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| ==Dear Mr. Joyce:== | | ==Dear Mr. Joyce:== |
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| By letter dated March 29, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100900458), PSEG Nuclear LLC (PSEG) submitted a license amendment request for Hope Creek Generating Station (HCGS). The proposed amendment would revise the HCGS Technical Specifications to extend the Allowed Outage Time for the "A" and "B" Emergency Diesel Generators from 72 hours to 14 days. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. | | By letter dated March 29, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100900458), PSEG Nuclear LLC (PSEG) submitted a license amendment request for Hope Creek Generating Station (HCGS). The proposed amendment would revise the HCGS Technical Specifications to extend the Allowed Outage Time for the "A" and "B" Emergency Diesel Generators from [[estimated NRC review hours::72 hours]] to 14 days. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. |
| Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. | | Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. |
| This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. | | This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. |
Latest revision as of 16:58, 21 March 2020
Letter Sequence Acceptance Review |
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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] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 15, 2010 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear P.O. Box 236, 1\109 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GEI\IERATING STATION - ACCEPTANCE REVIEW REGARDING EMERGENCY DIESEL GENERATOR ALLOWED OUTAGE TIME EXTENSION AMENDMENT REQUEST (TAC NO. ME3597)
Dear Mr. Joyce:
By letter dated March 29, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100900458), PSEG Nuclear LLC (PSEG) submitted a license amendment request for Hope Creek Generating Station (HCGS). The proposed amendment would revise the HCGS Technical Specifications to extend the Allowed Outage Time for the "A" and "B" Emergency Diesel Generators from 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> to 14 days. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
By letter dated May 4,2010 (ADAMS Accession No. ML101200075), the NRC staff notified PSEG of specific supplemental information that needed to be submitted to enable the staff to begin its detailed technical review. By letter dated May 28, 2010 (ADAMS Accession No. ML101590514), PSEG provided the supplemental information.
The NRC staff has reviewed the supplemental information and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
T. Joyce -2 If you have any questions, please contact me at (301) 415-1420.
Sincerely, Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 cc: Distribution via Listserv
T. Joyce -2 If you have any questions, please contact me at (301) 415-1420.
Sincerely,
/raJ Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 cc: Distribution via Listserv DISTRIBUTION PUBLIC RidsOgcRp Resource LPL 1-2 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl1-2 Resource RidsNrrDeEeeb Resource RidsNrrLAABaxter Resource RidsNrrDraApla Resource RidsNrrPMHopeCreek Resource RidsNrrDorl Resource RidsNrrDorlDpr Resource RidsRgn 1MailCenter Resource VGoel, NRR/EEEB AHowe, NRR/APLA ADAM Accession No.: ML101610025 OFFICE LPL 1-2/PM LPL 1-2/LA LPL1-2/BC NAME REnnis ABaxter HChernoff DATE 6/10/10 6/11/10 6/15/10 OFFICIAL RECORD COpy
