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Category:Legal-Affidavit
MONTHYEARLR-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-N21-0018, 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 LR-N20-0023, License Amendment Request: Revise Hope Creek Generating Station Low Pressure Safety Limit to Address General Electric Nuclear Energy Part-21 Safety Communication SC05-032020-09-24024 September 2020 License Amendment Request: Revise Hope Creek Generating Station Low Pressure Safety Limit to Address General Electric Nuclear Energy Part-21 Safety Communication SC05-03 LR-N19-0101, Submittal of Core Operating Limits Report, Reload 22, Cycle 23, Revision 172019-11-12012 November 2019 Submittal of Core Operating Limits Report, Reload 22, Cycle 23, Revision 17 LR-N19-0074, Core Operating Limits Report, Reload 21, Cycle 22, Revision 162019-09-0303 September 2019 Core Operating Limits Report, Reload 21, Cycle 22, Revision 16 LR-N19-0015, Core Operating Limits Report, Reload 21, Cycle 22, Revision 152019-03-0606 March 2019 Core Operating Limits Report, Reload 21, Cycle 22, Revision 15 LR-N18-0055, Attachment 3 to LR-N18-0055, Affidavit for Core Operating Limits Report for Unit 12018-05-0909 May 2018 Attachment 3 to LR-N18-0055, Affidavit for Core Operating Limits Report for Unit 1 LR-N17-0181, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-19019 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate LR-N17-0126, Response to Request for Additional Information (Rai), P-T Limit Report License Amendment Application2017-09-0505 September 2017 Response to Request for Additional Information (Rai), P-T Limit Report License Amendment Application ML17188A2622017-03-29029 March 2017 Enclosure 7 to LR-N17-0044 and LAR H17-03 - Affidavits from GEH and the Electric Power Research Institute (EPRI) Supporting the Withholding of Information in Enclosure 6 from Public Disclosure ML17188A2682017-03-29029 March 2017 Enclosure 13 of LR-N17-0044 and LAR H17-03 - Affidavits from Cameron International Corporation Supporting the Withholding of Information in Enclosures 9 and 11 from Public Disclosure LR-N17-0044, Enclosure 13 of LR-N17-0044 and LAR H17-03 - Affidavits from Cameron International Corporation Supporting the Withholding of Information in Enclosures 9 and 11 from Public Disclosure2017-03-29029 March 2017 Enclosure 13 of LR-N17-0044 and LAR H17-03 - Affidavits from Cameron International Corporation Supporting the Withholding of Information in Enclosures 9 and 11 from Public Disclosure LR-N17-0044, Enclosure 7 to LR-N17-0044 and LAR H17-03 - Affidavits from GEH and the Electric Power Research Institute (EPRI) Supporting the Withholding of Information in Enclosure 6 from Public Disclosure2017-03-29029 March 2017 Enclosure 7 to LR-N17-0044 and LAR H17-03 - Affidavits from GEH and the Electric Power Research Institute (EPRI) Supporting the Withholding of Information in Enclosure 6 from Public Disclosure LR-N16-0202, PSEG Nuclear LLC (PSEG) - Board Resolutions - Foreign Ownership, Control, or Influence2016-11-0303 November 2016 PSEG Nuclear LLC (PSEG) - Board Resolutions - Foreign Ownership, Control, or Influence LR-N22-0083, Enclosure 3 - Global Nuclear Fuel - Americas Affidavit of Lukas Trosman2016-10-28028 October 2016 Enclosure 3 - Global Nuclear Fuel - Americas Affidavit of Lukas Trosman LR-N16-0204, Affidavit for Core Operating Limits Report, Reload 20, Cycle 21, Revision 132016-10-28028 October 2016 Affidavit for Core Operating Limits Report, Reload 20, Cycle 21, Revision 13 LR-N16-0113, GEH Affidavits Supporting the Withholding of Information in Enclosure 6 from Public Disclosure2016-08-16016 August 2016 GEH Affidavits Supporting the Withholding of Information in Enclosure 6 from Public Disclosure LR-N15-0071, Core Operating Limits Report, Reload 18, Cycle 19, Revision 102015-03-20020 March 2015 Core Operating Limits Report, Reload 18, Cycle 19, Revision 10 ML14204A7092014-07-23023 July 2014 Enclosure 3, Affidavit of Peter M. Yandow LR-N14-0157, PSEG Nuclear (PSEG) Response to NRC Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request, Dated May 5, 20142014-06-19019 June 2014 PSEG Nuclear (PSEG) Response to NRC Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request, Dated May 5, 2014 LR-N12-0075, Core Operating Limits Report, Reload 16, Cycle 17, Revision 62012-02-28028 February 2012 Core Operating Limits Report, Reload 16, Cycle 17, Revision 6 ML1127000682011-09-26026 September 2011 Enclosure 3, Mfn 10-245 R4, Affidavit LR-N11-0087, 2011 Annual Report - Guarantees of Payment of Deferred Premiums2011-03-31031 March 2011 2011 Annual Report - Guarantees of Payment of Deferred Premiums ML0831008272008-10-31031 October 2008 Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit LR-N08-0224, Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit2008-10-31031 October 2008 Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit LR-N08-0029, Transmittal of Proprietary Report 07-17P, Revision 3, Stress Assessment of Hope Creek Unit 1 Steam Dryer Based on Revision 4 Loads Model.2008-01-30030 January 2008 Transmittal of Proprietary Report 07-17P, Revision 3, Stress Assessment of Hope Creek Unit 1 Steam Dryer Based on Revision 4 Loads Model. LR-N08-0028, Responses to Requests for Additional Information Request for License Amendment - Extended Power Uprate2008-01-25025 January 2008 Responses to Requests for Additional Information Request for License Amendment - Extended Power Uprate LR-N08-0014, Responses to Requests for Additional Information Request for License Amendment - Extended Power Uprate2008-01-18018 January 2008 Responses to Requests for Additional Information Request for License Amendment - Extended Power Uprate LR-N07-0215, Supplement to License Amendment Request for Extended Power Uprate2007-08-27027 August 2007 Supplement to License Amendment Request for Extended Power Uprate LR-N07-0102, Response to Request for Additional Information Request for License Amendment - Extended Power Uprate2007-05-10010 May 2007 Response to Request for Additional Information Request for License Amendment - Extended Power Uprate LR-N07-0099, Response to Request for Additional Information Request for License Amendment, Extended Power Uprate2007-04-30030 April 2007 Response to Request for Additional Information Request for License Amendment, Extended Power Uprate LR-N07-0060, Response to Request for Additional Information Request for License Amendment - Extended Power Uprate2007-03-30030 March 2007 Response to Request for Additional Information Request for License Amendment - Extended Power Uprate LR-N06-0192, Guaranteed Retrospective Premiums Following Nuclear Accident, Salem and Hope Creek2006-05-0101 May 2006 Guaranteed Retrospective Premiums Following Nuclear Accident, Salem and Hope Creek LR-N05-0448, Response to Request for Additional Information Re Request for Change to Technical Specifications Arts/Mellla Implementation2005-09-23023 September 2005 Response to Request for Additional Information Re Request for Change to Technical Specifications Arts/Mellla Implementation ML0520003282005-07-14014 July 2005 Surveillance Program for Channel-Control Blade Interference LR-N05-0247, Stations - Guaranteed Retrospective Premiums Following a Nuclear Accident2005-04-29029 April 2005 Stations - Guaranteed Retrospective Premiums Following a Nuclear Accident ML0419004262004-07-0101 July 2004 GE Nuclear Energy Request for Withholding - Hope Creek Fuel Vendor Change Response to NRC Request for Additional Information (Docket No. 50-354) LR-N03-0386, Transmittal of Information Relating to SVEA-96+ Modeling Dimensions in Support of the Nrc'S Review of GNF-A Proprietary Report, NEDC-33107P, GEXL80 Correlation for SVEA96+ Fuel, Dated September 20032003-09-0808 September 2003 Transmittal of Information Relating to SVEA-96+ Modeling Dimensions in Support of the Nrc'S Review of GNF-A Proprietary Report, NEDC-33107P, GEXL80 Correlation for SVEA96+ Fuel, Dated September 2003 2021-05-27
[Table view] 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, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC 10 CFR 50.90 LR-N08-0014 LCR H05-01, Rev. 1 January .18, 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:
Responses to Requests for Additional Information Request for License Amendment - Extended Power Uprate
Reference:
- 1) Letter from George P. Barnes (PSEG Nuclear LLC) to USNRC, September 18, 2006
- 2) Letter from USNRC to William Levis (PSEG Nuclear LLC),
December 28, 2007
- 3) Letter from Carl J. Fricker (PSEG Nuclear LLC) to USNRC, January 15, 2008 In Reference 1, PSEG Nuclear LLC (PSEG) requested an amendment to Facility Operating License NPF-57 and the Technical Specifications (TS) for the Hope Creek Generating Station (HCGS) to increase the maximum authorized power level to 3840 megawatts thermal (MWt).
In Reference 2, the NRC requested additional information concerning PSEG's request.
PSEG provided responses to questions 14.79, 14.110, 14.115, 14.118(a) and 14.121(d) in Reference 3. Attachment 1 to this letter provides responses to the remaining questions. contains information proprietary to Continuum Dynamics, Inc. (C.D.I.).
C.D.I. requests that the proprietary information in Attachment 1 be withheld from public 95-2168 REV. 7/99
LR-N08-0014 LCR H05-01, Rev. 1 January 18, 2008 Page 2 disclosure in accordance with 10 CFR 2.390(a)(4). An affidavit supporting this request is included with Attachment 1. A non-proprietary version of PSEG's Attachment 1 responses is provided in Attachment 2.
C.D.I. Report 07-17P, Revision 3, "Stress Assessment of Hope Creek Unit 1 Steam Dryer Based on Revision 4 Loads Model," is provided in Attachment 3 to this letter. The report provides updated dryer stress analyses based on the loads determined from the MSL in-plant measurements.
C.D.I. Report 07-17P contains information which C.D.I. considers to be proprietary.
C.D.I. requests that the proprietary information be withheld from public disclosure in accordance with 10 CFR 2.390(a)(4). An affidavit supporting this request is provided in .
PSEG will provide a non-proprietary version of the document in Attachment 3 suitable for public disclosure by January 30, 2008.
There are no regulatory commitments contained within this letter.
Should you have any questions regarding this submittal, please contact Mr. Paul Duke at 856-339-1466.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on __/ _-_
(date)
Sincerely, George P. Barnes Site Vice President Hope Creek Generating Station
LR-N08-0014 LCR H05-01, Rev. 1 January 18, 2008 Page 3 Attachments (3)
- 1. Response to Request for Additional Information (proprietary)
- 2. Response to Request for Additional Information (non-proprietary)
- 3. C.D.I. Report 07-17P cc: S. Collins, Regional Administrator - NRC Region I J. Lamb, Project Manager - USNRC NRC Senior Resident Inspector - Hope Creek P. Mulligan, Manager IV, NJBNE
4Continuum Dynamics, Inc.
(609) 538-0444 (609) 538-0464 fax 34 Lexington Avenue Ewing, NJ 08618-2302 AFFIDAVIT Re: Responses to Hope Creek Generating Station - Request for Additional Information Regarding Extended Power Uprate (TAC No. MD3002),
December 28,2007 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 attachment to C.D.I. Letter No. 08013 dated 18 January 2008 Responses to Hope Creek Generating Station - Request for Additional Information Regarding Extended Power Uprate (TAC No. MD 3002), December 28,2007.
- 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 J6C V 2008.
/1344 &/6lead44~
Alan T. Bilanin Continuum Dynamics, Inc.
Subscribed and sworn before me this day: - d' c4)C F--
(; 62ntir Zsme Public EILEEN P. BURMEISTER NOTARY PUBLIC OF NEW JERSEY MY COMM. EXPIRES MAY 6, 2012
'I
LR-N08-0014 ATTACHMENT 2 Hope Creek Generating Station Facility Operating License NPF-57 Docket No. 50-354 Extended Power Uprate Response to Request for Additional Information In Reference 1, PSEG Nuclear LLC (PSEG) requested an amendment to Facility Operating License NPF-57 and the Technical Specifications (TS) for the Hope Creek Generating Station (HCGS) to increase the maximum authorized power level to 3840 megawatts thermal (MWt).
In Reference 2, the NRC requested additional information concerning PSEG's request.
PSEG provided responses to questions 14.79, 14.110, 14.115, 14.118(a) and 14.121(d) in Reference 3. PSEG's responses to the remaining questions are provided below.
RAI 14.107 2 nd Follow-Up PSEG estimates that a standpipe resonance may be excited at 118 Hz. Since the frequencies of resonance/instability coupling are known to shift slightly with increasing flow rate, it is possible that the actual observed resonance frequency may be closer to 120 Hz. Please explain whether current filtering of 120 Hz signal from the MSL measurements would affect the magnitude of the standpipe resonance signal, which may be close to 120 Hz. Please also explain how the standpipe resonance signal would be quantified.
Response
As discussed in response to 14.107, the 120 Hz electrical noise is not easily masked by the SRV resonance. ((
LR-N08-0014 Attachment 2 Page 2
))
The main steam line pressure data will then be processed and analyzed with the ACM methodology as has been previously discussed in C.D.I. Report No.07-18P.
LR-N08-0014 Attachment 2 Page 3 RAI 14.116(a) Follow-Up The signal to noise ratio assumed in the analysis is not apparent from the response.
PSEG is requested to provide typical values of the factor ((
)), which is used to remove the background noise.
Response
Typical values of the factor may be taken from the Hope Creek main steam line data at the A upper strain gage (as an example). These values are shown below at selected frequencies, averaged from -0.5 Hz to 0.5 Hz around the frequency listed:
))
RAI 14.116(c) Follow-Up The PSEG response does not provide the basis for correcting the coherence between
((
Response
The reference J. S. Bendat and A. G. Piersol, 1966, Measurement and Analysis of Random Data, John Wiley and Sons, Page 215, Table 5.1 (described in C.D.I. Report No.07-09P) gives 99% confidence limits on the coherence based on coherence estimates, as provided in our previous response to this RAI:
Coherence Estimate Lower Confidence Limits 0.4 0.19 0.5 0.29 0.6 0.41 0.7 0.54 0.8 0.68 0.9 0.83
LR-N08-0014 Attachment 2 Page 4 A plot of these data gives the following:
I
- ~ 99% Confidence Limit 0.8 - 100% Confidence Limit -
-- Average Confidence Limit 0ý 0.6 --
0.4 0.2 :- i - - [-
0 0 0.2 0.4 0.6 0.8 1 Computed Coherence (x) where a linear curve fit through the data points (black circles) gives the line y = -0.346+1.286x (R2 = 0.995) in black, the one-to-one curve (no correction) in blue, and the line halfway between the linear curve fit and no correction (halfway to the lower confidence limits, identified in the figure as the average confidence limit) in red. The average confidence limit recovers a corrected coherence that is more conservative (a higher value) than use of the 99% confidence limit as suggested in the data of Bendat and Piersol, as it follows from the equation y = -0.173+1.143x. For example, if the computed coherence between the upper and lower strain gage measurements is 0.6, no correction would leave the coherence at 0.6, use of the 99% confidence limit curve would give a corrected coherence of 0.4, while an average coherence value would give 0.5. The average values are used in the analysis.
LR-N08-0014 Attachment 2 Page 5 I
LR-N08-0014 Attachment 2 Page 6 1]
RAI 14.118 Follow-UD (b) Substantiate the choice of various model parameters such as ((
)) at the inlet of the MSLs.
Response
The values of the various ACM modeling parameters at the inlets of the MSLs are as follows:
R]
These parameters were chosen for the following reasons:
Acoustic Speed: an application of the ASME steam tables in subroutine form [1],
used previously in examining pipe flow [2] determined that the acoustic speed at 1000 psig saturated steam conditions was 1484.3 ft/sec.
Acoustic Speed Damping in Steam Dome: the steam dome is assumed to be lightly damped, as no structures, or moisture are present in the steam dome volume that can result in damping.
((
LR-N08-0014 Attachment 2 Page 7
REFERENCES:
- 1. Indiana University Chemistry Department / Babcock and Wilcox Co. Fossil Generation Division. Subprograms of 1967 ASME Steam Tables. Quantum Chemistry Program Exchange Program No. SPHF006.
- 2. Bliss, D. B., T. R. Quackenbush, and M. E. Teske. 1982. Computational Simulation of High-Speed Steady Homogeneous Two-Phase Flow in Complex Piping Systems. Transactionsof the ASME Journalof Pressure Vessel Technology 104: 272-277.
LR-N08-0014 Attachment 2 Page 8 (c) If the dipole source strengths show a high degree of asymmetry, explain the reason of this large asymmetry by referring to pressure measurements on the dryer which cause this large asymmetry.
Response
Please refer to the two figures attached below shown schematically. ((
1]
LR-N08-0014 Attachment 2 Page 9 I]
Figure 14.118(c).1
LR-N08-0014 Attachment 2 Page 10 Figure 14.118(c).2
LR-N08-0014 Attachment 2 Page 11 RAI 14.120 Follow-Up PSEG compares measurements of ((
))
(a) What is the purpose of Figure 14.120-1? Why are the unfiltered data at low flow conditions (1000#) compared with (( )) at CLTP?
Are the CLTP data in Figure 14.120-1c filtered or unfiltered? Why are there no CLTP data in Figure 14.120-id?
Response
CDI Report No.07-17P "Stress Assessment of Hope Creek Unit 1 Steam Dryer Based on Rev. 4 Loads Model," Revision 3 (Attachment 3 to this letter) describes the method using filtered 1000# data to remove a portion of the 80 Hz dryer load.
(b) Are the dryer loads (shown in Figure 14.120-2) for the low flow condition based on filtered or raw MSL pressures? If they are based on filtered MSL pressures, please provide additional comparisons of the filtered MSL pressures at CLTP and at low flow rates ((
]B.
Response
CDI Report No.07-17P "Stress Assessment of Hope Creek Unit 1 Steam Dryer Based on Rev. 4 Loads Model," Revision 3 describes the method using filtered 1000# data to remove a portion of the 80 Hz dryer load.
(c) Why are data for MSL pairs with coherence less than (( ))? What is the basis for this assumption?
Response
Please refer to the response to RAI 14.116(c) Follow-Up. ((
1]
LR-N08-0014 Attachment 2 Page 12 (d) Will improved strain gage calibrations be used to reduce extraneous MSL pressure signals at 80 Hz in future submissions, as discussed in recent meetings with PSEG?
Specifically, during the October 11, 2007, meeting, it was mentioned that the 80 Hz signal may be due to ((
]J. Please provide variations in ((
)) and how they are accounted for in estimating acoustic pressures at those locations.
Response
PSEG does not currently plan to use improved strain gage calibrations to reduce extraneous MSL pressure signals at 80 Hz. See CDI Report No.07-17P "Stress Assessment of Hope Creek Unit 1 Steam Dryer Based on Rev. 4 Loads Model,"
Revision 3 for a description of the method using filtered 1000# data to remove a portion of the 80 Hz dryer load.
(e) What is the final PSEG stress margin for the dryer: ((
Response
The minimum alternating stress ratio on the dryer at CLTP conditions with all end-to-end biases and uncertainties included is (( )) See CDI Report No..07-17P "Stress Assessment of Hope Creek Unit I Steam Dryer Based on Rev. 4 Loads Model," Revision 3 for additional information.
(f) To conclusively confirm the reasonableness of removing a portion of the 80 Hz dryer loads at CLTP, provide a dryer stress analysis using the filtered MSL inputs at 1000#
and compare the dryer stress margins at high CLTP stress locations against those computed using filtered CLTP loads. In particular, explain the differences in stresses at 80 Hz. To ensure consistency, be sure to use signal processing and filtering for the 1000# stress analyses that are identical to those used for the previous CLTP stress analysis.
Response
See CDI Report No.07-17P "Stress Assessment of Hope Creek Unit 1 Steam Dryer Based on Rev. 4 Loads Model," Revision 3 for the requested analysis.
LR-N08-0014 Attachment 2 Page 13 RAI 14.121(c) Follow-Up PSEG provides dryer pressure data for frequencies between 75 and 85 Hz in 1 Hz increments to justify linearly interpolating acoustic pressure loads in 5 Hz increments (Figure RAI14.121.1).
(a) Where are these pressure/velocity ratios computed?
Response
The peak pressure/velocity ratios were found at the intersection of the outer bank hood with the cover plate, at the centerline of the dryer between main steam lines C and D.
(b) How do the pressure loads vary at the frequencies where peaks are observed in the MSL data
Response
PSD of the pressure load was provided in Figure 4.6 of C.D.I. Report No.07-18P.
The PSDs at frequencies when peaks are observed in the main steam lines, up to 100 Hz, at the intersection of the outer bank hood with the cover plate, at the centerline of the dryer between main steam lines C and D, are as follows:
((I (c) The comparison shown in Figure RAI14.121.1 indicates that if the load frequency were (( )), then there will be a nonconservative error of about (( )). If the load frequency were (( )), then there will be a conservative error of about
(( )). Should these errors be treated as uncertainties and included in the dryer stress estimates? For other peaks below 100 Hz, are there any other uncertainties or bias errors?
Response
The Helmholtz solution is a part of the ACM. ((
)) The apparent nonconservative or conservative effects seen in Figure RAI14.121.1 are
LR-N08-0014 Attachment 2 Page 14 therefore accounted for in the model prediction. ((
)) The same argument would apply for other peaks below 100 Hz.
References
- 1) Letter from George P. Barnes (PSEG Nuclear LLC) to USNRC, September 18, 2006
- 2) Letter from USNRC to William Levis (PSEG Nuclear LLC), December 28, 2007
- 3) Letter from Carl J. Fricker (PSEG Nuclear LLC) to USNRC, January 15, 2008
LR-N08-0014 C.D.I. Proprietary Information ATTACHMENT 3 Hope Creek Generating Station Facility Operating License NPF-57 Docket No. 50-354 Extended Power Uprate Stress Assessment of Hope Creek Unit 1 Steam Dryer Based on Revision 4 Loads Model CDI Report No.07-17P, Revision 3
SrANO Continuum Dynamics, Inc.
(609) 538-0444 (609) 538-0464 fax 34 Lexington Avenue Ewing, NJ 08618-2302 AFFIDAVIT Re: C.D.I. Report No.07-17P "Stress Assessment of Hope Creek Unit 1 Steam Dryer Based on Revision 4 Loads Model," Revision 3 dated January 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(aX4) 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 attachment to C.D.I. Letter No. 08014 dated 18 January 2008 C.D.I. Report No.07-17P "Stress Assessment of Hope Creek Unit 1 Steam Dryer Based on Revision 3 dated January 2008.
- 3. The Information summarizes:
(a) a process or method, including supporting data and analysis, where prevention of its use by C.D.l.'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
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- 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 -' 2008.
Alan J. Bilanin Continuum Dynamics, Inc.
Subscribed and sworn before me this day:- /c.
- EILEEN P. BURMEISTER NOTARY PUBLIC OF NEW JERSEY MY COMM. EXPIRES MAY 6,2012