Letter Sequence Supplement |
---|
|
|
|
|
---|
Category:Letter type:LR
MONTHYEARLR-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 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 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) 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 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 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 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 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 LR-N22-0075, 2022 Annual 10 CFR 50.46 Report2022-09-30030 September 2022 2022 Annual 10 CFR 50.46 Report LR-N22-0074, Emergency Plan Evacuation Time Estimate2022-09-15015 September 2022 Emergency Plan Evacuation Time Estimate LR-N22-0051, License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report2022-06-22022 June 2022 License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report LR-N22-0044, Emergency Plan Document Revisions Implemented November, 20212022-05-19019 May 2022 Emergency Plan Document Revisions Implemented November, 2021 LR-N22-0041, 2021 Annual Radioactive Effluent Release Report (Rerr)2022-04-28028 April 2022 2021 Annual Radioactive Effluent Release Report (Rerr) LR-N22-0040, 2021 Annual Radiological Environmental Operating Report2022-04-28028 April 2022 2021 Annual Radiological Environmental Operating Report LR-N22-0039, Emergency Plan Document Revisions Implemented March 24, 20222022-04-21021 April 2022 Emergency Plan Document Revisions Implemented March 24, 2022 LR-N22-0023, Guarantees of Payment of Deferred Premiums2022-03-21021 March 2022 Guarantees of Payment of Deferred Premiums LR-N22-0017, Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data2022-02-25025 February 2022 Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data LR-N22-0016, Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility2022-02-24024 February 2022 Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility LR-N22-0019, Technical Specification 6.9.1.5.b 2021 Annual Report of SRV Challenges2022-02-24024 February 2022 Technical Specification 6.9.1.5.b 2021 Annual Report of SRV Challenges LR-N22-0011, Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2022-02-0101 February 2022 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N22-0005, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-01-0707 January 2022 Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs LR-N22-0007, Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs2022-01-0505 January 2022 Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs LR-N21-0087, Corrected Hope Creek 10 CFR 50.46 Reports2021-12-0202 December 2021 Corrected Hope Creek 10 CFR 50.46 Reports LR-N21-0078, Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-11-18018 November 2021 Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0081, Submittal of Updated Final Safety Analysis Report, Revision 25, Summary of Revised Regulatory Commitments2021-11-15015 November 2021 Submittal of Updated Final Safety Analysis Report, Revision 25, Summary of Revised Regulatory Commitments LR-N21-0056, License Amendment Request to Amend the Technical Specifications to Revise Surveillance Requirements for Electric Power Monitor Channels for the Reactor Protection System (RPS) and Power Range Neutron Monitoring System2021-11-0303 November 2021 License Amendment Request to Amend the Technical Specifications to Revise Surveillance Requirements for Electric Power Monitor Channels for the Reactor Protection System (RPS) and Power Range Neutron Monitoring System LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2021-11-0303 November 2021 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N21-0071, 2021 Annual 10 CFR 50.46 Report2021-09-30030 September 2021 2021 Annual 10 CFR 50.46 Report LR-N21-0065, License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-09-29029 September 2021 License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0069, Emergency Plan Document Revisions Implemented August 10, 20212021-09-0909 September 2021 Emergency Plan Document Revisions Implemented August 10, 2021 LR-N21-0059, In-Service Inspection Activities - 90 Day Twenty-Third Refueling Outage2021-08-13013 August 2021 In-Service Inspection Activities - 90 Day Twenty-Third Refueling Outage LR-N21-0054, Correction to Prior Spent Fuel Cask Registration Letter2021-07-15015 July 2021 Correction to Prior Spent Fuel Cask Registration Letter LR-N21-0046, Submittal of Salem Generating Station Updated Final Safety Analysis Report, Revision 32, Summary of Revised Regulatory Commitments for Salem, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem2021-06-17017 June 2021 Submittal of Salem Generating Station Updated Final Safety Analysis Report, Revision 32, Summary of Revised Regulatory Commitments for Salem, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem LR-N21-0040, Response to Request for Additional Information SNSB-RAI 1 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication2021-05-27027 May 2021 Response to Request for Additional Information SNSB-RAI 1 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication LR-N21-0042, Core Operating Limits Report, Reload 23, Cycle 24, Revision 212021-05-24024 May 2021 Core Operating Limits Report, Reload 23, Cycle 24, Revision 21 LR-N21-0025, License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2021-05-0707 May 2021 License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N21-0039, Deviation from EPRI Document 33002012244 Inspection Requirements2021-04-30030 April 2021 Deviation from EPRI Document 33002012244 Inspection Requirements LR-N21-0018, Response to Requests for Additional Information SNSB-RAI 2 and SNSB-RAI 3 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication2021-04-29029 April 2021 Response to Requests for Additional Information SNSB-RAI 2 and SNSB-RAI 3 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication 2023-09-08
[Table view] |
Text
PSEG Nuclear LLC P.O. Box 236, HancocksBridge,.NJ 08038-0236 0 PSEG Nuclear L.L. C.
10 CFR 50.55a LR-N09-0140 June 25, 2009 U.S. Nuclear Regulatory Commission
- ATTN:.Document Control Desk Washington, DC .20555-0001 Hope Creek Generating Station Facility.Operating License No. NPF-57 NRC .Docket'No. 50-354
Subject:
Supplement to Response to.Request for Additional Information Regarding Relief Request for 'Examinations and Tests of Snubbers
References:
- 1) Letterfrom George P. 'Barnes (PSEG NucleariLLC) to USNRC, "Relief Request forThird Interval Inservice Inspection -Program for
'Examinations and Tests.of-Snubbers and Associated License Amendment Request," -dated July.30, .2008
- 2) Letter from Jeffrie Keenan (PSEG Nuclear LLC) to USNRC, "Response to Request for Additional Information Regarding Relief Request for
'Examinations and Tests of Snubbers,"' dated -June -11, 2009 In-Reference 1, -PSEG-Nuclear.LLC (PSEG) submitted relief request HC-13R-04 and-an
.associated license amendment request-for Hope Creek Generating Station (HCGS)
'related.to examinations and 'tests for snubbers. 'The relief request proposed an
- alternative 'to-the requirements -of the-American Society of 'Mechanical Engineers (ASME) Code for Operation and Maintenance of NuclearPower.Plants for snubber operational readiness testing. In Reference 2,-PSEG provided additional information concerning-the relief request.
Attachment 1 to this .letter .provides clarifications .to the information provided -in Reference 2.
There .are no'commitments contained in-this letter.
Dqk7
4i
,LR-N09-0140 June 25, 2009 Page2 Should you have any questions regarding this submittal, please contact Mr. Paul Duke at 856-339-1466.
Sincerely, Manager - Licensing PSEG Nuclear.LLC Attachment
- 1. Supplement to Response to Request for Additional Information cc: S. Collins, Regional Administrator.-NRC Region I R. Ennis, Project Manager-- USNRC NRC Senior Resident Inspector- Hope Creek
-P. Mulligan, Manager IV, NJBNE LR-N09-0140
'Page 1 of 2 SUPPLEMENT TO RESPONSE TO REQUEST-FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUEST HC-13R-.04 FORTHIRD TEN-YEAR INSERVICE INSPECTION INTERVAL HOPE CREEK GENERATING :STATION DOCKET NO. 50-354
!By letter dated July 30, 2008, as supplemented by letters dated January 30, :and February 6, 2009 (Agencywide Documents Access and Management System (ADAMS)
Accession Nos. ML082200316, ML090490674, and ML090560538 respectively), PSEG Nuclear LLC (PSEG or the licensee) submitted relief request HC-13R-04 and an associated license amendment request-for Hope Creek Generating Station (HCGS) related to examinations and tests for snubbers. With respect to relief request HC-13R-04, PSEG -requested relief from certain requirements specified in the American Society of Mechanical Engineers Boiler (ASME) Code for Operation.and Maintenance of Nuclear Power Plants (OM)-for thethird inservice inspection (ISI) interval at HCGS.
!By letter dated June 11, 2009 PSEG.provided :additional information concerning the
-reliefrequest. In response -to a request from the NRC staff, the following information is
-provided as clarifications to information contained 'in the June 11, .2009 letter.
- 1. In Response to RAI # 1.b, second paragraph, fourth line, PSEG states that "The most recent series of tests conducted during RF15 in the'sping of 2009 resulted in 55 acceptable tests, and no unacceptable tests on :snubbers." Whereas in
-response to RAI#41.c, first paragraph, PSEG-states that "There have -been eight
-testcampaigns successfully completed using the.sample plan described in Technical Specification Surveillance Requirement 47.5.e.2 (similar-to-the 37 sample plan from ISTD)."
Please clarify the number of snubbers tested or sample plan used (37.snubber
-plan or-different 55 plan) during -RF15,at Hope Creek.
Response
-Hope Creek tested .:55snubbers during -RF1"5, in anticipation of implementing the proposed .alternative during RF16. -There were no operational readiness test failures amongthe 55 snubbers tested. Upon authorization of the proposed alternative, PSEG plansto extend the test interval to two .cycles (i.e., -bypass a test campaign -at RF16), -based on the successfully completed test campaigns
.during RF!.3, RF14 .and RF15.
The'RF 15-total consisted .of 37 snubbers to -satisfy current-Technical Specification (TS) Surveillance 'Requirement-4-.7:5.:e.2; -15 .additional snubbers to satisfy OM N-15,Table .1, Column A; :two-non-TS -snubbers; and a :snubber found LR-N09-0140 Page.2 of.2 to have an empty fluid reservoir (described in the response to RAI l.a in PSEG's letter dated June 11,2009).
- 2. InResponse-to RAI#1.:b, second paragraph, eighth line, PSEG statesthat
"'During -the past .eight fuel cycles, visual examinations have been conducted in
,accordance with the -schedule specified in HCGS Technical Specification Table 47.5-:1 (similar-to Table ISTD-4252-1) on all accessible and inaccessible snubbers." Whereas in response to RAI # 5, fourth line, it states that "PSEG will continue to perform approximately half of the visual examinations during each fuel cycle (accessible/inaccessible)."
Please verify the difference in these statements. Table ISTD-4252-1 allows the, licensee-to skip the visual examination-based on snubbers' performance. Please
-explain and verify, if PSEG is planning to use a different approach (half of the visual examination of snubbers during each -cycle) for visual examination than as required by ISTD Table-4252-1.
-Response PSEG currently performsthe HCGS accessible-and inaccessible.snubber visual
-examinations during alternating refueling outages. This results in approximately
-one half of-the snubber population -being examined -each -refueling outage. Visual examinations Will be performed in accordance with the requirements ofTable ISTD-4252-1 of Subsection ISTOD. However, when Table ISTD-4252-:1 permits the-examination interval to be extended -to:two-fuel cycles, :PSEG -plans-to continue-the current practice of performing visual examinations on the accessible
-and inaccessible snubbers during alternating refueling outages.
.3. PSEG's RAI response indicates that TS23/4.7.5 is still being used for snubber examination -and testing at Hope Creek, -which was authorized via Relief Request HC-1-3R-02 for-its :third 10-year interval.-program.
When -is -PSEG planning to convert-Hope Creek's third year interval program to ISTD to make use of requirements~as-specified in Code Case OMN-15?
- Response PSEG plans to adoptSubsection ISTD -upon -implementation of-the license
.-amendment -adding .Limitin.g Condition for Operation (LCO) -3.0.8-and relocating TS 3/47 .5-tothe HCGS-Technical Requirements Manual (TRM). Upon
-implementation of the license amendment, PSEG will -make appropriate changes
- to-the'TRM reflecting -adoption of Subsection ISTD.