amendment for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP).
The proposed amendment would revise Technical Specification (TS) Section 3.7.5a to restore the Ultimate Heat Sink Main Reservoir minimum level to the value allowed by the initial operating license as a result of improvements made to the Emergency Service Water system.
The change will allow continued plant operation to a Main Reservoir minimum level of 206 feet Mean Sea Level (MSL) in Mode 1-4, versus the current minimum allowed level of 215 feet MSL.
The U.S. Nuclear Regulatory Commission staff has determined that it needs additional information in order to complete its review. Kindly respond to the enclosed questions by June 30, 2009, in order to facilitate a timely completion of the staff review. Please contact me at 301-415-3178 if you have any questions on this issue, would like to participate in a conference call, or if you require additional time to submit your responses.
Sincerely, IRA!
Marlayna Vaaler, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400
Enclosure:
As stated cc w/enclosure: Distribution via ListServ DISTRIBUTION:
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