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| | number = ML16231A427 | | | number = ML16231A427 |
| | issue date = 08/24/2016 | | | issue date = 08/24/2016 |
| | title = Hope Creek Generating Station Request for Additional Information Regarding Relief Request VR-02, Associated with the Fourth 10-Year Inservice Test Interval | | | title = Request for Additional Information Regarding Relief Request VR-02, Associated with the Fourth 10-Year Inservice Test Interval |
| | 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 MF7201 | | | case reference number = CAC MF7201 |
| | 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 August 24, 2016 Hancocks Bridge, NJ 08038 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 24, 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 RELIEF REQUEST VR-02, ASSOCIATED WITH THE FOURTH 10-YEAR INSERVICE TEST INTERVAL (CAC NO. MF7201) | | HOPE CREEK GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST VR-02, ASSOCIATED WITH THE FOURTH 10-YEAR INSERVICE TEST INTERVAL (CAC NO. MF7201) |
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| ==Dear Mr. Sena:== | | ==Dear Mr. Sena:== |
| By letter dated December 18, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15352A127), as supplemented by letter dated June 10, 2016 (ADAMS Accession No. ML 16162A709), PSEG Nuclear LLC (PSEG or the licensee) submitted Relief Requests GR-01, PR-01, PR-02, VR-01, and VR-02, for the fourth 10-year inservice testing interval for the Hope Creek Generating Station. These proposed alternatives apply to certain requirements of the American Society of Mechanical Engineers Code for the Operation and Maintenance of Nuclear Power Plants and were submitted pursuant to Title 10 of the Code of Federal Regulations Sections 50.55a(a)(z)(1) and 50.55a(a)(z)(2). | | |
| The U.S. Nuclear Regulatory Commission staff has reviewed the licensee's application and, based upon this review, determined that additional information is needed for Relief Request VR-02, "Main Steam Safety Relief Valves," as set forth in the enclosed Request for Additional Information. | | By letter dated December 18, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15352A127), as supplemented by letter dated June 10, 2016 (ADAMS Accession No. ML16162A709), PSEG Nuclear LLC (PSEG or the licensee) submitted Relief Requests GR-01, PR-01, PR-02, VR-01, and VR-02, for the fourth 10-year inservice testing interval for the Hope Creek Generating Station. These proposed alternatives apply to certain requirements of the American Society of Mechanical Engineers Code for the Operation and Maintenance of Nuclear Power Plants and were submitted pursuant to Title 10 of the Code of Federal Regulations Sections 50.55a(a)(z)(1) and 50.55a(a)(z)(2). |
| On August 3, 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. | | The U.S. Nuclear Regulatory Commission staff has reviewed the licensee's application and, based upon this review, determined that additional information is needed for Relief Request VR-02, "Main Steam Safety Relief Valves," as set forth in the enclosed Request for Additional Information. On August 3, 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 August 18, 2016, a teleconference was held to clarify the questions. Mr. Duke indicated that PSEG will submit a response within 30 days of the date of this letter. |
| On August 18, 2016, a teleconference was held to clarify the questions. | | |
| Mr. Duke indicated that PSEG will submit a response within 30 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. |
| P. Sena If you have any questions, please contact me at (301) 415-1603 or by e-mail at Carleen.Parker@nrc.gov. | | Carleen J. a ker, Project Manager Plant Licens , g Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 |
| 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 Carleen J. a ker, Project Manager Plant Licens , g Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST VR-02 FOR THE INSERVICE TESTING PROGRAM FOURTH 10-YEAR INTERVAL PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By letter dated December 18, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15352A127), as supplemented by letter dated June 10, 2016 (ADAMS Accession No. ML 16162A709), PSEG Nuclear LLC submitted Relief Requests GR-01, PR-01, PR-02, VR-01, and VR-02, for the fourth 10-year inservice testing interval for the Hope Creek Generating Station. These proposed alternatives apply to certain requirements of the American Society of Mechanical Engineers Code for the Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and were submitted pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Sections 50.55a(a)(z)(1) and 50.55a(a)(z)(2). | | |
| The U.S. Nuclear Regulatory Commission staff has reviewed the licensee's application and, based upon this review, determined that following additional information is needed for Relief Request VR-02: Relief Request VR-02: The regulations in 10 CFR 50.55a(f), "lnservice testing requirements," require, in part, that inservice testing of certain ASME Code Class 1, 2, and 3 components must meet the requirements of the ASME OM Code and applicable addenda, except where alternatives have been authorized pursuant to paragraphs 10 CFR 50.55a(z)(1) or 10 CFR 50.55a(z)(2). | | REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST VR-02 FOR THE INSERVICE TESTING PROGRAM FOURTH 10-YEAR INTERVAL PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By letter dated December 18, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15352A127), as supplemented by letter dated June 10, 2016 (ADAMS Accession No. ML16162A709), PSEG Nuclear LLC submitted Relief Requests GR-01, PR-01, PR-02, VR-01, and VR-02, for the fourth 10-year inservice testing interval for the Hope Creek Generating Station. These proposed alternatives apply to certain requirements of the American Society of Mechanical Engineers Code for the Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and were submitted pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Sections 50.55a(a)(z)(1) and 50.55a(a)(z)(2). The U.S. Nuclear Regulatory Commission staff has reviewed the licensee's application and, based upon this review, determined that following additional information is needed for Relief Request VR-02: |
| : 1. How will the ASME OM Code sample test requirement of l-1320(a) (i.e., 20 percent per 24 months) be applied to the main steam pressure relief valves? 2. How will the 20 percent be determined? | | Relief Request VR-02: |
| : 3. Will the two stage and three stage Target Rock valves be in separate groups (a group being defined in accordance with 1-1200)? 4. How will the change in the number of three stage versus two stage Target Rock valves affect the grouping(s)? | | The regulations in 10 CFR 50.55a(f), "lnservice testing requirements," require, in part, that inservice testing of certain ASME Code Class 1, 2, and 3 components must meet the requirements of the ASME OM Code and applicable addenda, except where alternatives have been authorized pursuant to paragraphs 10 CFR 50.55a(z)(1) or 10 CFR 50.55a(z)(2). |
| P.Sena If you have any questions, please contact me at (301) 415-1603 or by e-mail at Carleen.Parker@nrc.gov. | | : 1. How will the ASME OM Code sample test requirement of l-1320(a) (i.e., 20 percent per 24 months) be applied to the main steam pressure relief valves? |
| Sincerely, /RA/ Carleen J. Parker, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 | | : 2. How will the 20 percent be determined? |
| | : 3. Will the two stage and three stage Target Rock valves be in separate groups (a group being defined in accordance with 1-1200)? |
| | : 4. How will the change in the number of three stage versus two stage Target Rock valves affect the grouping(s)? |
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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, |
| | /RA/ |
| | 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 RidsNrrPMHopeCreek Resource RidsNrrLALRonewicz Resource ResourceRidsNrrDeEpnb Resource MHamm, NRR LPLl-2 R/F RidsRgn1 MailCenter Resource RidsNrrDorlLpl1-2 Resource JBillerbeck, NRR RidsACRS_MailCTR Resource RidsNrrDorlDpr Resource ADAMS A ccess1on No.: ML16231A427 *b>V e-ma1 OFFICE DORL/LPL 1-2/PM DORL/LPL 1-2/LA DE/EPNB/BC* DORL/LPL 1-2/BC DORL/LPL 1-2/PM NAME CParker LRonewicz DAiiey DBroaddus CSanders DATE 08/23/16 08/22/16 07/12/16 08/23/16 08/24/16 OFFICIAL RECORD COPY}} |
| PUBLIC RidsNrrPMHopeCreek Resource ResourceRidsNrrDeEpnb Resource MHamm, NRR RidsRgn1 MailCenter Resource RidsNrrDorlLpl1-2 Resource RidsACRS_MailCTR Resource RidsNrrDorlDpr Resource ADAMS A ccess1on N o.: ML 16231A427 OFFICE DORL/LPL 1-2/PM DORL/LPL 1-2/LA DE/EPNB/BC* | |
| NAME CParker LRonewicz DAiiey DATE 08/23/16 08/22/16 07/12/16 OFFICIAL RECORD COPY RidsNrrLALRonewicz Resource LPLl-2 R/F JBillerbeck, NRR *b >V e-ma1 DORL/LPL 1-2/BC DORL/LPL 1-2/PM DBroaddus CSanders 08/23/16 08/24/16}} | |
Letter Sequence RAI |
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MONTHYEARLR-N15-0250, Lnservice Testing (IST) Program - Fourth Ten-Year Interval2015-12-18018 December 2015
Lnservice Testing (IST) Program - Fourth Ten-Year Interval
Project stage: Request
ML16007A1202016-01-0707 January 2016
NRR E-mail Capture - Acceptance Review for Hope Creek Relief Requests GR-01, PR-01, PR-02, VR-01, and VR-02
Project stage: Acceptance Review
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
Project stage: RAI
LR-N16-0105, Request for Additional Information Regarding Relief Requests Associated with the Fourth 10-Year Lnservice Test Interval2016-06-10010 June 2016
Request for Additional Information Regarding Relief Requests Associated with the Fourth 10-Year Lnservice Test Interval
Project stage: Request
ML16231A4272016-08-24024 August 2016
Request for Additional Information Regarding Relief Request VR-02, Associated with the Fourth 10-Year Inservice Test Interval
Project stage: RAI
LR-N16-0174, Response to Second Request for Additional Information Regarding Relief Request VR-02 Associated with the Fourth 10-Year Inservice Test Interval2016-09-23023 September 2016
Response to Second Request for Additional Information Regarding Relief Request VR-02 Associated with the Fourth 10-Year Inservice Test Interval
Project stage: Request
ML16343A0572016-12-20020 December 2016
Requests for Relief GR-01, PR-01, PR-02, VR-01, and VR-02, for the Fourth Inservice Testing Interval
Project stage: Other
2016-05-05
[Table View] |
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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
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 24, 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 RELIEF REQUEST VR-02, ASSOCIATED WITH THE FOURTH 10-YEAR INSERVICE TEST INTERVAL (CAC NO. MF7201)
Dear Mr. Sena:
By letter dated December 18, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15352A127), as supplemented by letter dated June 10, 2016 (ADAMS Accession No. ML16162A709), PSEG Nuclear LLC (PSEG or the licensee) submitted Relief Requests GR-01, PR-01, PR-02, VR-01, and VR-02, for the fourth 10-year inservice testing interval for the Hope Creek Generating Station. These proposed alternatives apply to certain requirements of the American Society of Mechanical Engineers Code for the Operation and Maintenance of Nuclear Power Plants and were submitted pursuant to Title 10 of the Code of Federal Regulations Sections 50.55a(a)(z)(1) and 50.55a(a)(z)(2).
The U.S. Nuclear Regulatory Commission staff has reviewed the licensee's application and, based upon this review, determined that additional information is needed for Relief Request VR-02, "Main Steam Safety Relief Valves," as set forth in the enclosed Request for Additional Information. On August 3, 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 August 18, 2016, a teleconference was held to clarify the questions. Mr. Duke indicated that PSEG will submit a response within 30 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.
Carleen J. a ker, Project Manager Plant Licens , g 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 REGARDING RELIEF REQUEST VR-02 FOR THE INSERVICE TESTING PROGRAM FOURTH 10-YEAR INTERVAL PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By letter dated December 18, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15352A127), as supplemented by letter dated June 10, 2016 (ADAMS Accession No. ML16162A709), PSEG Nuclear LLC submitted Relief Requests GR-01, PR-01, PR-02, VR-01, and VR-02, for the fourth 10-year inservice testing interval for the Hope Creek Generating Station. These proposed alternatives apply to certain requirements of the American Society of Mechanical Engineers Code for the Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and were submitted pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Sections 50.55a(a)(z)(1) and 50.55a(a)(z)(2). The U.S. Nuclear Regulatory Commission staff has reviewed the licensee's application and, based upon this review, determined that following additional information is needed for Relief Request VR-02:
Relief Request VR-02:
The regulations in 10 CFR 50.55a(f), "lnservice testing requirements," require, in part, that inservice testing of certain ASME Code Class 1, 2, and 3 components must meet the requirements of the ASME OM Code and applicable addenda, except where alternatives have been authorized pursuant to paragraphs 10 CFR 50.55a(z)(1) or 10 CFR 50.55a(z)(2).
- 1. How will the ASME OM Code sample test requirement of l-1320(a) (i.e., 20 percent per 24 months) be applied to the main steam pressure relief valves?
- 2. How will the 20 percent be determined?
- 3. Will the two stage and three stage Target Rock valves be in separate groups (a group being defined in accordance with 1-1200)?
- 4. How will the change in the number of three stage versus two stage Target Rock valves affect the grouping(s)?
P.Sena If you have any questions, please contact me at (301) 415-1603 or by e-mail at Carleen.Parker@nrc.gov.
Sincerely,
/RA/
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 RidsNrrPMHopeCreek Resource RidsNrrLALRonewicz Resource ResourceRidsNrrDeEpnb Resource MHamm, NRR LPLl-2 R/F RidsRgn1 MailCenter Resource RidsNrrDorlLpl1-2 Resource JBillerbeck, NRR RidsACRS_MailCTR Resource RidsNrrDorlDpr Resource ADAMS A ccess1on No.: ML16231A427 *b>V e-ma1 OFFICE DORL/LPL 1-2/PM DORL/LPL 1-2/LA DE/EPNB/BC* DORL/LPL 1-2/BC DORL/LPL 1-2/PM NAME CParker LRonewicz DAiiey DBroaddus CSanders DATE 08/23/16 08/22/16 07/12/16 08/23/16 08/24/16 OFFICIAL RECORD COPY
