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| number = ML17222A165
| number = ML17222A165
| issue date = 08/10/2017
| issue date = 08/10/2017
| title = 2017/08/10 NRR E-mail Capture - Hope Creek: Final Request for Information, Pressure-Temperature Limit Report Request (MF9502)
| title = NRR E-mail Capture - Hope Creek: Final Request for Information, Pressure-Temperature Limit Report Request (MF9502)
| author name = Regner L M
| author name = Regner L
| author affiliation = NRC/NRR/DORL/LPLIV
| author affiliation = NRC/NRR/DORL/LPLIV
| addressee name = Duke P R
| addressee name = Duke P
| addressee affiliation = PSEG Nuclear, LLC
| addressee affiliation = PSEG Nuclear, LLC
| docket = 05000354
| docket = 05000354
Line 14: Line 14:
| page count = 3
| page count = 3
}}
}}
=Text=
{{#Wiki_filter: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.
1
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
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:}}

Latest revision as of 07:05, 4 December 2019

NRR E-mail Capture - Hope Creek: Final Request for Information, Pressure-Temperature Limit Report Request (MF9502)
ML17222A165
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 08/10/2017
From: Lisa Regner
Plant Licensing Branch IV
To: Duke P
Public Service Enterprise Group
References
MF9502
Download: ML17222A165 (3)
v • d • e


Text

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.

1

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

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:

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