ML16180A249: Difference between revisions

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| number = ML16180A249
| number = ML16180A249
| issue date = 06/27/2016
| issue date = 06/27/2016
| title = 2016/06/27 NRR E-mail Capture - Hope Creek Generating Station - Acceptance Review of LAR to Amend TSs to Modify Section 2.1, Safety Limits (CAC No. MF7793)
| title = NRR E-mail Capture - Hope Creek Generating Station - Acceptance Review of LAR to Amend TSs to Modify Section 2.1, Safety Limits
| author name = Parker C J
| author name = Parker C
| author affiliation = NRC/NRR/DORL/LPLI-2
| author affiliation = NRC/NRR/DORL/LPLI-2
| addressee name = Duke P R, Thomas B
| addressee name = Duke P, Thomas B
| addressee affiliation = PSEG Nuclear, LLC
| addressee affiliation = PSEG Nuclear, LLC
| docket = 05000354
| docket = 05000354
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:1NRR-PMDAPEm ResourceFrom:Parker, Carleen JSent:Monday, June 27, 2016 2:19 PMTo:Duke, Paul R. (Paul.Duke@pseg.com); Thomas, Brian J. (Brian.Thomas@pseg.com)Cc:BROADDUS, Doug A; Forsaty, Fred M; Tilton, Caroline E; OESTERLE, ERIC R
{{#Wiki_filter:NRR-PMDAPEm Resource From:                             Parker, Carleen J Sent:                             Monday, June 27, 2016 2:19 PM To:                               Duke, Paul R. (Paul.Duke@pseg.com); Thomas, Brian J. (Brian.Thomas@pseg.com)
Cc:                               BROADDUS, Doug A; Forsaty, Fred M; Tilton, Caroline E; OESTERLE, ERIC R


==Subject:==
==Subject:==
Acceptance Review - Hope Creek LAR To Modify TS 2.1, Safety LimitsPaul, By letter dated June 8, 2016, PSEG Nuclear LLC submitted a license amendment request to modify Technical Specification (TS) Section 2.1, Safety Limits, for Hope Creek Generating Station (HCGS). Specifically, this change would incorporate a revised Safety Limit Minimum Critical Power Ratio (SLMCPR) for single recirculation loop operation (SLO) due to the cycle specific analysis performed by Global Nuclear Fuel for HCGS Cycle 21.  
Acceptance Review - Hope Creek LAR To Modify TS 2.1, Safety Limits
 
: Paul, By letter dated June 8, 2016, PSEG Nuclear LLC submitted a license amendment request to modify Technical Specification (TS) Section 2.1, Safety Limits, for Hope Creek Generating Station (HCGS). Specifically, this change would incorporate a revised Safety Limit Minimum Critical Power Ratio (SLMCPR) for single recirculation loop operation (SLO) due to the cycle specific analysis performed by Global Nuclear Fuel for HCGS Cycle 21.
The purpose of this email is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The purpose of this email is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.  
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staffs detailed technical review by separate correspondence.
If you have any questions, please contact me.
Carleen Parker Project Manager -
Hope Creek and Salem Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission (301)415-1603 carleen.parker@nrc.gov 1


If you have any questions, please contact me.
2 Hearing Identifier:     NRR_PMDA Email Number:           2922 Mail Envelope Properties       (d01fe9697624452fad9a99e926b77b63)
Carleen Parker Project Manager -    Hope Creek and Salem Plant Licensing Branch I-2   Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission (301)415-1603 carleen.parker@nrc.gov 2
Hearing Identifier: NRR_PMDA Email Number: 2922   Mail Envelope Properties   (d01fe9697624452fad9a99e926b77b63)  


==Subject:==
==Subject:==
Acceptance Review - Hope Creek LAR To Modify TS 2.1, Safety Limits Sent Date:   6/27/2016 2:19:05 PM Received Date: 6/27/2016 2:19:00 PM From:   Parker, Carleen J Created By:   Carleen.Parker@nrc.gov Recipients:     "BROADDUS, Doug A" <Doug.Broaddus@nrc.gov>
Acceptance Review - Hope Creek LAR To Modify TS 2.1, Safety Limits Sent Date:               6/27/2016 2:19:05 PM Received Date:           6/27/2016 2:19:00 PM From:                   Parker, Carleen J Created By:             Carleen.Parker@nrc.gov Recipients:
Tracking Status: None "Forsaty, Fred M" <Fred.Forsaty@nrc.gov>
"BROADDUS, Doug A" <Doug.Broaddus@nrc.gov>
Tracking Status: None "Tilton, Caroline E" <Caroline.Tilton@nrc.gov> Tracking Status: None "OESTERLE, ERIC R" <Eric.Oesterle@nrc.gov> Tracking Status: None "Duke, Paul R. (Paul.Duke@pseg.com)" <Paul.Duke@pseg.com> Tracking Status: None "Thomas, Brian J. (Brian.Thomas@pseg.com)" <Brian.Thomas@pseg.com> Tracking Status: None Post Office:   HQPWMSMRS04.nrc.gov   Files     Size     Date & Time MESSAGE   2738     6/27/2016 2:19:00 PM Options Priority:     Standard   Return Notification:   No   Reply Requested:   No   Sensitivity:     Normal Expiration Date:     Recipients Received:      
Tracking Status: None "Forsaty, Fred M" <Fred.Forsaty@nrc.gov>
}}
Tracking Status: None "Tilton, Caroline E" <Caroline.Tilton@nrc.gov>
Tracking Status: None "OESTERLE, ERIC R" <Eric.Oesterle@nrc.gov>
Tracking Status: None "Duke, Paul R. (Paul.Duke@pseg.com)" <Paul.Duke@pseg.com>
Tracking Status: None "Thomas, Brian J. (Brian.Thomas@pseg.com)" <Brian.Thomas@pseg.com>
Tracking Status: None Post Office:             HQPWMSMRS04.nrc.gov Files                             Size                 Date & Time MESSAGE                           2738                 6/27/2016 2:19:00 PM Options Priority:                         Standard Return Notification:             No Reply Requested:                 No Sensitivity:                     Normal Expiration Date:
Recipients Received:}}

Latest revision as of 14:37, 4 December 2019

NRR E-mail Capture - Hope Creek Generating Station - Acceptance Review of LAR to Amend TSs to Modify Section 2.1, Safety Limits
ML16180A249
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 06/27/2016
From: Carleen Parker
Plant Licensing Branch 1
To: Duke P, Bernard Thomas
Public Service Enterprise Group
References
MF7793
Download: ML16180A249 (3)
v • d • e


Text

NRR-PMDAPEm Resource From: Parker, Carleen J Sent: Monday, June 27, 2016 2:19 PM To: Duke, Paul R. (Paul.Duke@pseg.com); Thomas, Brian J. (Brian.Thomas@pseg.com)

Cc: BROADDUS, Doug A; Forsaty, Fred M; Tilton, Caroline E; OESTERLE, ERIC R

Subject:

Acceptance Review - Hope Creek LAR To Modify TS 2.1, Safety Limits

Paul, By letter dated June 8, 2016, PSEG Nuclear LLC submitted a license amendment request to modify Technical Specification (TS) Section 2.1, Safety Limits, for Hope Creek Generating Station (HCGS). Specifically, this change would incorporate a revised Safety Limit Minimum Critical Power Ratio (SLMCPR) for single recirculation loop operation (SLO) due to the cycle specific analysis performed by Global Nuclear Fuel for HCGS Cycle 21.

The purpose of this email is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.

The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staffs detailed technical review by separate correspondence.

If you have any questions, please contact me.

Carleen Parker Project Manager -

Hope Creek and Salem Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission (301)415-1603 carleen.parker@nrc.gov 1

2 Hearing Identifier: NRR_PMDA Email Number: 2922 Mail Envelope Properties (d01fe9697624452fad9a99e926b77b63)

Subject:

Acceptance Review - Hope Creek LAR To Modify TS 2.1, Safety Limits Sent Date: 6/27/2016 2:19:05 PM Received Date: 6/27/2016 2:19:00 PM From: Parker, Carleen J Created By: Carleen.Parker@nrc.gov Recipients:

"BROADDUS, Doug A" <Doug.Broaddus@nrc.gov>

Tracking Status: None "Forsaty, Fred M" <Fred.Forsaty@nrc.gov>

Tracking Status: None "Tilton, Caroline E" <Caroline.Tilton@nrc.gov>

Tracking Status: None "OESTERLE, ERIC R" <Eric.Oesterle@nrc.gov>

Tracking Status: None "Duke, Paul R. (Paul.Duke@pseg.com)" <Paul.Duke@pseg.com>

Tracking Status: None "Thomas, Brian J. (Brian.Thomas@pseg.com)" <Brian.Thomas@pseg.com>

Tracking Status: None Post Office: HQPWMSMRS04.nrc.gov Files Size Date & Time MESSAGE 2738 6/27/2016 2:19:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

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