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| | number = ML16271A205 | | | number = ML16271A205 |
| | issue date = 11/02/2016 | | | issue date = 11/02/2016 |
| | title = Hope Creek Generating Station - Request for Additional Information Regarding Request to Delete Technical Specifications Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves | | | title = Request for Additional Information Regarding Request to Delete Technical Specifications Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves |
| | author name = Parker C J | | | author name = Parker C |
| | author affiliation = NRC/NRR/DORL/LPLI-2 | | | author affiliation = NRC/NRR/DORL/LPLI-2 |
| | addressee name = Sena P P | | | addressee name = Sena P |
| | addressee affiliation = PSEG Nuclear, LLC | | | addressee affiliation = PSEG Nuclear, LLC |
| | docket = 05000354 | | | docket = 05000354 |
| | license number = NPF-057 | | | license number = NPF-057 |
| | contact person = Parker C J, NRR/DORL/LPLI-II, 415-1603 | | | contact person = Parker C, NRR/DORL/LPLI-II, 415-1603 |
| | case reference number = CAC MF7709 | | | case reference number = CAC MF7709 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:Mr. Peter P. Sena, Ill President PSEG Nuclear LLC -N09 P.O. Box 236 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 2, 2016 Hancocks Bridge, NJ 08038 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 2, 2016 Mr. Peter P. Sena, Ill President PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| HOPE CREEK GENERATING STATION-REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST TO DELETE TECHNICAL SPECIFICATION ACTION STATEMENT 3.4.2.1.b ASSOCIATED WITH STUCK OPEN SAFETY/RELIEF VALVES (CAC NO. MF7709) | | HOPE CREEK GENERATING STATION- REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST TO DELETE TECHNICAL SPECIFICATION ACTION STATEMENT 3.4.2.1.b ASSOCIATED WITH STUCK OPEN SAFETY/RELIEF VALVES (CAC NO. MF7709) |
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| ==Dear Mr. Sena:== | | ==Dear Mr. Sena:== |
| By letter dated May 11, 2016 (Agencywide Documents Access and Management System Accession No. ML 16132A374), PSEG Nuclear LLC (PSEG, the licensee) submitted a license amendment request (LAR) for Hope Creek Generating Station (Hope Creek). The LAR proposes to revise Hope Creek's Technical Specification (TS) requirements by deleting TS Action Statement 3.4.2.1.b concerning stuck open safety/relief valves. The U.S. Nuclear Regulatory Commission staff has reviewed the licensee's application and, based upon this review, determined that additional information is needed to complete our review. On September 22, 2016, a draft of these questions was sent to Mr. Paul Duke of your staff to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. | | |
| On October 18, 2016, a teleconference was held to clarify the questions. | | By letter dated May 11, 2016 (Agencywide Documents Access and Management System Accession No. ML16132A374), PSEG Nuclear LLC (PSEG, the licensee) submitted a license amendment request (LAR) for Hope Creek Generating Station (Hope Creek). The LAR proposes to revise Hope Creek's Technical Specification (TS) requirements by deleting TS Action Statement 3.4.2.1.b concerning stuck open safety/relief valves. |
| On October 24, 2016, Mr. Duke indicated that PSEG will submit a response within 45 days of the date of this letter. | | The U.S. Nuclear Regulatory Commission staff has reviewed the licensee's application and, based upon this review, determined that additional information is needed to complete our review. On September 22, 2016, a draft of these questions was sent to Mr. Paul Duke of your staff to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. On October 18, 2016, a teleconference was held to clarify the questions. On October 24, 2016, Mr. Duke indicated that PSEG will submit a response within 45 days of the date of this letter. |
| P.Sena If you have any questions, please contact me at (301) 415-1603 or by e-mail at Carleen.Parker@nrc.gov. | | |
| Docket No. 50-354 | | P.Sena If you have any questions, please contact me at (301) 415-1603 or by e-mail at Carleen.Parker@nrc.gov. |
| | Sincerely, |
| | ~ , \>.J-Carleen J arker, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Request for Additional Information cc w/enclosure: | | Request for Additional Information cc w/enclosure: Distribution via Listserv |
| Distribution via Listserv Sincerely, , \>.J-Carleen J arker, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION REQUEST TO DELETE TECHNICAL SPECIFICATION ACTION STATEMENT 3.4.2.1.b ASSOCIATED WITH STUCK OPEN SAFETY/RELIEF VALVES PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By letter dated May 11, 2016 (Agencywide Documents Access and Management System Accession No. ML 16132A374), PSEG Nuclear LLC (the licensee) submitted a license amendment request (LAR) for Hope Creek Generating Station (Hope Creek). The LAR proposes to revise Hope Creek's Technical Specification (TS) requirements by deleting TS Action Statement 3.4.2.1.b concerning stuck open safety/relief valves. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the application and, based upon this review, determined that additional information requested below is needed to complete our review. TS Action Statement 3.4.2.1.b currently states: With one or more safety/relief valves stuck open, provided that suppression pool average water temperature is less than 110°F, close the stuck open safety relief valve(s); | | |
| if unable to close the stuck open valve(s) within 2 minutes or if suppression pool average water temperature is 110°F or greater, place the reactor mode switch in the Shutdown position. | | REQUEST FOR ADDITIONAL INFORMATION REQUEST TO DELETE TECHNICAL SPECIFICATION ACTION STATEMENT 3.4.2.1.b ASSOCIATED WITH STUCK OPEN SAFETY/RELIEF VALVES PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By letter dated May 11, 2016 (Agencywide Documents Access and Management System Accession No. ML16132A374), PSEG Nuclear LLC (the licensee) submitted a license amendment request (LAR) for Hope Creek Generating Station (Hope Creek). The LAR proposes to revise Hope Creek's Technical Specification (TS) requirements by deleting TS Action Statement 3.4.2.1.b concerning stuck open safety/relief valves. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the application and, based upon this review, determined that additional information requested below is needed to complete our review. |
| TS 3.6.2.1 Action b.2, also requires the reactor mode switch to be placed in the shutdown position when the suppression chamber average water temperate exceeds 110 degrees Fahrenheit | | TS Action Statement 3.4.2.1.b currently states: |
| (°F), while in Modes 1, 2, and 3. The licensee states that this action will remain unchanged and provides appropriate remedial action, permitted by TSs, until the limiting condition for operation can be met. Title 1 O of the Code of Federal Regulations (1 O CFR), Section 50.36, "Technical specifications," establishes the NRC's regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: | | With one or more safety/relief valves stuck open, provided that suppression pool average water temperature is less than 110°F, close the stuck open safety relief valve(s); if unable to close the stuck open valve(s) within 2 minutes or if suppression pool average water temperature is 110°F or greater, place the reactor mode switch in the Shutdown position. |
| (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls. | | TS 3.6.2.1 Action b.2, also requires the reactor mode switch to be placed in the shutdown position when the suppression chamber average water temperate exceeds 110 degrees Fahrenheit (°F), while in Modes 1, 2, and 3. The licensee states that this action will remain unchanged and provides appropriate remedial action, permitted by TSs, until the limiting condition for operation can be met. |
| Request for Additional Information In order for the staff to evaluate the licensee's proposed deletion of TS 3.4.2.1, Action b associated with the subject safety-relief valves (SRVs), the NRC staff requests the following additional information: | | Title 1O of the Code of Federal Regulations (1 O CFR), Section 50.36, "Technical specifications," |
| : 1. Since TS requirements are derived from a licensee's licensing basis, please (1) provide documentation/references related to Hope Creek's current licensing Enclosure basis that requires inclusion of the '2 minute' SRV closure requirement in TS 3.4.2.1.b, and (2) indicate how long this requirement has been in the current TSs. 2. Please provide additional justification (such as operating experience, etc.) for the deletion of the proposed change. In order for the staff to evaluate the licensee's statement that the requirement for the reactor mode switch to be placed in the shutdown position when the suppression chamber average water temperate exceeds 110 °F while in Modes 1, 2, and 3 will not be changed, the NRC staff requests the following additional information | | establishes the NRC's regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls. |
| : 3. Please clarify when TS 3.6.2.1 Action b.2 applies. Specifically, address the applicable thermal power. 4. For TS 3.6.2.1 Action b, for a stuck open SRV in Modes 1, 2, or 3, how is the requirement to place the mode switch in shutdown accomplished during the allowed time to restore temperature below the maximum average temperature of 95 °F? | | Request for Additional Information In order for the staff to evaluate the licensee's proposed deletion of TS 3.4.2.1, Action b associated with the subject safety-relief valves (SRVs), the NRC staff requests the following additional information: |
| P. Sena If you have any questions, please contact me at (301) 415-1603 or by e-mail at Carleen.Parker@nrc.gov. | | : 1. Since TS requirements are derived from a licensee's licensing basis, please (1) provide documentation/references related to Hope Creek's current licensing Enclosure |
| Docket No. 50-354 | | |
| | basis that requires inclusion of the '2 minute' SRV closure requirement in TS 3.4.2.1.b, and (2) indicate how long this requirement has been in the current TSs. |
| | : 2. Please provide additional justification (such as operating experience, etc.) for the deletion of the proposed change. |
| | In order for the staff to evaluate the licensee's statement that the requirement for the reactor mode switch to be placed in the shutdown position when the suppression chamber average water temperate exceeds 110 °F while in Modes 1, 2, and 3 will not be changed, the NRC staff requests the following additional information |
| | : 3. Please clarify when TS 3.6.2.1 Action b.2 applies. Specifically, address the applicable thermal power. |
| | : 4. For TS 3.6.2.1 Action b, for a stuck open SRV in Modes 1, 2, or 3, how is the requirement to place the mode switch in shutdown accomplished during the allowed time to restore temperature below the maximum average temperature of 95 °F? |
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| | P. Sena If you have any questions, please contact me at (301) 415-1603 or by e-mail at Carleen.Parker@nrc.gov. |
| | Sincerely, IRA/ |
| | Carleen J. Parker, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Request for Additional Information cc w/enclosure: | | Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION: |
| Distribution via Listserv DISTRIBUTION: | | PUBLIC RidsRgn1 MailCenter Resource LPL 1-2 R/F RidsNrrDssStsb Resource RidsNrrDorllpl1-2 Resource LWheeler, NRR RidsNrrLALRonewicz Resource RGrover, NRR RidsNrrPMHopeCreek Resource RBeaton, NRR RidsACRS_MailCTR Resource ADAMS A ccess1on No.: ML16271A205 *b>Y e-ma1*1 d ae t d OFFICE DORL/LPL 1-2/PM DORL/LPL 1-2/LA DSS/STSB/BC* DORL/LPL 1-2/BC(A) DORL/LPL 1-2/PM NAME CParker LRonewicz AK le in SKoenick CParker DATE 10/26/16 10/6/16 9/15/2016 11/02/16 11/2/16 OFFICIAL RECORD COPY}} |
| PUBLIC LPL 1-2 R/F RidsNrrDorllpl1-2 Resource RidsNrrLALRonewicz Resource RidsNrrPMHopeCreek Resource RidsACRS_MailCTR Resource ADAMS A ccess1on N o.: ML16271A205 OFFICE DORL/LPL 1-2/PM DORL/LPL 1-2/LA NAME CParker LRonewicz DATE 10/26/16 10/6/16 Sincerely, IRA/ Carleen J. Parker, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsRgn1 MailCenter Resource RidsNrrDssStsb Resource LWheeler, NRR RGrover, NRR RBeaton, NRR *b *1 d t d >Y e-ma1 ae DSS/STSB/BC* | |
| DORL/LPL 1-2/BC(A) | |
| AK le in SKoenick 9/15/2016 11/02/16 DORL/LPL 1-2/PM CParker 11/2/16 OFFICIAL RECORD COPY}} | |
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Category:Letter
MONTHYEARIR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval ML24009A1022024-01-26026 January 2024 Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000354/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000354/2023401 ML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000354/20230032023-11-0707 November 2023 Integrated Inspection Report 05000354/2023003 IR 05000272/20234022023-10-12012 October 2023 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only) LR-N23-0065, Submittal of 2023 Annual 10 CFR 50.46 Report2023-10-0202 October 2023 Submittal of 2023 Annual 10 CFR 50.46 Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000354/20230052023-08-31031 August 2023 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2023005) ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 IR 05000354/20230102023-08-0303 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000354/2023010 LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.12023-07-31031 July 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1 LR-N23-0042, Spent Fuel Cask Registration2023-07-12012 July 2023 Spent Fuel Cask Registration LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 IR 05000354/20230112023-05-0101 May 2023 Commercial Grade Dedication Report 05000354/2023011 ML23121A1412023-05-0101 May 2023 Senior Reactor and Reactor Operator Initial License Examinations LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) IR 05000354/20230012023-04-26026 April 2023 Integrated Inspection Report 05000354/2023001 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023 License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23089A0942023-04-17017 April 2023 NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23086A0912023-03-24024 March 2023 NMFS to NRC, Transmittal of Biological Opinion for Continued Operations of Salem and Hope Creek Nuclear Generating Stations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums ML23037A9712023-03-0909 March 2023 and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report IR 05000354/20220062023-03-0101 March 2023 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2022006) LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0018, Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges2023-02-27027 February 2023 Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 IR 05000354/20220042023-01-24024 January 2023 Integrated Inspection Report 05000354/2022004 LR-N23-0011, In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage2023-01-19019 January 2023 In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023 and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022 Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments ML22335A0412022-12-0101 December 2022 Notification of Commercial Grade Dedication Inspection (05000354/2023011) and Request for Information IR 05000354/20220032022-11-0303 November 2022 Integrated Inspection Report 05000354/2022003 2024-02-01
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML22006A3212022-01-0606 January 2022 NRR E-mail Capture - Final RAI - Hope Creek - Revise TS Limits for Ultimate Heat Sink ML21300A0222021-10-27027 October 2021 Notification of Conduct of a Fire Protection Team Inspection ML21041A3972021-02-18018 February 2021 Request for Additional Information Revise Low Pressure Safety Limit to Address General Electric Part-21 Safety Communications (Non-Proprietary) ML20295A4922020-10-21021 October 2020 NRR E-mail Capture - Hope Creek - Final RAI Revise ECCS TS with Respect to HPCI System Inoperability (L-2020-LLA-0131) ML18263A1442018-09-12012 September 2018 NRR E-mail Capture - Final RAI from Apla: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101) ML18250A3142018-09-0606 September 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101) ML18150A6912018-05-30030 May 2018 NRR E-mail Capture - Hope Creek - Final RAI Revise TS to Adopt TSTF-542 ML18120A2482018-04-27027 April 2018 Information Request for the Cyber-Security Inspection, Notification to Perform Inspection 05000354/2018403 ML18094B0832018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to P. Duke RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for Salem and Hope Creek, and Peach Bottom ISFSIs Docket Nos. 72-48 and 72-29) ML17349A0812017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Reactor Systems Branch (Srxb) - Hope Creek Mur ML17348A9972017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Steam Dryer Analysis with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17348A6242017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Human Factors Associated with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17331A0072017-11-21021 November 2017 E-mail Regarding Final Eicb Request for Additional Information - Hope Creek Power Uprate ML17348A6282017-11-21021 November 2017 NRR E-mail Capture - Draft Request for Additional Information for Steam Dryer Analysis with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17324A2602017-11-17017 November 2017 NRR E-mail Capture - Final Request for Additional Information - Hope Creek Mur Electrical Instrumentation and Controls ML17320A2152017-11-16016 November 2017 NRR E-mail Capture - Hope Creek Measurement Uncertainty Recapture Application Review - Electrical Engineering (Eeob) Request for Additional Information (L-2017-LLS-0002) ML17290B0132017-10-17017 October 2017 NRR E-mail Capture - Hope Creek Mur Request for Additional Information for Apla and Snpb ML17222A1652017-08-10010 August 2017 NRR E-mail Capture - Hope Creek: Final Request for Information, Pressure-Temperature Limit Report Request (MF9502) ML17181A1352017-06-29029 June 2017 NRR E-mail Capture - Request for Additional Information Related to Hope Creek and Salem Emergency Action Level Scheme Change License Amendment Request (MF9268/69/70) ML17164A4062017-06-13013 June 2017 NRR E-mail Capture - Hope Creek - Final Request for Additional Information Concerning ILRT (MF8462) ML17027A3282017-02-27027 February 2017 Request for Additional Information Regarding License Amendment Request to Permanently Extend Type a and Type C Leak Rate Test Frequencies ML16321A4642016-11-21021 November 2016 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request for Additional Information Regarding License Amendment Request to Remove Certain Training Requirements ML16277A5142016-11-0303 November 2016 Request for Additional Information Regarding License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling ML16271A2052016-11-0202 November 2016 Request for Additional Information Regarding Request to Delete Technical Specifications Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves ML16231A4272016-08-24024 August 2016 Request for Additional Information Regarding Relief Request VR-02, Associated with the Fourth 10-Year Inservice Test Interval ML16217A4302016-08-17017 August 2016 Request for Additional Information Regarding Digital Power Range Neutron Monitoring System Upgrade ML16007A1742016-05-31031 May 2016 Request for Additional Information Regarding Review of Post-EPU Steam Dryer Stress Calculation Acoustic Circuit Model Software Error ML16089A0792016-05-0505 May 2016 Request for Additional Information Regarding Relief Requests GR-01, PR-01, PR-02, VR-01, and VR-02, Associated with the Fourth 10-Year Inservice Test Interval ML16124A5802016-05-0303 May 2016 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Redacted - Request for Additional Information Review of Security Plan Revision 17 Changes ML15055A3772015-03-10010 March 2015 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Request for Additional Information Request to Update Appendix B to Renewed Facility Operating License DPR-70, DPR-75 and NPF-57 ML14197A6192014-07-24024 July 2014 and Salem Nuclear Generating Station, Units 1 and 2 - Request for Additional Information Regarding Cyber Security Plan Milestone 8 Implementation Schedule (Tac Nos. MF3384, MF3385 and MF3386) ML14168A2352014-07-0202 July 2014 Request for Additional Information Regarding Flooding Hazard Reevaluation ML13309B5922013-11-22022 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13168A2762013-08-12012 August 2013 Peach Bottom, Units 2 and 3, Request for Additional Information Decommissioning Funding Status Report (TAC No. MF2202; MF2227; MF2228) ML13193A2912013-07-22022 July 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) TAC MF1031 ML13204A2532013-07-19019 July 2013 Draft RAIs - Decommissioning Funding Status Report for Hope Creek and Peach Bottom ML13190A2212013-07-0202 July 2013 RAIs for Hope Creek Regarding Response to Order EA-12-051 ML13154A4952013-06-0404 June 2013 Rai'S Following Ifib Analysis of Pseg'S 2013 Decommissioning Funding Status Report for Hope Creek Generating Station ML12334A3102012-12-0505 December 2012 Request for Additional Information Request to Correct Technical Specification and Facility Operating License Editorial Items ML12310A1672012-11-0101 November 2012 Draft RAI to License Amendment Request Regarding Average Power Range Monitoring Operability Requirements in Operational Condition 5 ML1227901012012-10-0505 October 2012 Clarifying Information for Question No. 4 (with Attachment) ML12212A1032012-08-0808 August 2012 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Request for Additional Information ML12216A1792012-08-0303 August 2012 Draft RAI Related to Request for Exemption from Certain Requirements of the Fitness for Duty Rule ML12213A6162012-07-30030 July 2012 Draft Request for Additional Information Related to Request for Exemption from Certain Requirements of the Fitness for Duty Rule ML1209002372012-03-29029 March 2012 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Draft Request for Additional Information ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic ML12056A0472012-03-12012 March 2012 Enclosure 1 - Recommendation 2.1: Seismic 2022-01-06
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 2, 2016 Mr. Peter P. Sena, Ill President PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION- REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST TO DELETE TECHNICAL SPECIFICATION ACTION STATEMENT 3.4.2.1.b ASSOCIATED WITH STUCK OPEN SAFETY/RELIEF VALVES (CAC NO. MF7709)
Dear Mr. Sena:
By letter dated May 11, 2016 (Agencywide Documents Access and Management System Accession No. ML16132A374), PSEG Nuclear LLC (PSEG, the licensee) submitted a license amendment request (LAR) for Hope Creek Generating Station (Hope Creek). The LAR proposes to revise Hope Creek's Technical Specification (TS) requirements by deleting TS Action Statement 3.4.2.1.b concerning stuck open safety/relief valves.
The U.S. Nuclear Regulatory Commission staff has reviewed the licensee's application and, based upon this review, determined that additional information is needed to complete our review. On September 22, 2016, a draft of these questions was sent to Mr. Paul Duke of your staff to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. On October 18, 2016, a teleconference was held to clarify the questions. On October 24, 2016, Mr. Duke indicated that PSEG will submit a response within 45 days of the date of this letter.
P.Sena If you have any questions, please contact me at (301) 415-1603 or by e-mail at Carleen.Parker@nrc.gov.
Sincerely,
~ , \>.J-Carleen J arker, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION REQUEST TO DELETE TECHNICAL SPECIFICATION ACTION STATEMENT 3.4.2.1.b ASSOCIATED WITH STUCK OPEN SAFETY/RELIEF VALVES PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By letter dated May 11, 2016 (Agencywide Documents Access and Management System Accession No. ML16132A374), PSEG Nuclear LLC (the licensee) submitted a license amendment request (LAR) for Hope Creek Generating Station (Hope Creek). The LAR proposes to revise Hope Creek's Technical Specification (TS) requirements by deleting TS Action Statement 3.4.2.1.b concerning stuck open safety/relief valves. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the application and, based upon this review, determined that additional information requested below is needed to complete our review.
TS Action Statement 3.4.2.1.b currently states:
With one or more safety/relief valves stuck open, provided that suppression pool average water temperature is less than 110°F, close the stuck open safety relief valve(s); if unable to close the stuck open valve(s) within 2 minutes or if suppression pool average water temperature is 110°F or greater, place the reactor mode switch in the Shutdown position.
TS 3.6.2.1 Action b.2, also requires the reactor mode switch to be placed in the shutdown position when the suppression chamber average water temperate exceeds 110 degrees Fahrenheit (°F), while in Modes 1, 2, and 3. The licensee states that this action will remain unchanged and provides appropriate remedial action, permitted by TSs, until the limiting condition for operation can be met.
Title 1O of the Code of Federal Regulations (1 O CFR), Section 50.36, "Technical specifications,"
establishes the NRC's regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls.
Request for Additional Information In order for the staff to evaluate the licensee's proposed deletion of TS 3.4.2.1, Action b associated with the subject safety-relief valves (SRVs), the NRC staff requests the following additional information:
- 1. Since TS requirements are derived from a licensee's licensing basis, please (1) provide documentation/references related to Hope Creek's current licensing Enclosure
basis that requires inclusion of the '2 minute' SRV closure requirement in TS 3.4.2.1.b, and (2) indicate how long this requirement has been in the current TSs.
- 2. Please provide additional justification (such as operating experience, etc.) for the deletion of the proposed change.
In order for the staff to evaluate the licensee's statement that the requirement for the reactor mode switch to be placed in the shutdown position when the suppression chamber average water temperate exceeds 110 °F while in Modes 1, 2, and 3 will not be changed, the NRC staff requests the following additional information
- 3. Please clarify when TS 3.6.2.1 Action b.2 applies. Specifically, address the applicable thermal power.
- 4. For TS 3.6.2.1 Action b, for a stuck open SRV in Modes 1, 2, or 3, how is the requirement to place the mode switch in shutdown accomplished during the allowed time to restore temperature below the maximum average temperature of 95 °F?
P. Sena If you have any questions, please contact me at (301) 415-1603 or by e-mail at Carleen.Parker@nrc.gov.
Sincerely, IRA/
Carleen J. Parker, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsRgn1 MailCenter Resource LPL 1-2 R/F RidsNrrDssStsb Resource RidsNrrDorllpl1-2 Resource LWheeler, NRR RidsNrrLALRonewicz Resource RGrover, NRR RidsNrrPMHopeCreek Resource RBeaton, NRR RidsACRS_MailCTR Resource ADAMS A ccess1on No.: ML16271A205 *b>Y e-ma1*1 d ae t d OFFICE DORL/LPL 1-2/PM DORL/LPL 1-2/LA DSS/STSB/BC* DORL/LPL 1-2/BC(A) DORL/LPL 1-2/PM NAME CParker LRonewicz AK le in SKoenick CParker DATE 10/26/16 10/6/16 9/15/2016 11/02/16 11/2/16 OFFICIAL RECORD COPY