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| {{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236,, Hancocks Bridge, NJ 08038-0236 0 PSEG Nuclear L.L. C.LR-N08-0257 November 21, 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 | | {{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236,, Hancocks Bridge, NJ 08038-0236 0 PSEG NuclearL.L. C. |
| | LR-N08-0257 November 21, 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 |
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| ==Subject:== | | ==Subject:== |
| Clarification to Final Safety Evaluation for Extended Power Uprate, License Amendment No. 174 | | Clarification to Final Safety Evaluation for Extended Power Uprate, License Amendment No. 174 |
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| ==Reference:== | | ==Reference:== |
| : 1) Letter from Christine T. Neely (PSEG Nuclear LLC) to USNRC, September 24, 2008 On May 14, 2008, the NRC issued Amendment No. 174 to the operating license for the Hope Creek Generating Station (HCGS), increasing the authorized maximum power level by approximately 15 percent, from 3,339 megawatts thermal (MWt) to 3,840 MWt.In Reference 1, PSEG Nuclear (LLC) identified some items requiring clarification in the related safety evaluation. | | : 1) Letter from Christine T. Neely (PSEG Nuclear LLC) to USNRC, September 24, 2008 On May 14, 2008, the NRC issued Amendment No. 174 to the operating license for the Hope Creek Generating Station (HCGS), increasing the authorized maximum power level by approximately 15 percent, from 3,339 megawatts thermal (MWt) to 3,840 MWt. |
| Attachment I to this letter provides an additional clarification to the safety evaluation. | | In Reference 1, PSEG Nuclear (LLC) identified some items requiring clarification in the related safety evaluation. |
| A markup of the affected page of the safety evaluation is provided in Attachment | | Attachment I to this letter provides an additional clarification to the safety evaluation. A markup of the affected page of the safety evaluation is provided in Attachment 2. The clarification does not invalidate the conclusions documented in the safety evaluation. |
| : 2. The clarification does not invalidate the conclusions documented in the safety evaluation.
| |
| There are no regulatory commitments in this letter or attachments. | | There are no regulatory commitments in this letter or attachments. |
| If you have any questions or require additional information, please contact Mr. Paul Duke at 856-339-1466. | | If you have any questions or require additional information, please contact Mr. Paul Duke at 856-339-1466. |
| Sincerely, 4JeeKeenan Manager -Licensing PSEG Nuclear LLC LR-N08-0257 November 21, 2008 Page 2 Attachments (2)1. Clarification to Final Safety Evaluation for Extended Power Uprate, License Amendment No. 174 2. Marked-up Page cc: S. Collins, Regional Administrator | | Sincerely, 4JeeKeenan Manager - Licensing PSEG Nuclear LLC |
| -NRC Region I J. Lamb, Project Manager -USNRC NRC Senior Resident Inspector | | |
| -Hope Creek P. Mulligan, Manager IV, NJBNE LR-N08-0257 Page 1 of 1 ATTACHMENT 1 Hope Creek Generating Station NRC Docket No. 50-354 Clarifications to Final Safety Evaluation for Extended Power Uprate, License Amendment No. 174 Item Location Existing Text Recommended Text Basis 1. Section A.2.1, Steam PSEG did not take credit for [delete] The stress results account for all Dryer, Acoustic Circuit conservative (negative) bias the end-to-end biases and Model values in the stress results. uncertainties in the loads model.Treatment of Acoustic Circuit Page A-5 Model biases and uncertainties is described in:* Section 2, C.D.I.Technical Note No.07-29P, Rev. 0 (Attachment 6 to PSEG letter LR-N07-0171, August 3, 2007)* Table 11, C.D.I. Report No. 07-17P, Rev. 4 (Attachment 3 to PSEG letter LR-N08-0033, January 30, 2008)"Page numbers correspond to Appendix A to the Final Safety Evaluation for Amendment No. 174, Accession No. ML081230648 LR-N08-0205 ATTACHMENT 2 Hope Creek Generating Station NRC Docket No. 50-354 Clarifications to Final Safety Evaluation for Extended Power Uprate, License Amendment No. 174 Marked-up Pages Page A-5 A-5 Acoustic Circuit Model PSEG developed a new acoustic circuit model (ACM Rev. 4) to predict full scale steam dryer loads from in-plant measurements, with the inclusion of a low frequency hydrodynamic contribution. | | LR-N08-0257 November 21, 2008 Page 2 Attachments (2) |
| The model is described in LR-N07-0171, 9 Attachment 3, CDI Report 07-09P (Rev.1), "Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, with the Inclusion of a Low Frequency Hydrodynamic Contribution" (Proprietary), 10 and is based on the Bounding Pressure Model defined in LR-N06-0286, 1 1 Attachment 20, CDI Report 05-28P,"Bounding Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements (C.D.I. Proprietary)." 1 2 The new model improves the prediction of the steam dryer loads at low frequencies up to 60 Hz. [[]]The parameters of the new ACM Rev. 4 are "tuned" by means of QC2 in-plant measurements at OLTP (790 megawatts electric [MWe]) because the corresponding Mach number (M=O.105) in QC2 MSLs would be similar to that for Hope Creek at EPU conditions. | | : 1. Clarification to Final Safety Evaluation for Extended Power Uprate, License Amendment No. 174 |
| The MSL strain gage measurements are used to estimate the [[]]. The predictions of the new version are compared with the pressure measurements on the steam dryer in QC2. The low frequency | | : 2. Marked-up Page cc: S. Collins, Regional Administrator - NRC Region I J. Lamb, Project Manager - USNRC NRC Senior Resident Inspector - Hope Creek P. Mulligan, Manager IV, NJBNE |
| (<60 Hz) prediction appears to envelop the QC2 measurements at low frequencies. | | |
| In addition, the new model seems to reduce the bias and uncertainty errors in the frequency range of 40 to 60 Hz (bias from 14 to 0.4 percent and uncertainty from 15 to 7 percent).In LR-N07-0171, Attachment 3, CDI Report 07-09P (Rev. 1), "Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, with the Inclusion of a Low Frequency Hydrodynamic Contribution," PSEG compared the direct measurements and 'blind' simulations of the surface pressures on the QC2 dryer (prior to the installation of acoustic side branches (ASBs) at QC) and established the bias errors and uncertainties associated with ACM-generated loads on the dryer. The bias errors and uncertainties of the analysis were found to be frequency-dependent. | | LR-N08-0257 Page 1 of 1 ATTACHMENT 1 Hope Creek Generating Station NRC Docket No. 50-354 Clarifications to Final Safety Evaluation for Extended Power Uprate, License Amendment No. 174 Item Location Existing Text Recommended Text Basis |
| For example, the bias errors were negative (conservative), or less than [[]] percent, for all evaluated frequency ranges with the exception of a positive [ ]percent bias error between 116 and 120 Hz. The uncertainty values lu p rcent wilt i ic int ervals over th nc range. Pno ake redi ons aiv e ive o value nthe ress Sul .he largebia e r"7 ]] percent)requencie n 1 a is ase n e ACM's underestimation of the dryer loads caused by flow-induced acoustic resonances in the SRVs of the QC2 plant at 156 Hz.Because similar errors may occur for other SRV resonances in other plants, PSEG will apply the[[ ]] percent bias and [[ ]] percent uncertainty to any SRV resonance that may appear in the MSL signals during Hope Creek power ascension. | | : 1. Section A.2.1, Steam PSEG did not take credit for [delete] The stress results account for all Dryer, Acoustic Circuit conservative (negative) bias the end-to-end biases and Model values in the stress results. uncertainties in the loads model. |
| 9 PSEG Letter (LR-N07-0171) to NRC dated August 3. 2007, "Response to Request for Additional Information, Request For Ucense Amendment, Extended Power Uprate" ADAMS Accession No. ML072250369 10 CDI Report 07-09P (Rev. 1). "Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, with the Inclusion of a Low Frequency Hydrodynamic Contribution" (Proprietary) | | Treatment of Acoustic Circuit Page A-5 Model biases and uncertainties is described in: |
| ADAMS Accession No. ML072250371 11 PSEG Letter (LR-N06-0286) to NRC dated September 18, 2006, "Request for License Amendment Extended Power Uprate,~ Hope Creek Generating Station Facility, Operating License NPF-57, Docket No. 50-354" ADAMS Accession No. ML062680451 12 ADAMS Accession No. ML061300484 (Proprietary)}} | | * Section 2, C.D.I. |
| | Technical Note No. |
| | 07-29P, Rev. 0 (Attachment 6 to PSEG letter LR-N07-0171, August 3, 2007) |
| | * Table 11, C.D.I. Report No. 07-17P, Rev. 4 (Attachment 3 to PSEG letter LR-N08-0033, January 30, 2008) |
| | "Page numbers correspond to Appendix A to the Final Safety Evaluation for Amendment No. 174, Accession No. ML081230648 |
| | |
| | LR-N08-0205 ATTACHMENT 2 Hope Creek Generating Station NRC Docket No. 50-354 Clarifications to Final Safety Evaluation for Extended Power Uprate, License Amendment No. 174 Marked-up Pages Page A-5 |
| | |
| | A-5 Acoustic Circuit Model PSEG developed a new acoustic circuit model (ACM Rev. 4) to predict full scale steam dryer loads from in-plant measurements, with the inclusion of a low frequency hydrodynamic contribution. The model is described in LR-N07-0171, 9 Attachment 3, CDI Report 07-09P (Rev. |
| | 1), "Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, with the Inclusion of a Low Frequency Hydrodynamic Contribution" (Proprietary), 10 and is based on the Bounding Pressure Model defined in LR-N06-0286,1 1 Attachment 20, CDI Report 05-28P, "Bounding Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements (C.D.I. Proprietary)."1 2 The new model improves the prediction of the steam dryer loads at low frequencies up to 60 Hz. (( |
| | )) |
| | The parameters of the new ACM Rev. 4 are "tuned" by means of QC2 in-plant measurements at OLTP (790 megawatts electric [MWe]) because the corresponding Mach number (M=O.105) in QC2 MSLs would be similar to that for Hope Creek at EPU conditions. The MSL strain gage measurements are used to estimate the (( |
| | )). The predictions of the new version are compared with the pressure measurements on the steam dryer in QC2. The low frequency (< |
| | 60 Hz) prediction appears to envelop the QC2 measurements at low frequencies. In addition, the new model seems to reduce the bias and uncertainty errors in the frequency range of 40 to 60 Hz (bias from 14 to 0.4 percent and uncertainty from 15 to 7 percent). |
| | In LR-N07-0171, Attachment 3, CDI Report 07-09P (Rev. 1), "Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, with the Inclusion of a Low Frequency Hydrodynamic Contribution," PSEG compared the direct measurements and 'blind' simulations of the surface pressures on the QC2 dryer (prior to the installation of acoustic side branches (ASBs) at QC) and established the bias errors and uncertainties associated with ACM-generated loads on the dryer. The bias errors and uncertainties of the analysis were found to be frequency-dependent. For example, the bias errors were negative (conservative), or less than (()) percent, for all evaluated frequency ranges with the exception of a positive [ ] |
| | percent bias error between 116 and 120 Hz. The uncertainty values lu p rcent wilt i ic intervals over th nc range. Pno ake redi o ons aiv e ive value nthe ress Sul . he largebia e r"7 )) percent) requencie n1 a is ase n e ACM's underestimation of the dryer loads caused by flow-induced acoustic resonances in the SRVs of the QC2 plant at 156 Hz. |
| | Because similar errors may occur for other SRV resonances in other plants, PSEG will apply the |
| | (( )) percent bias and (( )) percent uncertainty to any SRV resonance that may appear in the MSL signals during Hope Creek power ascension. |
| | 9 PSEG Letter (LR-N07-0171) to NRC dated August 3. 2007, "Response to Request for Additional Information, Request For Ucense Amendment, Extended Power Uprate" ADAMS Accession No. ML072250369 10CDI Report 07-09P (Rev. 1). "Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, with the Inclusion of a Low Frequency Hydrodynamic Contribution" (Proprietary) ADAMS Accession No. ML072250371 11PSEG Letter (LR-N06-0286) to NRC dated September 18, 2006, "Request for License Amendment Extended Power Uprate, |
| | ~ Hope Creek Generating Station Facility, Operating License NPF-57, Docket No. 50-354" ADAMS Accession No. ML062680451 12 ADAMS Accession No. ML061300484 (Proprietary)}} |
Letter Sequence Supplement |
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TAC:MD3002, Control Room Habitability (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
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MONTHYEARML0733004532003-11-27027 November 2003 Schedule and Response to PSEG Letter (LR-N07-0274) Dated October 23, 2007, Plans Related to Steam Dryer Evaluation Regarding Request for Extended Power Uprate Project stage: Other ML0626900642006-09-0101 September 2006 Attachment 26, C.D.I. Report No. 06-16NP, Rev 1, Estimating High Frequency Flow Induced Vibration in the Main Stream Lines at Hope Creek Unit 1: a Subscale Four Line Investigation of Standpipe Behavior. Project stage: Request LR-N06-0286, Request for License Amendment Extended Power Uprate2006-09-18018 September 2006 Request for License Amendment Extended Power Uprate Project stage: Request ML0626900442006-09-30030 September 2006 Attachment 21, C.D.I. Report No. 06-27, Rev 0, Stress Analysis of Hope Creek Unit 1 Steam Dryer at CLTP and EPU Conditions Using 1/8th Scale Model Pressure Measurement Data. Project stage: Request ML0631101672006-09-30030 September 2006 Attachment 2 - CDI Technical Memo 06-23P (Non-Proprietary) Comparison of Hope Creek and Quad Cities Steam Dryer Loads at EPU Conditions, Revision 0, Dated September 2006 Project stage: Request LR-N06-0413, Supplement to License Amendment Request for Extended Power Uprate2006-10-10010 October 2006 Supplement to License Amendment Request for Extended Power Uprate Project stage: Supplement ML0628303692006-10-13013 October 2006 Supplement to Application for Extended Power Uprate Project stage: Other ML0629003222006-10-18018 October 2006 Extended Power Uprate Accpetance Review Results Project stage: Other LR-N06-0418, Supplement to License Amendment Request for Extended Power Uprate, to Increase the Maximum Authorized Power Level to 3840 Megawatts Thermal2006-10-20020 October 2006 Supplement to License Amendment Request for Extended Power Uprate, to Increase the Maximum Authorized Power Level to 3840 Megawatts Thermal Project stage: Supplement ML0628304722006-11-0808 November 2006 PSEG Nuclear LLC, Withholding from Public Disclosure, NEDC-33076P, Revision 2, Safety Analysis Report for Hope Creek Constant Pressure Power Uprate, Class III, MD3002 Project stage: Other ML0628304532006-11-21021 November 2006 PSEG Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance ML0633301432006-12-15015 December 2006 11/13-14/2006 Summary of Category 1 Meeting with PSEG Nuclear LLC, Regarding Application for Extended Power Uprate for Hope Creek Project stage: Meeting ML0703002772007-01-26026 January 2007 E-Mail Shea-NRR,to Duke, PSEG, Group1 Draft EPU RAI Project stage: Draft Other ML0716303072007-01-31031 January 2007 C.D.I. Technical Note No. 07-01NP, EPU Conditions in the Main Steam Lines at Hope Creek Unit 1: Additional Subscale Four Line Tests. Project stage: Request LR-N07-0034, C.D.I. Technical Memorandum No. 06-23NP, Revision 1, Comparison of the Hope Creek and Quad Cities Steam Dryer Loads at EPU Conditions.2007-01-31031 January 2007 C.D.I. Technical Memorandum No. 06-23NP, Revision 1, Comparison of the Hope Creek and Quad Cities Steam Dryer Loads at EPU Conditions. Project stage: Request LR-N07-0026, Supplemental to License Amendment Request for Extended Power Uprate2007-02-14014 February 2007 Supplemental to License Amendment Request for Extended Power Uprate Project stage: Supplement LR-N07-0029, Supplement to License Amendment Request for Extended Power Uprate2007-02-16016 February 2007 Supplement to License Amendment Request for Extended Power Uprate Project stage: Supplement ML0703304152007-02-16016 February 2007 Request for Additional Information Regarding Request for Extended Power Uprate Project stage: RAI ML0706606192007-02-20020 February 2007 Draft Request for Additional Information Hope Creek EPU Grp 5 Project stage: Draft RAI ML0706601992007-02-20020 February 2007 Draft Request for Additional Information Hope Creek EPU Grp 4 Project stage: Draft RAI ML0704602432007-02-23023 February 2007 Ltr Request for Additional Information Related to the Request for Extended Power Uprate Project stage: RAI ML0706606382007-02-23023 February 2007 Draft Request for Additional Information Hope Creek EPU Grp 6 Project stage: Draft RAI ML0706803142007-02-28028 February 2007 Hope Creek, Supplement to License Amendment Request for Extended Power Uprate Project stage: Supplement ML0708103652007-02-28028 February 2007 C.D.I. Report No. 07-01NP, Rev. 0, Revised Hydrodynamic Loads on Hope Creek Unit 1 Steam Dryer to 200 Hz. Project stage: Request ML0706006112007-03-0202 March 2007 Request for Additional Information Regarding Request for Extended Power Uprate Project stage: RAI ML0709200252007-03-0202 March 2007 Slides for Summary of March 2, 2007 Meeting with PSEG Nuclear LLC on an Application for Extended Power Uprate for Hope Creek Generating Station Regarding Steam Dryer Margin Project stage: Meeting ML0706803062007-03-13013 March 2007 Request for Additional Information Regarding Request for Extended Power Uprate Project stage: RAI LR-N07-0035, Response to Request for Additional Information Request for License Amendment - Extended Power Uprate2007-03-13013 March 2007 Response to Request for Additional Information Request for License Amendment - Extended Power Uprate Project stage: Response to RAI LR-N07-0055, Supplement to License Amendment Request for Extended Power Uprate2007-03-13013 March 2007 Supplement to License Amendment Request for Extended Power Uprate Project stage: Supplement ML0708004302007-03-29029 March 2007 Summary of March 2, 2007, Meeting with PSEG Nuclear, LLC, on an Application for Extended Power Uprate for Hope Creek Generating Station Regarding Steam Dryer Margin Project stage: Meeting 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 Project stage: Response to RAI LR-N07-0069, 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 Project stage: Response to RAI LR-N07-0070, Response to Request for Additional Information on Request for License Amendment - Extended Power Uprate2007-04-13013 April 2007 Response to Request for Additional Information on Request for License Amendment - Extended Power Uprate Project stage: Response to RAI LR-N07-0084, Supplement to License Amendment Request for Extended Power Uprate, Revised No Significant Hazards Consideration2007-04-18018 April 2007 Supplement to License Amendment Request for Extended Power Uprate, Revised No Significant Hazards Consideration Project stage: Supplement ML0711400912007-04-20020 April 2007 Request for Additional Information Regarding Request for Extended Power Uprate (TAC MD3002) - NON-PROPRIETARY Project stage: RAI ML0713603772007-04-30030 April 2007 C.D.I. Report No. 06-16NP, Rev. 2, Estimating High Frequency Flow Induced Vibration in the Main Steam Lines at Hope Creek, Unit 1: a Subscale Four Line Investigation of Standpipe Behavior. Project stage: Request 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 Project stage: Response to RAI ML0710104492007-05-0303 May 2007 Explanation of Hope Creek Nuclear Generating Station Extended Power Uprate and Conclusion of Informal Consultation Project stage: Other ML0712404872007-05-0909 May 2007 PSEG Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance 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 Project stage: Response to RAI ML0712404112007-05-14014 May 2007 RAI, Request for Additional Information Regarding Request for Extended Power Uprate Project stage: RAI ML0712405052007-05-15015 May 2007 Summary of Meeting with PSEG Nuclear LLC, Regarding Technical Aspects of the Licensee'S Application for an Extended Power Uprate (EPU) at the Hope Creek Generating Station (Hope Creek) Project stage: Meeting ML0712404612007-05-17017 May 2007 PSEG Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance ML0628605302007-05-17017 May 2007 Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance ML0713707002007-05-17017 May 2007 Request for Additional Information (RAI) Regarding Request for Extended Power Uprate Project stage: RAI ML0712405102007-05-17017 May 2007 PSEG Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance LR-N07-0123, Response to Request for Additional Information, Request for License Amendment - Extended Power Uprate2007-05-18018 May 2007 Response to Request for Additional Information, Request for License Amendment - Extended Power Uprate Project stage: Response to RAI LR-N07-0113, Supplement to Request for License Amendment Extended Power Uprate Steam Dryer Limit Curves2007-05-18018 May 2007 Supplement to Request for License Amendment Extended Power Uprate Steam Dryer Limit Curves Project stage: Supplement LR-N07-0122, Supplement to Request for License Amendment Re Extended Power Uprate & C.D.I. Technical Note No. 07-012007-05-24024 May 2007 Supplement to Request for License Amendment Re Extended Power Uprate & C.D.I. Technical Note No. 07-01 Project stage: Supplement ML0717203702007-05-31031 May 2007 Attachment 2, C.D.I. Technical Note No. 07-19NP, Revision 0, Hope Creek, Unit 1, Extended Power Uprate Limit Curve Analysis for Dryer Stress Prediction During Power Ascension Project stage: Request 2007-02-28
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Category:Letter type:LR
MONTHYEARLR-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-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) 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-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 2024-08-06
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PSEG Nuclear LLC P.O. Box 236,, Hancocks Bridge, NJ 08038-0236 0 PSEG NuclearL.L. C.
LR-N08-0257 November 21, 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:
Clarification to Final Safety Evaluation for Extended Power Uprate, License Amendment No. 174
Reference:
- 1) Letter from Christine T. Neely (PSEG Nuclear LLC) to USNRC, September 24, 2008 On May 14, 2008, the NRC issued Amendment No. 174 to the operating license for the Hope Creek Generating Station (HCGS), increasing the authorized maximum power level by approximately 15 percent, from 3,339 megawatts thermal (MWt) to 3,840 MWt.
In Reference 1, PSEG Nuclear (LLC) identified some items requiring clarification in the related safety evaluation.
Attachment I to this letter provides an additional clarification to the safety evaluation. A markup of the affected page of the safety evaluation is provided in Attachment 2. The clarification does not invalidate the conclusions documented in the safety evaluation.
There are no regulatory commitments in this letter or attachments.
If you have any questions or require additional information, please contact Mr. Paul Duke at 856-339-1466.
Sincerely, 4JeeKeenan Manager - Licensing PSEG Nuclear LLC
LR-N08-0257 November 21, 2008 Page 2 Attachments (2)
- 1. Clarification to Final Safety Evaluation for Extended Power Uprate, License Amendment No. 174
- 2. Marked-up Page 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-N08-0257 Page 1 of 1 ATTACHMENT 1 Hope Creek Generating Station NRC Docket No. 50-354 Clarifications to Final Safety Evaluation for Extended Power Uprate, License Amendment No. 174 Item Location Existing Text Recommended Text Basis
- 1. Section A.2.1, Steam PSEG did not take credit for [delete] The stress results account for all Dryer, Acoustic Circuit conservative (negative) bias the end-to-end biases and Model values in the stress results. uncertainties in the loads model.
Treatment of Acoustic Circuit Page A-5 Model biases and uncertainties is described in:
Technical Note No.07-29P, Rev. 0 (Attachment 6 to PSEG letter LR-N07-0171, August 3, 2007)
- Table 11, C.D.I. Report No.07-17P, Rev. 4 (Attachment 3 to PSEG letter LR-N08-0033, January 30, 2008)
"Page numbers correspond to Appendix A to the Final Safety Evaluation for Amendment No. 174, Accession No. ML081230648
LR-N08-0205 ATTACHMENT 2 Hope Creek Generating Station NRC Docket No. 50-354 Clarifications to Final Safety Evaluation for Extended Power Uprate, License Amendment No. 174 Marked-up Pages Page A-5
A-5 Acoustic Circuit Model PSEG developed a new acoustic circuit model (ACM Rev. 4) to predict full scale steam dryer loads from in-plant measurements, with the inclusion of a low frequency hydrodynamic contribution. The model is described in LR-N07-0171, 9 Attachment 3, CDI Report 07-09P (Rev.
1), "Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, with the Inclusion of a Low Frequency Hydrodynamic Contribution" (Proprietary), 10 and is based on the Bounding Pressure Model defined in LR-N06-0286,1 1 Attachment 20, CDI Report 05-28P, "Bounding Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements (C.D.I. Proprietary)."1 2 The new model improves the prediction of the steam dryer loads at low frequencies up to 60 Hz. ((
))
The parameters of the new ACM Rev. 4 are "tuned" by means of QC2 in-plant measurements at OLTP (790 megawatts electric [MWe]) because the corresponding Mach number (M=O.105) in QC2 MSLs would be similar to that for Hope Creek at EPU conditions. The MSL strain gage measurements are used to estimate the ((
)). The predictions of the new version are compared with the pressure measurements on the steam dryer in QC2. The low frequency (<
60 Hz) prediction appears to envelop the QC2 measurements at low frequencies. In addition, the new model seems to reduce the bias and uncertainty errors in the frequency range of 40 to 60 Hz (bias from 14 to 0.4 percent and uncertainty from 15 to 7 percent).
In LR-N07-0171, Attachment 3, CDI Report 07-09P (Rev. 1), "Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, with the Inclusion of a Low Frequency Hydrodynamic Contribution," PSEG compared the direct measurements and 'blind' simulations of the surface pressures on the QC2 dryer (prior to the installation of acoustic side branches (ASBs) at QC) and established the bias errors and uncertainties associated with ACM-generated loads on the dryer. The bias errors and uncertainties of the analysis were found to be frequency-dependent. For example, the bias errors were negative (conservative), or less than (()) percent, for all evaluated frequency ranges with the exception of a positive [ ]
percent bias error between 116 and 120 Hz. The uncertainty values lu p rcent wilt i ic intervals over th nc range. Pno ake redi o ons aiv e ive value nthe ress Sul . he largebia e r"7 )) percent) requencie n1 a is ase n e ACM's underestimation of the dryer loads caused by flow-induced acoustic resonances in the SRVs of the QC2 plant at 156 Hz.
Because similar errors may occur for other SRV resonances in other plants, PSEG will apply the
(( )) percent bias and (( )) percent uncertainty to any SRV resonance that may appear in the MSL signals during Hope Creek power ascension.
9 PSEG Letter (LR-N07-0171) to NRC dated August 3. 2007, "Response to Request for Additional Information, Request For Ucense Amendment, Extended Power Uprate" ADAMS Accession No. ML072250369 10CDI Report 07-09P (Rev. 1). "Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, with the Inclusion of a Low Frequency Hydrodynamic Contribution" (Proprietary) ADAMS Accession No. ML072250371 11PSEG Letter (LR-N06-0286) to NRC dated September 18, 2006, "Request for License Amendment Extended Power Uprate,
~ Hope Creek Generating Station Facility, Operating License NPF-57, Docket No. 50-354" ADAMS Accession No. ML062680451 12 ADAMS Accession No. ML061300484 (Proprietary)