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Category:Letter type:LR
MONTHYEARLR-N24-0063, Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF)2024-10-0707 October 2024 Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF) LR-N24-0059, 2024 Annual 10 CFR 50.46 Report2024-09-30030 September 2024 2024 Annual 10 CFR 50.46 Report LR-N24-0056, Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-09-26026 September 2024 Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle LR-N24-0057, In-Service Inspection Activities2024-09-10010 September 2024 In-Service Inspection Activities LR-N24-0044, Relief Request VR-042024-08-0606 August 2024 Relief Request VR-04 LR-N24-0030, License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves2024-06-28028 June 2024 License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves LR-N24-0041, Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response2024-05-22022 May 2024 Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response LR-N24-0004, License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-05-20020 May 2024 License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) LR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-26026 April 2024 Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary LR-N24-0011, Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-0505 April 2024 Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary LR-N24-0028, And Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal2024-03-28028 March 2024 And Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal LR-N24-0021, And Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2024-03-20020 March 2024 And Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums LR-N24-0027, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-03-19019 March 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram LR-N24-0020, Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report2024-03-0707 March 2024 Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report LR-N24-0010, Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges2024-02-22022 February 2024 Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges 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 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-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) 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-N23-0010, 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-N22-0040, 2021 Annual Radiological Environmental Operating Report2022-04-28028 April 2022 2021 Annual Radiological Environmental Operating Report LR-N22-0041, 2021 Annual Radioactive Effluent Release Report (Rerr)2022-04-28028 April 2022 2021 Annual Radioactive Effluent Release Report (Rerr) 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-N22-0019, 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-N22-0016, 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-N22-0011, 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 2024-09-30
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PSEG Nuclear LLC PO. Box 236,, Hancocks Bridge, NJ 08038-0236 0 PSEG Nuclear L.L. C.FOL 2.C.(22)2.b LR-N08-0199 September 2, 2008 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:
License Condition 2.C.(22)2.b
Reference:
- 1) Hope Creek Generating Station -Issuance of Amendment Re: Extended Power Uprate (TAC No. MD3002)This letter provides information in accordance with the subject requirement in connection with the license amendment (Reference
- 1) which increased the authorized maximum power level for the Hope Creek Generating Station to 3,840 megawatts thermal (MWt).License Conditions 2.C.(22)2.b requires: After reaching 111.5 percent of 3339 MWt, PSEG Nuclear LLC shall obtain measurements from the MSL strain gages and establish the steam dryer flow-induced vibration load fatigue margin for the facility, update the dryer stress report, and re-establish the limit curves with the updated ACM load definition, which will be submitted to the NRC staff.The required information is provided in the following attachments which have been updated to reflect operation at 111.5 percent of 3,339 MWt. Attachment 1 provides the limit curves based on in-plant strain gage data obtained at 111.5 percent of 3,339 MWt and the minimum stress ratio calculated from the strain gage data. Attachment 2 provides the updated dryer stress report.1 gooi LR-N08-0199 September 2, 2008 Page 2 Attachments 1 and 2 contain information proprietary to Continuum Dynamics, Inc.(C.D.l.).
C.D.I. requests that the proprietary information in Attachments I and 2 be withheld from public disclosure in accordance with 10 CFR 2.390(a)(4).
An affidavit supporting this request is provided in Attachment
- 3. Non-proprietary versions of the C.D.I. documents are provided in Attachments 4 and 5.The information contained in this letter and attachments is provided to comply with the subject requirement.
There are no new regulatory commitments contained in this submittal.
Should you have any questions regarding this submittal, please contact Mr. Paul Duke at 856-339-1466.
Sincerely, Manager -Licensing Attachments (5)1. C.D.I. Technical Note No.08-20P, Revision 1 (Proprietary Information)
.2. C.D.I. Report No.08-29P, Revision 0 (Proprietary Information)
- 3. Affidavit for Withholding C.D.I. Technical Note No.08-20P and C.D.I. Report No.08-29P from public disclosure
- 4. C.D.I.Technical Note No. 08-20NP, Revision 1 (Non-Proprietary version)5. C.D.I. Report No. 08-29NP, Revision 0 (Non-Proprietary version)cc: S. Collins, Regional Administrator
-NRC Region I J, Lamb, Project Manager -USNRC NRC Senior Resident Inspector
-Hope Creek P. Mulligan, Manager IV, NJBNE LR-N08-0199 ATTACHMENT 3 Hope Creek Generating Station Facility Operating License NPF-57 Docket No. 50-354 Affidavit for Withholding C.D.I. Technical Note No.08-20P and C.D.I. Report No.08-29P from public disclosure 4Continuum Dynamics, Inc.(609) 538-0444 (609) 538-0464 fax 34 Lexington Avenue Ewing, NJ 08618-2302 AFFIDAVIT Re: "Limit Curves with ACM Rev. 4 for 111.5% Power Level Basis at Hope Creek Unit 1," C.D.I. Technical Note No.08-20P, Revision 1, prepared by Continuum Dynamics, Inc. dated August 2008 and "Final Stress Assessment of Hope Creek Unit I Steam Dryer at 111.5% CLTP Conditions," C.D.I. Report No.08-29P, Revision 0, prepared by Continuum Dynamics, Inc. dated August 2008 I, Alan J. Bilanin, being duly sworn, depose and state as follows: I1. I hold the position of President and Senior Associate of Continuum Dynamics, Inc. (hereinafter referred to as C.D.I.), and I am authorized to make the request for withholding from Public Record the Information contained in the documents described in Paragraph
- 2. This Affidavit
- is submitted to the Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 2.390(a)(4) based on the fact that the attached information consists of trade secret(s) of C.D.I. and that the NRC will receive the information from C'D.I. under privilege and in confidence.
- 2. The Information sought to be withheld, as transmitted to -PSEG Nuclear LLC as ,attachments to C.D.I. Letter No. 08144 dated 2 September 2008 "Limit Curves with ACM Rev. 4 for 111.5% Power Level Basis at Hope Creek Unit 1," C.D.I.Technical Note No.08-20P, Revision 1, prepared by Continuum Dynamics, Inc.dated August 2008 and "Final Stress Assessment of Hope Creek Unit 1 Steam Dryer at 111.5% CLTP Conditions," C.D.I. Report No.08-29P, Revision 0, prepared by Continuum Dynamics, Inc. dated August 2008 3. The Information summarizes: (a) a process or method, including supporting data and analysis, where prevention of its use by C.D.I.'s competitors without license from C.D.I. constitutes a competitive advantage over other companies;(b) Information which, if used by a competitor, would-reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;(c) Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
The information sought to be withheld is considered to be proprietary for the reasons set forth in-paragraphs 3(a), 3(b) and 3(c) above.
- 4. The Information has been held in confidence by C.D.I., its owner. The Information has consistently been held in confidence by C.D.I. and no public disclosure has'been made and it is not available to the public. All disclosures to third parties, which have been limited, have been made pursuant to the terms and conditions contained in C.D.I.'s Nondisclosure Secrecy Agreement which must be fully executed prior to disclosure.
- 5. The Information is a-type customarily held in confidence by C.D.I. and there is a rational basis therefore.
The Information is a type, which C.D.I. considers trade secret and is held in confidence by C.D.I. because it constitutes a source of competitive advantage in the competition and performance of -such work in the industry.
Public disclosure of the Information is likely to cause substantial harm to C.D.I.'s competitive position and foreclose or reduce the availability of profit-making opportunities.
I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to be the best of my-knowledge, information and belief.Executed on this day of -r-,' -2008.Pan J. u lai Sbscribed and sworn before me this day: _ /&4n 4 eite"r, Notary Public EILEEN P. BURMEISTER NOTARY PUBLICOF NEW JERSEY MY COMM. EXPIRES MAY-6, 2012