ML17222A165: Difference between revisions
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{{#Wiki_filter:NRR-PMDAPEm Resource From: | {{#Wiki_filter:1 NRR-PMDAPEm Resource From: | ||
Regner, Lisa Sent: | |||
Thursday, August 10, 2017 11:02 AM To: | |||
Paul.Duke@pseg.com Cc: | |||
Regner, Lisa | |||
==Subject:== | ==Subject:== | ||
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Final Request for Additional Information On August 8, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff sent PSEG Nuclear LLC (PSEG) the draft Request for Additional Information (RAI) provided below. This RAI relates to a license amendment request (LAR) that would revise the reactor coolant system pressure-temperature (P-T) limit curves and relocate the new P-T limit curves from the Hope Creek Technical Specifications (TS) to a new P-T Limits Report (PTLR). | Final Request for Additional Information On August 8, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff sent PSEG Nuclear LLC (PSEG) the draft Request for Additional Information (RAI) provided below. This RAI relates to a license amendment request (LAR) that would revise the reactor coolant system pressure-temperature (P-T) limit curves and relocate the new P-T limit curves from the Hope Creek Technical Specifications (TS) to a new P-T Limits Report (PTLR). | ||
PSEG staff subsequently informed the NRC staff that the information requested by the NRC staff was understood and no additional clarification of the RAI was necessary. Mr. Paul Duke agreed to provide a response to this final RAI within 30 days from the date of this correspondence. The NRC staff also informed the licensee that a publicly available version of this final RAI would be placed in the NRCs Agencywide Documents Access and Management System. | PSEG staff subsequently informed the NRC staff that the information requested by the NRC staff was understood and no additional clarification of the RAI was necessary. Mr. Paul Duke agreed to provide a response to this final RAI within 30 days from the date of this correspondence. The NRC staff also informed the licensee that a publicly available version of this final RAI would be placed in the NRCs Agencywide Documents Access and Management System. | ||
REQUEST FOR ADDITIONAL INFORMATION HOPE CREEK GENERATING STATION By letter dated March 27, 2017 (ADAMS Accession No. ML17086A364), PSEG submitted a License Amendment Request (LAR) for Hope Creek, pursuant to 10 CFR 50.90 (CAC No. MF9502). The LAR proposes changes to the Hope Creek Technical Specifications (TS) that would revise the reactor coolant system pressure-temperature (P-T) limit curves and relocate the new P-T limit curves from the Hope Creek Technical Specifications (TS) to a new P-T Limits Report (PTLR). | REQUEST FOR ADDITIONAL INFORMATION HOPE CREEK GENERATING STATION By {{letter dated|date=March 27, 2017|text=letter dated March 27, 2017}} (ADAMS Accession No. ML17086A364), PSEG submitted a License Amendment Request (LAR) for Hope Creek, pursuant to 10 CFR 50.90 (CAC No. MF9502). The LAR proposes changes to the Hope Creek Technical Specifications (TS) that would revise the reactor coolant system pressure-temperature (P-T) limit curves and relocate the new P-T limit curves from the Hope Creek Technical Specifications (TS) to a new P-T Limits Report (PTLR). | ||
The staff has determined that additional information is required in order to complete its review of the subject LAR. In order complete an expedited review of this LARas needed to support a separate technical review of a linked power uprate amendment application that relies on the proposed PTLR. | The staff has determined that additional information is required in order to complete its review of the subject LAR. In order complete an expedited review of this LARas needed to support a separate technical review of a linked power uprate amendment application that relies on the proposed PTLR. | ||
Request for Hope Creek Integrated Surveillance Program (ISP) Data from BWRVIP-135 Tables 10, 11, and 12 of the proposed Hope Creek PTLR list the adjusted reference temperature (ART) calculations and the supporting material property and neutron fluence inputs for the Hope Creek reactor pressure vessel (RPV) beltline materials, applicable to 32 effective full power years (EFPY), 44 EFPY, and 56 EFPY, respectively. Chemistry factor values for the ISP material line entries in the ART tables are marked as EPRI Proprietary Information. | Request for Hope Creek Integrated Surveillance Program (ISP) Data from BWRVIP-135 Tables 10, 11, and 12 of the proposed Hope Creek PTLR list the adjusted reference temperature (ART) calculations and the supporting material property and neutron fluence inputs for the Hope Creek reactor pressure vessel (RPV) beltline materials, applicable to 32 effective full power years (EFPY), 44 EFPY, and 56 EFPY, respectively. Chemistry factor values for the ISP material line entries in the ART tables are marked as EPRI Proprietary Information. | ||
PTLR Criterion 7 of Generic Letter (GL) 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protections System Limits, specifies that the licensee should provide supplemental data and calculations of the chemistry factor in the PTLR if the surveillance data are used in the ART [adjusted reference temperature] calculation. Therefore, in order to ensure that the proposed Hope Creek PTLR is consistent with Criterion 7 in GL 96-03, provide supporting data and calculations from the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Integrated Surveillance Program Data Source Book (BWRVIP-135) for determining the proprietary ISP material chemistry factor values listed in Tables 10, 11, and 12 of the Hope Creek PTLR. | PTLR Criterion 7 of Generic Letter (GL) 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protections System Limits, specifies that the licensee should provide supplemental data and calculations of the chemistry factor in the PTLR if the surveillance data are used in the ART [adjusted reference temperature] calculation. Therefore, in order to ensure that the proposed Hope Creek PTLR is consistent with Criterion 7 in GL 96-03, provide supporting data and calculations from the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Integrated Surveillance Program Data Source Book (BWRVIP-135) for determining the proprietary ISP material chemistry factor values listed in Tables 10, 11, and 12 of the Hope Creek PTLR. | ||
Lisa M. Regner Senior Project Manager Branch 4, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Lisa.Regner@NRC.gov 301-415-1906 OWFN 9D14 | 2 Lisa M. Regner Senior Project Manager Branch 4, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Lisa.Regner@NRC.gov 301-415-1906 OWFN 9D14 | ||
Hearing Identifier: | Hearing Identifier: | ||
NRR_PMDA Email Number: | |||
3653 Mail Envelope Properties (313ce0bbd9b44131bfbde260812e104f) | |||
==Subject:== | ==Subject:== | ||
Final RAI: P-T Limit Report License Amendment Application (MF9502) | Final RAI: P-T Limit Report License Amendment Application (MF9502) | ||
Sent Date: | Sent Date: | ||
8/10/2017 11:01:40 AM Received Date: | |||
8/10/2017 11:01:41 AM From: | |||
Regner, Lisa Created By: | |||
Lisa.Regner@nrc.gov Recipients: | |||
"Regner, Lisa" <Lisa.Regner@nrc.gov> | "Regner, Lisa" <Lisa.Regner@nrc.gov> | ||
Tracking Status: None "Paul.Duke@pseg.com" <Paul.Duke@pseg.com> | Tracking Status: None "Paul.Duke@pseg.com" <Paul.Duke@pseg.com> | ||
Tracking Status: None Post Office: | Tracking Status: None Post Office: | ||
HQPWMSMRS01.nrc.gov Files Size Date & Time MESSAGE 3344 8/10/2017 11:01:41 AM Options Priority: | |||
Standard Return Notification: | |||
No Reply Requested: | |||
No Sensitivity: | |||
Normal Expiration Date: | |||
Recipients Received:}} | Recipients Received:}} | ||
Latest revision as of 14:40, 8 January 2025
| ML17222A165 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/10/2017 |
| From: | Lisa Regner Plant Licensing Branch IV |
| To: | Duke P Public Service Enterprise Group |
| References | |
| MF9502 | |
| Download: ML17222A165 (3) | |
Text
1 NRR-PMDAPEm Resource From:
Regner, Lisa Sent:
Thursday, August 10, 2017 11:02 AM To:
Paul.Duke@pseg.com Cc:
Regner, Lisa
Subject:
Final RAI: P-T Limit Report License Amendment Application (MF9502)
Final Request for Additional Information On August 8, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff sent PSEG Nuclear LLC (PSEG) the draft Request for Additional Information (RAI) provided below. This RAI relates to a license amendment request (LAR) that would revise the reactor coolant system pressure-temperature (P-T) limit curves and relocate the new P-T limit curves from the Hope Creek Technical Specifications (TS) to a new P-T Limits Report (PTLR).
PSEG staff subsequently informed the NRC staff that the information requested by the NRC staff was understood and no additional clarification of the RAI was necessary. Mr. Paul Duke agreed to provide a response to this final RAI within 30 days from the date of this correspondence. The NRC staff also informed the licensee that a publicly available version of this final RAI would be placed in the NRCs Agencywide Documents Access and Management System.
REQUEST FOR ADDITIONAL INFORMATION HOPE CREEK GENERATING STATION By letter dated March 27, 2017 (ADAMS Accession No. ML17086A364), PSEG submitted a License Amendment Request (LAR) for Hope Creek, pursuant to 10 CFR 50.90 (CAC No. MF9502). The LAR proposes changes to the Hope Creek Technical Specifications (TS) that would revise the reactor coolant system pressure-temperature (P-T) limit curves and relocate the new P-T limit curves from the Hope Creek Technical Specifications (TS) to a new P-T Limits Report (PTLR).
The staff has determined that additional information is required in order to complete its review of the subject LAR. In order complete an expedited review of this LARas needed to support a separate technical review of a linked power uprate amendment application that relies on the proposed PTLR.
Request for Hope Creek Integrated Surveillance Program (ISP) Data from BWRVIP-135 Tables 10, 11, and 12 of the proposed Hope Creek PTLR list the adjusted reference temperature (ART) calculations and the supporting material property and neutron fluence inputs for the Hope Creek reactor pressure vessel (RPV) beltline materials, applicable to 32 effective full power years (EFPY), 44 EFPY, and 56 EFPY, respectively. Chemistry factor values for the ISP material line entries in the ART tables are marked as EPRI Proprietary Information.
PTLR Criterion 7 of Generic Letter (GL) 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protections System Limits, specifies that the licensee should provide supplemental data and calculations of the chemistry factor in the PTLR if the surveillance data are used in the ART [adjusted reference temperature] calculation. Therefore, in order to ensure that the proposed Hope Creek PTLR is consistent with Criterion 7 in GL 96-03, provide supporting data and calculations from the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Integrated Surveillance Program Data Source Book (BWRVIP-135) for determining the proprietary ISP material chemistry factor values listed in Tables 10, 11, and 12 of the Hope Creek PTLR.
2 Lisa M. Regner Senior Project Manager Branch 4, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Lisa.Regner@NRC.gov 301-415-1906 OWFN 9D14
Hearing Identifier:
NRR_PMDA Email Number:
3653 Mail Envelope Properties (313ce0bbd9b44131bfbde260812e104f)
Subject:
Final RAI: P-T Limit Report License Amendment Application (MF9502)
Sent Date:
8/10/2017 11:01:40 AM Received Date:
8/10/2017 11:01:41 AM From:
Regner, Lisa Created By:
Lisa.Regner@nrc.gov Recipients:
"Regner, Lisa" <Lisa.Regner@nrc.gov>
Tracking Status: None "Paul.Duke@pseg.com" <Paul.Duke@pseg.com>
Tracking Status: None Post Office:
HQPWMSMRS01.nrc.gov Files Size Date & Time MESSAGE 3344 8/10/2017 11:01:41 AM Options Priority:
Standard Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
Recipients Received: