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| | issue date = 05/31/2007 | | | issue date = 05/31/2007 |
| | title = 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 | | | title = 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 |
| | author name = Bilanin A J, Teske M E | | | author name = Bilanin A, Teske M |
| | author affiliation = Continuum Dynamics, Inc | | | author affiliation = Continuum Dynamics, Inc |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:Attachment 2 LR-N07-0113 LCR H05-01, Rev. 1 Hope Creek Generating Station Facility Operating License NPF-57 Docket No. 50-354 Extended Power Uprate Lirnt Curve Analysis for Dryer Stress Prediction During Power Ascension of Hope Creek Unit 1 C.D.I. Technical Note No. 07-19NP, Revision 0 May 2007 This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information C.D.I. Technical Note No. 07-19NP Limit Curve Analysis for Dryer Stress Prediction During Power Ascension of Hope Creek Unit 1 Revision 0 Prepared by Continuum Dynamics, Inc.34 Lexington Avenue Ewing, NJ 08618 Prepared under Purchase Order No. 4500400038 for Nuclear Business Unit, PSEG Nuclear LLC Materials Center, Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Approved by Alan J. lRnin Reviewed by Milton E. Teske May 2007 This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information Table of Contents Section Page T able of C ontents ..................................................................... | | {{#Wiki_filter:Attachment 2 LR-N07-0113 LCR H05-01, Rev. 1 Hope Creek Generating Station Facility Operating License NPF-57 Docket No. 50-354 Extended Power Uprate Lirnt Curve Analysis for Dryer Stress Prediction During Power Ascension of Hope Creek Unit 1 C.D.I. Technical Note No. 07-19NP, Revision 0 May 2007 |
| i 1. Introduction
| | |
| ............................................................................ | | This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information C.D.I. Technical Note No. 07-19NP Limit Curve Analysis for Dryer Stress Prediction During Power Ascension of Hope Creek Unit 1 Revision 0 Prepared by Continuum Dynamics, Inc. |
| 1 2. A pproach ...............................................................................
| | 34 Lexington Avenue Ewing, NJ 08618 Prepared under Purchase Order No. 4500400038 for Nuclear Business Unit, PSEG Nuclear LLC Materials Center, Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Approved by Alan J. lRnin Reviewed by Milton E. Teske May 2007 |
| 2 3. L im it C urves ...........................................................................
| | |
| 4 4. D iscussion
| | This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information Table of Contents Section Page T able of C ontents ..................................................................... i |
| ............................................................................. | | : 1. Introduction ............................................................................ 1 |
| 7 5. R eferences
| | : 2. A pproach ............................................................................... 2 |
| ............................................................................ | | : 3. L im it C urves ........................................................................... 4 |
| 10 This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information
| | : 4. D iscussion ............................................................................. 7 |
| : 1. Introduction PSEG is planning power ascension of Hope Creek Unit 1 (HC1). During ascension, it is required to monitor the dryer stresses anticipated at plant power levels that have not yet been achieved. | | : 5. R eferences ............................................................................ 10 |
| A convenient way to track these stresses is through the use of limit curves. Limit curves provide an upper bound safeguard against the potential for dryer stresses becoming higher than allowable, by estimating the not-to-be-exceeded main steam line pressure levels. In the case of HC1, main steam line data have been analyzed at Current Licensed Thermal Power (CLTP)in-plant [1] and in subscale tests [2], and at Extended Power Uprate (EPU) in subscale tests [3].EPU at HC1 is 115% of CLTP. A finite element model stress analysis has been undertaken on the EPU subscale test data [4]. These existing data provide the basis for generation of the limit curves to be used during HC 1 power ascension. | | |
| Continuum Dynamics, Inc. (C.D.I.) has developed an acoustic circuit methodology (ACM) that determines the relationship between main steam line data and pressure on the steam dryer [5]. This methodology, and the use of a finite element model analysis, provides the computational engine behind which dryer stresses at distinct steam dryer locations may be tracked through power ascension. | | This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information |
| Limit curves allow the PSEG engineer to estimate dryer stress levels conservatively, by simply comparing the main steam line pressure readings (represented in Power Spectral Density, or PSD, format) with the upper bound PSD derived from existing in-plant and subscale test data.This technical note summarizes the proposed approach that will be used to track the anticipated stress levels in the HC1 steam dryer during power ascension, and the options available to PSEG should a limit curve be reached. | | : 1. Introduction PSEG is planning power ascension of Hope Creek Unit 1 (HC1). During ascension, it is required to monitor the dryer stresses anticipated at plant power levels that have not yet been achieved. A convenient way to track these stresses is through the use of limit curves. Limit curves provide an upper bound safeguard against the potential for dryer stresses becoming higher than allowable, by estimating the not-to-be-exceeded main steam line pressure levels. In the case of HC1, main steam line data have been analyzed at Current Licensed Thermal Power (CLTP) in-plant [1] and in subscale tests [2], and at Extended Power Uprate (EPU) in subscale tests [3]. |
| | EPU at HC1 is 115% of CLTP. A finite element model stress analysis has been undertaken on the EPU subscale test data [4]. These existing data provide the basis for generation of the limit curves to be used during HC 1 power ascension. |
| | Continuum Dynamics, Inc. (C.D.I.) has developed an acoustic circuit methodology (ACM) that determines the relationship between main steam line data and pressure on the steam dryer [5]. This methodology, and the use of a finite element model analysis, provides the computational engine behind which dryer stresses at distinct steam dryer locations may be tracked through power ascension. Limit curves allow the PSEG engineer to estimate dryer stress levels conservatively, by simply comparing the main steam line pressure readings (represented in Power Spectral Density, or PSD, format) with the upper bound PSD derived from existing in-plant and subscale test data. |
| | This technical note summarizes the proposed approach that will be used to track the anticipated stress levels in the HC1 steam dryer during power ascension, and the options available to PSEG should a limit curve be reached. |
| | |
| | This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information |
| | : 2. Approach The limit curve analysis for HC1 parallels the approach followed by Entergy Vermont Yankee (VY) in its power uprate [6]. In their analysis, two levels of steam dryer performance criteria were described: (1) a Level 1 pressure level based on maintaining the ASME allowable alternating stress value on the dryer, and (2) a Level 2 pressure level based on maintaining 80% |
| | of the allowable alternating stress value on the dryer. Should Level 2 be reached or exceeded (under the rules to be discussed below), reactor power ascension was to be suspended until an engineering evaluation concluded that further power ascension was justified. Should Level I be reached or exceeded, reactor power was to be returned to a previously acceptable power level while an engineering evaluation was undertaken. |
| | To develop the limit curves upon which Level 1 and Level 2 were based, VY calculated the stress levels in the dryer corresponding to the current plant acoustic signature, and then determined how much the acoustic signature could be increased while maintaining stress levels below the 13,600 psi fatigue limit. A Level 1 limit curve was then constructed by scaling up the current plant acoustic signature at each point along the frequency spectrum of interest by this overall factor. A Level 2 limit curve was produced in the same manner except at 80% of the fatigue limit, or 10,880 psi, arbitrarily selected by VY, to determine the overall factor. During power ascension, the Level 2 limit curve was reached at discrete frequencies at three power levels. In each case VY stopped the power ascension, determined the impact of the new acoustic signature on the dryer stresses, and developed revised Level 2 limit curves to use at higher power steps. Their Level 1 limit curve was never reached. The VY approach is summarized in [7]. |
| | Steam dryer data and evaluations will be performed as required per Attachment 3 "Dryer Data Collection" (Test No. 101) of HC.OP-FT.ZZ-0004(Q), "Extended Power Uprate Power Ascension Testing" supplied by PSEG. The following power ascension approach is proposed for monitoring steam dryer stresses: |
| | : 1. During power ascension, plant data will be collected, as a minimum, every 1% (of CLTP) for trending, every 2.5% (of CLTP) for evaluation, and every 5% (of CLTP) for evaluation and transmittal to the NRC. Target Power Uprate (TPU) is 111.5% of CLTP. Thus, the 2.5% |
| | intervals are at 102.5% and 107.5% CLTP, and the power plateaus are at 105.0%, 110.0%, and 111.5% CLTP. TPU is treated as a plateau. |
| | : 2. At each data point the pressure data from the eight main steam line strain gages will be recorded. (( |
| | (3))) |
| | : 3. Should any power level produce main steam line pressure signals that exceed discrete frequencies in the Level 2 limit curves, a finite element model, which evaluates the limiting points on the dryer, will be run to generate revised limit curves. |
| | : 4. It is not anticipated that the Level I limit curves will be reached. |
| | 2 |
| | |
| | This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information A previous finite element analysis of subscale EPU data found a lowest alternating stress ratio of 1.96 [4]. ACM bias and uncertainty were summarized previously in [8] and are shown in Table 2.1 (a negative bias is conservative). |
| | Table 2.1. Bias and uncertainty for HC1 [8]. |
| | Term Bias (%) Uncertainty (%) |
| | Strain Gage Conversion 0.0 7.2 Strain Gage Location 0.0 4.2 Quad Cities Unit 2 Dryer -3.0 2.9 Pressure Measurement ACM Low Frequency 3.0 0.0 Limitation ACM Accuracy -10.8 25.7 SUBTOTALS -10.8 27.2 (3))) |
| | Limit curves may then be generated based on the limiting stress ratio and the VY practice of assigning the Level 2 limit curves at 80% of the Level 1 limit curves. |
| | 3 |
| | |
| | This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information |
| | : 3. Limit Curves Limit curves were generated from the subscale EPU pressure transducer data collected in May 2006 and reported in [3]. (( |
| | (3))) Level 1 limit curves are found by multiplying the main steam line pressure PSD traces by the square of the corrected limiting stress ratio, while the Level 2 limit curves are found by multiplying the PSD traces by 0.64 of the square of the corrected limiting stress ratio (recovering 80% of the limiting stress ratio), as PSD is related to the square of the pressure. |
| | 4 |
| | |
| | This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information r[ |
| | (3))) |
| | 5 |
| | |
| | This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information |
| | [1 (3))) |
| | 6 |
| | |
| | This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information |
| | : 4. Discussion As in-plant data were previously recorded at CLTP conditions, and reported in [1], it is instructive to compare these data with the Level 2 limit curves determined above. These results are shown in Figures 4.1 and 4.2. It may be seen that the Level 2 limit curves bound the full scale CLTP results across all frequencies of interest. |
| | The strategy to be invoked for power ascension is the following: |
| | ((1. |
| | (3)] |
| | ((2. |
| | (3))) |
| | : 3. Upon achieving TPU for the fuel cycle, PSEG may elect to perform a complete finite element calculation. |
| | 7 |
| | |
| | This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information |
| | [I (3))) |
| | 8 |
| | |
| | This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information (3))) |
| | 9 |
| | |
| This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information | | This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information |
| : 2. Approach The limit curve analysis for HC1 parallels the approach followed by Entergy Vermont Yankee (VY) in its power uprate [6]. In their analysis, two levels of steam dryer performance criteria were described:
| |
| (1) a Level 1 pressure level based on maintaining the ASME allowable alternating stress value on the dryer, and (2) a Level 2 pressure level based on maintaining 80%of the allowable alternating stress value on the dryer. Should Level 2 be reached or exceeded (under the rules to be discussed below), reactor power ascension was to be suspended until an engineering evaluation concluded that further power ascension was justified.
| |
| Should Level I be reached or exceeded, reactor power was to be returned to a previously acceptable power level while an engineering evaluation was undertaken.
| |
| To develop the limit curves upon which Level 1 and Level 2 were based, VY calculated the stress levels in the dryer corresponding to the current plant acoustic signature, and then determined how much the acoustic signature could be increased while maintaining stress levels below the 13,600 psi fatigue limit. A Level 1 limit curve was then constructed by scaling up the current plant acoustic signature at each point along the frequency spectrum of interest by this overall factor. A Level 2 limit curve was produced in the same manner except at 80% of the fatigue limit, or 10,880 psi, arbitrarily selected by VY, to determine the overall factor. During power ascension, the Level 2 limit curve was reached at discrete frequencies at three power levels. In each case VY stopped the power ascension, determined the impact of the new acoustic signature on the dryer stresses, and developed revised Level 2 limit curves to use at higher power steps. Their Level 1 limit curve was never reached. The VY approach is summarized in [7].Steam dryer data and evaluations will be performed as required per Attachment 3 "Dryer Data Collection" (Test No. 101) of HC.OP-FT.ZZ-0004(Q), "Extended Power Uprate Power Ascension Testing" supplied by PSEG. The following power ascension approach is proposed for monitoring steam dryer stresses: 1. During power ascension, plant data will be collected, as a minimum, every 1% (of CLTP) for trending, every 2.5% (of CLTP) for evaluation, and every 5% (of CLTP) for evaluation and transmittal to the NRC. Target Power Uprate (TPU) is 111.5% of CLTP. Thus, the 2.5%intervals are at 102.5% and 107.5% CLTP, and the power plateaus are at 105.0%, 110.0%, and 111.5% CLTP. TPU is treated as a plateau.2. At each data point the pressure data from the eight main steam line strain gages will be recorded.
| |
| [[(3)]]3. Should any power level produce main steam line pressure signals that exceed discrete frequencies in the Level 2 limit curves, a finite element model, which evaluates the limiting points on the dryer, will be run to generate revised limit curves.4. It is not anticipated that the Level I limit curves will be reached.2 This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information A previous finite element analysis of subscale EPU data found a lowest alternating stress ratio of 1.96 [4]. ACM bias and uncertainty were summarized previously in [8] and are shown in Table 2.1 (a negative bias is conservative).
| |
| Table 2.1. Bias and uncertainty for HC1 [8].Term Bias (%) Uncertainty
| |
| (%)Strain Gage Conversion 0.0 7.2 Strain Gage Location 0.0 4.2 Quad Cities Unit 2 Dryer -3.0 2.9 Pressure Measurement ACM Low Frequency 3.0 0.0 Limitation ACM Accuracy -10.8 25.7 SUBTOTALS
| |
| -10.8 27.2 (3)]]Limit curves may then be generated based on the limiting stress ratio and the VY practice of assigning the Level 2 limit curves at 80% of the Level 1 limit curves.3 This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information
| |
| : 3. Limit Curves Limit curves were generated from the subscale EPU pressure transducer data collected in May 2006 and reported in [3]. [[(3)]] Level 1 limit curves are found by multiplying the main steam line pressure PSD traces by the square of the corrected limiting stress ratio, while the Level 2 limit curves are found by multiplying the PSD traces by 0.64 of the square of the corrected limiting stress ratio (recovering 80% of the limiting stress ratio), as PSD is related to the square of the pressure.4 This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information r[(3)]]5 This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information
| |
| [1 (3)]]6 This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information
| |
| : 4. Discussion As in-plant data were previously recorded at CLTP conditions, and reported in [1], it is instructive to compare these data with the Level 2 limit curves determined above. These results are shown in Figures 4.1 and 4.2. It may be seen that the Level 2 limit curves bound the full scale CLTP results across all frequencies of interest.The strategy to be invoked for power ascension is the following:
| |
| [[1.(3)][[2.(3)]]3. Upon achieving TPU for the fuel cycle, PSEG may elect to perform a complete finite element calculation.
| |
| 7 This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information
| |
| [I (3)]]8 This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information (3)]]9 This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information
| |
| : 5. References | | : 5. References |
| : 1. Continuum Dynamics, Inc. 2007. Revised Hydrodynamic Loads on Hope Creek Unit 1 Steam Dryer to 200 Hz (Rev. 0). C.D.I. Report No. 07-01 (Proprietary). | | : 1. Continuum Dynamics, Inc. 2007. Revised Hydrodynamic Loads on Hope Creek Unit 1 Steam Dryer to 200 Hz (Rev. 0). C.D.I. Report No. 07-01 (Proprietary). |
| : 2. Continuum Dynamics, Inc. 2007. EPU Conditions in the Main Steam Lines at Hope Creek Unit 1: Additional Subscale Four Line Tests (Rev. 0). C.D.I. Technical Note No. 07-01 (Proprietary). | | : 2. Continuum Dynamics, Inc. 2007. EPU Conditions in the Main Steam Lines at Hope Creek Unit 1: Additional Subscale Four Line Tests (Rev. 0). C.D.I. Technical Note No. 07-01 (Proprietary). |
| : 3. Continuum Dynamics, Inc. 2007. Estimating High Frequency Flow Induced Vibration in the Main Steam Lines at Hope Creek Unit 1: A Subscale Four Line Investigation of Standpipe Behavior (Rev. 2). C.D.I. Report No. 06-16 (Proprietary). | | : 3. Continuum Dynamics, Inc. 2007. Estimating High Frequency Flow Induced Vibration in the Main Steam Lines at Hope Creek Unit 1: A Subscale Four Line Investigation of Standpipe Behavior (Rev. 2). C.D.I. Report No. 06-16 (Proprietary). |
| : 4. Continuum Dynamics, Inc. 2007. Stress Analysis of the Hope Creek Unit 1 Steam Dryer at EPU Conditions using One-Eighth Scale Model Pressure Measurement Data (Rev. 2). C.D.I.Report No. 06-27.5. Continuum Dynamics, Inc. 2005. Methodology to Determine Unsteady Pressure Loading on Components in Reactor Steam Domes (Rev. 6). C.D.I. Report No. 04-09 (Proprietary). | | : 4. Continuum Dynamics, Inc. 2007. Stress Analysis of the Hope Creek Unit 1 Steam Dryer at EPU Conditions using One-Eighth Scale Model Pressure Measurement Data (Rev. 2). C.D.I. |
| : 6. Entergy Nuclear Northeast. | | Report No. 06-27. |
| 2005. Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 263 -Supplement No. 26: Extended Power Uprate -Steam Dryer Analyses and Monitoring, Attachment | | : 5. Continuum Dynamics, Inc. 2005. Methodology to Determine Unsteady Pressure Loading on Components in Reactor Steam Domes (Rev. 6). C.D.I. Report No. 04-09 (Proprietary). |
| : 2. Letter No. BVY 05-034 to Document Control Desk, U. S. Nuclear Regulatory Commission.
| | : 6. Entergy Nuclear Northeast. 2005. Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 263 - Supplement No. 26: Extended Power Uprate - |
| Dated 31 March 2005.7. State of Vermont Public Service Board. 2006. Petition of Vermont Department of Public Service for an Investigation into the Reliability of the Steam Dryer and Resulting Performance of the Vermont Yankee Nuclear Power Station under Uprate Conditions. | | Steam Dryer Analyses and Monitoring, Attachment 2. Letter No. BVY 05-034 to Document Control Desk, U. S. Nuclear Regulatory Commission. Dated 31 March 2005. |
| Docket No. 7195. Hearings held 17-18 August 2006.8. PSEG. 2007. Hope Creek Generating Station Facility Operating License NPF-57 Docket No.50-354: Request for License Amendment Extended Power Uprate Steam Dryer Evaluation. | | : 7. State of Vermont Public Service Board. 2006. Petition of Vermont Department of Public Service for an Investigation into the Reliability of the Steam Dryer and Resulting Performance of the Vermont Yankee Nuclear Power Station under Uprate Conditions. |
| Attachment No. 7 (Rev. 1). Dated April 2007.10}} | | Docket No. 7195. Hearings held 17-18 August 2006. |
| | : 8. PSEG. 2007. Hope Creek Generating Station Facility Operating License NPF-57 Docket No. |
| | 50-354: Request for License Amendment Extended Power Uprate Steam Dryer Evaluation. |
| | Attachment No. 7 (Rev. 1). Dated April 2007. |
| | 10}} |
Letter Sequence Request |
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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
|
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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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 AscensionML071720370 |
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Bilanin A, Teske M Continuum Dynamics |
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Office of Nuclear Reactor Regulation, Public Service Enterprise Group |
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References |
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4500400038, LCR H05-01, Rev 1, LR-N07-0113 07-19NP, Rev 0 |
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Category:Report
MONTHYEARML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23249A2622023-09-0606 September 2023 Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021) LR-N21-0007, Report of Changes, Tests, and Experiments2021-01-28028 January 2021 Report of Changes, Tests, and Experiments ML20121A1332020-03-0303 March 2020 Biological Opinion 2019 Annual Incidental Take Report LR-N18-0056, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-07-25025 July 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions LR-N18-0057, Pressure and Temperature Limits Report, Revision 12018-06-0808 June 2018 Pressure and Temperature Limits Report, Revision 1 LR-N17-0163, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary2017-11-0909 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary LR-N17-0092, Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2017-04-28028 April 2017 Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report ML17188A2672017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) LR-N17-0044, Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version)2017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) LR-N17-0049, Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.12017-02-0909 February 2017 Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.1 LR-N17-0036, License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 202017-02-0707 February 2017 License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20 ML17188A2652016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi LR-N17-0044, Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Ve2016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi LR-N16-0112, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal2016-12-29029 December 2016 Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal ML16256A6412016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. LR-N16-0113, NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses.2016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. ML16256A6422016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. ML16256A6402016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment LR-N16-0113, NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2.2016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. LR-N16-0113, Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment2016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment ML16256A6432016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0113, ISG-06 Enclosure B Roadmap, Phase 2 Documents.2016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0099, GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21.2016-05-31031 May 2016 GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21. ML16049A6092016-02-29029 February 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident and Staff Closure LR-N16-0113, NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan.2015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. LR-N15-0178, NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary)2015-09-30030 September 2015 NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary) ML16256A6442015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. LR-N14-0248, Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5.2014-12-0909 December 2014 Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5. ML15030A2942014-09-22022 September 2014 Table 03, Effluent Data Tritium Activity ML15030A2952014-09-22022 September 2014 Table 04, Groundwater Measurements and Elevations - First Quarter 2014 LR-N14-0175, CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-92332014-08-11011 August 2014 CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-9233 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 LR-N14-0112, CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station2014-04-25025 April 2014 CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station LR-N14-0035, PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima...2014-03-28028 March 2014 PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima... ML13365A2532014-02-11011 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14028A0742014-02-0606 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Hope Creek Generating Station, TAC No. MF0867 LR-N14-0024, Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic2014-01-29029 January 2014 Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic ML13266A2972013-11-18018 November 2013 Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 92012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 9 LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G2012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G ML13052A6772012-11-30030 November 2012 Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 5 ML13052A6782012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 9 ML13052A6792012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G LR-N12-0366, Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 52012-11-30030 November 2012 Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 5 LR-N12-0366, Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary2012-11-28028 November 2012 Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary ML13052A6752012-11-28028 November 2012 Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary ML13052A6802012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix H Through Appendix J ML13052A6812012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-1 Through K-75 ML13052A6822012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-149 2023-09-06
[Table view] Category:Technical
MONTHYEARML23249A2622023-09-0606 September 2023 Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021) ML20121A1332020-03-0303 March 2020 Biological Opinion 2019 Annual Incidental Take Report LR-N18-0057, Pressure and Temperature Limits Report, Revision 12018-06-0808 June 2018 Pressure and Temperature Limits Report, Revision 1 LR-N17-0163, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary2017-11-0909 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary LR-N17-0092, Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2017-04-28028 April 2017 Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report LR-N17-0044, Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version)2017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) ML17188A2672017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) ML17188A2652016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi LR-N17-0044, Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Ve2016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi ML16256A6422016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. LR-N16-0113, NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2.2016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. ML16256A6442015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. LR-N15-0178, NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary)2015-09-30030 September 2015 NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary) LR-N16-0113, NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan.2015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. ML15030A2952014-09-22022 September 2014 Table 04, Groundwater Measurements and Elevations - First Quarter 2014 ML15030A2942014-09-22022 September 2014 Table 03, Effluent Data Tritium Activity ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML13365A2532014-02-11011 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14028A0742014-02-0606 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Hope Creek Generating Station, TAC No. MF0867 LR-N14-0024, Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic2014-01-29029 January 2014 Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G2012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G ML13052A6772012-11-30030 November 2012 Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 5 ML13052A6782012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 9 ML13052A6792012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 92012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 9 LR-N12-0366, Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 52012-11-30030 November 2012 Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 5 LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix H Through Appendix J2012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix H Through Appendix J LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-1 Through K-752012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-1 Through K-75 LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-1492012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-149 ML13052A6802012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix H Through Appendix J ML13052A6812012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-1 Through K-75 ML13052A6822012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-149 LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix L Through Appendix N2012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix L Through Appendix N LR-N11-0289, Site-Specific Cost Estimates2011-09-15015 September 2011 Site-Specific Cost Estimates ML1027901062010-09-30030 September 2010 NEDO-33506, Rev 0, Hope Creek, Final Feedwater Temperture Reduction and Feedwater Heaters Out-of-Service. LR-N10-0239, 0000-0119-1728, Revision 0, Hope Creek Cycle 17 Stability Results for GE14i Support, Attachment 12010-06-30030 June 2010 0000-0119-1728, Revision 0, Hope Creek Cycle 17 Stability Results for GE14i Support, Attachment 1 ML1029806222010-04-30030 April 2010 Email from Cahill, Christopher to Burritt, Arthur; Cline, Leonard, FW: AFW Missile Barrier. ML1013903182009-11-15015 November 2009 Calculation 80096650, Revision 0, Leakage Reduction Program Calculation, Attachment 6 to LR-N10-0163 LR-N08-0224, Attachment 6 - Hope Creek Final Stress Assessment of Hope Creek, Unit 1 Steam Dryer at 115% CLTP Conditions, C.D.I. Report No. 08-21NP, Revision 12008-10-31031 October 2008 Attachment 6 - Hope Creek Final Stress Assessment of Hope Creek, Unit 1 Steam Dryer at 115% CLTP Conditions, C.D.I. Report No. 08-21NP, Revision 1 LR-N08-0224, Attachment 5 - Limit Curves with ACM Rev. 4 for 115% Power Level Basis at Hope Creek, Unit 1, C.D.I. Technical Note No. 08-22NP, Revision 02008-10-31031 October 2008 Attachment 5 - Limit Curves with ACM Rev. 4 for 115% Power Level Basis at Hope Creek, Unit 1, C.D.I. Technical Note No. 08-22NP, Revision 0 ML0831008282008-10-31031 October 2008 Attachment 5 - Limit Curves with ACM Rev. 4 for 115% Power Level Basis at Hope Creek, Unit 1, C.D.I. Technical Note No. 08-22NP, Revision 0 LR-N08-0199, Attachment 4 - C.D.I. Technical Note No. 08-20NP, Rev. 1, Limit Curves with ACM Rev. 4 for 111.5% Power Level Basis at Hope Creek Unit 1.2008-08-31031 August 2008 Attachment 4 - C.D.I. Technical Note No. 08-20NP, Rev. 1, Limit Curves with ACM Rev. 4 for 111.5% Power Level Basis at Hope Creek Unit 1. ML0825403292008-08-31031 August 2008 Attachment 4 - C.D.I. Technical Note No. 08-20NP, Rev. 1, Limit Curves with ACM Rev. 4 for 111.5% Power Level Basis at Hope Creek Unit 1. LR-N08-0199, Attachment 5 - C.D.I. Report.No. 08-29NP, Rev. 0, Final Stress Assessment of Hope Creek Unit 1 Steam Dryer at 111.5% CLTP Conditions.2008-08-31031 August 2008 Attachment 5 - C.D.I. Report.No. 08-29NP, Rev. 0, Final Stress Assessment of Hope Creek Unit 1 Steam Dryer at 111.5% CLTP Conditions. ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 LR-N08-0123, C.D.I. Technical Note No. 07-29NP, Revision 2, Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Hope Creek Unit 1.2008-05-31031 May 2008 C.D.I. Technical Note No. 07-29NP, Revision 2, Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Hope Creek Unit 1. ML0813604922008-04-30030 April 2008 Attachment 2, C.D.I. Technical Note No. 07-29NP, Revision 1, Limit Curve Analysis with ACM Rev. 4 at Hope Creek Unit 1. ML0804205442008-01-31031 January 2008 CDI Report No. 07-17NP Revision 3 Stress Assessment of Hope Creek Unit 1 Steam Dryer Based on Revision 4 Loads Mode. LR-N08-0033, CDI Report No. 07-17NP, Revision 4, Stress Assessment of Hope Creek Unit I Steam Dryer Based on Revision 4 Loads Model.2008-01-31031 January 2008 CDI Report No. 07-17NP, Revision 4, Stress Assessment of Hope Creek Unit I Steam Dryer Based on Revision 4 Loads Model. ML0726404112007-08-31031 August 2007 CDI Report 07-17NP, Stress Assessment of Hope Creek, Unit 1 Steam Dryer Based on Revision 4 Loads Model Revision 2. 2023-09-06
[Table view] |
Text
Attachment 2 LR-N07-0113 LCR H05-01, Rev. 1 Hope Creek Generating Station Facility Operating License NPF-57 Docket No. 50-354 Extended Power Uprate Lirnt Curve Analysis for Dryer Stress Prediction During Power Ascension of Hope Creek Unit 1 C.D.I. Technical Note No. 07-19NP, Revision 0 May 2007
This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information C.D.I. Technical Note No. 07-19NP Limit Curve Analysis for Dryer Stress Prediction During Power Ascension of Hope Creek Unit 1 Revision 0 Prepared by Continuum Dynamics, Inc.
34 Lexington Avenue Ewing, NJ 08618 Prepared under Purchase Order No. 4500400038 for Nuclear Business Unit, PSEG Nuclear LLC Materials Center, Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Approved by Alan J. lRnin Reviewed by Milton E. Teske May 2007
This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information Table of Contents Section Page T able of C ontents ..................................................................... i
- 1. Introduction ............................................................................ 1
- 2. A pproach ............................................................................... 2
- 3. L im it C urves ........................................................................... 4
- 4. D iscussion ............................................................................. 7
- 5. R eferences ............................................................................ 10
This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information
- 1. Introduction PSEG is planning power ascension of Hope Creek Unit 1 (HC1). During ascension, it is required to monitor the dryer stresses anticipated at plant power levels that have not yet been achieved. A convenient way to track these stresses is through the use of limit curves. Limit curves provide an upper bound safeguard against the potential for dryer stresses becoming higher than allowable, by estimating the not-to-be-exceeded main steam line pressure levels. In the case of HC1, main steam line data have been analyzed at Current Licensed Thermal Power (CLTP) in-plant [1] and in subscale tests [2], and at Extended Power Uprate (EPU) in subscale tests [3].
EPU at HC1 is 115% of CLTP. A finite element model stress analysis has been undertaken on the EPU subscale test data [4]. These existing data provide the basis for generation of the limit curves to be used during HC 1 power ascension.
Continuum Dynamics, Inc. (C.D.I.) has developed an acoustic circuit methodology (ACM) that determines the relationship between main steam line data and pressure on the steam dryer [5]. This methodology, and the use of a finite element model analysis, provides the computational engine behind which dryer stresses at distinct steam dryer locations may be tracked through power ascension. Limit curves allow the PSEG engineer to estimate dryer stress levels conservatively, by simply comparing the main steam line pressure readings (represented in Power Spectral Density, or PSD, format) with the upper bound PSD derived from existing in-plant and subscale test data.
This technical note summarizes the proposed approach that will be used to track the anticipated stress levels in the HC1 steam dryer during power ascension, and the options available to PSEG should a limit curve be reached.
This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information
- 2. Approach The limit curve analysis for HC1 parallels the approach followed by Entergy Vermont Yankee (VY) in its power uprate [6]. In their analysis, two levels of steam dryer performance criteria were described: (1) a Level 1 pressure level based on maintaining the ASME allowable alternating stress value on the dryer, and (2) a Level 2 pressure level based on maintaining 80%
of the allowable alternating stress value on the dryer. Should Level 2 be reached or exceeded (under the rules to be discussed below), reactor power ascension was to be suspended until an engineering evaluation concluded that further power ascension was justified. Should Level I be reached or exceeded, reactor power was to be returned to a previously acceptable power level while an engineering evaluation was undertaken.
To develop the limit curves upon which Level 1 and Level 2 were based, VY calculated the stress levels in the dryer corresponding to the current plant acoustic signature, and then determined how much the acoustic signature could be increased while maintaining stress levels below the 13,600 psi fatigue limit. A Level 1 limit curve was then constructed by scaling up the current plant acoustic signature at each point along the frequency spectrum of interest by this overall factor. A Level 2 limit curve was produced in the same manner except at 80% of the fatigue limit, or 10,880 psi, arbitrarily selected by VY, to determine the overall factor. During power ascension, the Level 2 limit curve was reached at discrete frequencies at three power levels. In each case VY stopped the power ascension, determined the impact of the new acoustic signature on the dryer stresses, and developed revised Level 2 limit curves to use at higher power steps. Their Level 1 limit curve was never reached. The VY approach is summarized in [7].
Steam dryer data and evaluations will be performed as required per Attachment 3 "Dryer Data Collection" (Test No. 101) of HC.OP-FT.ZZ-0004(Q), "Extended Power Uprate Power Ascension Testing" supplied by PSEG. The following power ascension approach is proposed for monitoring steam dryer stresses:
- 1. During power ascension, plant data will be collected, as a minimum, every 1% (of CLTP) for trending, every 2.5% (of CLTP) for evaluation, and every 5% (of CLTP) for evaluation and transmittal to the NRC. Target Power Uprate (TPU) is 111.5% of CLTP. Thus, the 2.5%
intervals are at 102.5% and 107.5% CLTP, and the power plateaus are at 105.0%, 110.0%, and 111.5% CLTP. TPU is treated as a plateau.
- 2. At each data point the pressure data from the eight main steam line strain gages will be recorded. ((
(3)))
- 3. Should any power level produce main steam line pressure signals that exceed discrete frequencies in the Level 2 limit curves, a finite element model, which evaluates the limiting points on the dryer, will be run to generate revised limit curves.
- 4. It is not anticipated that the Level I limit curves will be reached.
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This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information A previous finite element analysis of subscale EPU data found a lowest alternating stress ratio of 1.96 [4]. ACM bias and uncertainty were summarized previously in [8] and are shown in Table 2.1 (a negative bias is conservative).
Table 2.1. Bias and uncertainty for HC1 [8].
Term Bias (%) Uncertainty (%)
Strain Gage Conversion 0.0 7.2 Strain Gage Location 0.0 4.2 Quad Cities Unit 2 Dryer -3.0 2.9 Pressure Measurement ACM Low Frequency 3.0 0.0 Limitation ACM Accuracy -10.8 25.7 SUBTOTALS -10.8 27.2 (3)))
Limit curves may then be generated based on the limiting stress ratio and the VY practice of assigning the Level 2 limit curves at 80% of the Level 1 limit curves.
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This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information
- 3. Limit Curves Limit curves were generated from the subscale EPU pressure transducer data collected in May 2006 and reported in [3]. ((
(3))) Level 1 limit curves are found by multiplying the main steam line pressure PSD traces by the square of the corrected limiting stress ratio, while the Level 2 limit curves are found by multiplying the PSD traces by 0.64 of the square of the corrected limiting stress ratio (recovering 80% of the limiting stress ratio), as PSD is related to the square of the pressure.
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This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information r[
(3)))
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This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information
- 4. Discussion As in-plant data were previously recorded at CLTP conditions, and reported in [1], it is instructive to compare these data with the Level 2 limit curves determined above. These results are shown in Figures 4.1 and 4.2. It may be seen that the Level 2 limit curves bound the full scale CLTP results across all frequencies of interest.
The strategy to be invoked for power ascension is the following:
((1.
(3)]
((2.
(3)))
- 3. Upon achieving TPU for the fuel cycle, PSEG may elect to perform a complete finite element calculation.
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This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information
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8
This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information (3)))
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This Report Does Not Contain Continuum Dynamics, Inc. Proprietary Information
- 5. References
- 1. Continuum Dynamics, Inc. 2007. Revised Hydrodynamic Loads on Hope Creek Unit 1 Steam Dryer to 200 Hz (Rev. 0). C.D.I. Report No. 07-01 (Proprietary).
- 2. Continuum Dynamics, Inc. 2007. EPU Conditions in the Main Steam Lines at Hope Creek Unit 1: Additional Subscale Four Line Tests (Rev. 0). C.D.I. Technical Note No. 07-01 (Proprietary).
- 3. Continuum Dynamics, Inc. 2007. Estimating High Frequency Flow Induced Vibration in the Main Steam Lines at Hope Creek Unit 1: A Subscale Four Line Investigation of Standpipe Behavior (Rev. 2). C.D.I. Report No. 06-16 (Proprietary).
- 4. Continuum Dynamics, Inc. 2007. Stress Analysis of the Hope Creek Unit 1 Steam Dryer at EPU Conditions using One-Eighth Scale Model Pressure Measurement Data (Rev. 2). C.D.I.
Report No. 06-27.
- 5. Continuum Dynamics, Inc. 2005. Methodology to Determine Unsteady Pressure Loading on Components in Reactor Steam Domes (Rev. 6). C.D.I. Report No. 04-09 (Proprietary).
- 6. Entergy Nuclear Northeast. 2005. Vermont Yankee Nuclear Power Station Technical Specification Proposed Change No. 263 - Supplement No. 26: Extended Power Uprate -
Steam Dryer Analyses and Monitoring, Attachment 2. Letter No. BVY 05-034 to Document Control Desk, U. S. Nuclear Regulatory Commission. Dated 31 March 2005.
- 7. State of Vermont Public Service Board. 2006. Petition of Vermont Department of Public Service for an Investigation into the Reliability of the Steam Dryer and Resulting Performance of the Vermont Yankee Nuclear Power Station under Uprate Conditions.
Docket No. 7195. Hearings held 17-18 August 2006.
- 8. PSEG. 2007. Hope Creek Generating Station Facility Operating License NPF-57 Docket No.
50-354: Request for License Amendment Extended Power Uprate Steam Dryer Evaluation.
Attachment No. 7 (Rev. 1). Dated April 2007.
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