ML17114A312

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NRR E-mail Capture - Draft Non-Accept with Opportunity to Supplement: Hope Creek P-T Limit Curve LAR (MF9502)
ML17114A312
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 04/24/2017
From: Carleen Parker
Plant Licensing Branch 1
To: Duke P, Bernard Thomas
Public Service Enterprise Group
References
MF9502
Download: ML17114A312 (4)


Text

NRR-PMDAPEm Resource From: Parker, Carleen Sent: Monday, April 24, 2017 1:40 PM To: Duke, Paul R.; Thomas, Brian J. (Brian.Thomas@pseg.com)

Cc: Parks, Benjamin; Danna, James; Klett, Audrey; Grover, Ravinder; Peng, Shie-Jeng; Young, Austin; Sydnor, Christopher

Subject:

DRAFT Non-Accept with Opportunity to Supplement: Hope Creek P-T Limit Curve LAR (MF9502)

Attachments: DRAFT NonAccept with Opportunity to Supplement Hope Creek PTLR.pdf Good Afternoon, By letter dated March 27, 2017, PSEG Nuclear LLC (PSEG) submitted a license amendment request for Hope Creek Generating Station (Hope Creek). The proposed amendment would amend the Hope Creek technical specifications (TSs) to revise and relocate the Pressure-Temperature (PT) Limit Curves to a licensee-controlled Pressure and Temperature Limits Report (PTLR). The request was submitted in accordance with guidance provided in U.S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits.

The purpose of this letter is to provide the DRAFT 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 preliminarily concluded that the information delineated in the DRAFT request attached to this email is necessary to enable the staff to 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.

This DRAFT is being sent to in accordance with LIC-109, Acceptance Review Procedures, to facilitate a conference call with the NRC staff. It is the staffs expectation that the conference call will occur as soon as possible, but no later than 5 days from the date of this email.

Please contact me with any questions, 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

Hearing Identifier: NRR_PMDA Email Number: 3465 Mail Envelope Properties (Carleen.Parker@nrc.gov20170424133900)

Subject:

DRAFT Non-Accept with Opportunity to Supplement: Hope Creek P-T Limit Curve LAR (MF9502)

Sent Date: 4/24/2017 1:39:51 PM Received Date: 4/24/2017 1:39:00 PM From: Parker, Carleen Created By: Carleen.Parker@nrc.gov Recipients:

"Parks, Benjamin" <Benjamin.Parks@nrc.gov>

Tracking Status: None "Danna, James" <James.Danna@nrc.gov>

Tracking Status: None "Klett, Audrey" <Audrey.Klett@nrc.gov>

Tracking Status: None "Grover, Ravinder" <Ravinder.Grover@nrc.gov>

Tracking Status: None "Peng, Shie-Jeng" <Shie-Jeng.Peng@nrc.gov>

Tracking Status: None "Young, Austin" <Austin.Young@nrc.gov>

Tracking Status: None "Sydnor, Christopher" <Christopher.Sydnor@nrc.gov>

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

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

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 2236 4/24/2017 1:39:00 PM DRAFT NonAccept with Opportunity to Supplement Hope Creek PTLR.pdf 70699 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

DRAFT SUPPLEMENTAL INFORMATION NEEDED AMENDMENT REQUEST REGARDING REVISION AND RELOCATION OF THE PRESSURE-TEMPERATURE LIMIT CURVES TO A PRESSURE AND TEMPERATURE LIMITS REPORT PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By letter dated March 27, 2017, 1 PSEG Nuclear LLC (PSEG) submitted a license amendment request for Hope Creek Generating Station (Hope Creek). The proposed amendment would amend the Hope Creek technical specifications (TSs) to revise and relocate the Pressure-Temperature (PT) Limit Curves to a licensee-controlled Pressure and Temperature Limits Report (PTLR). The request was submitted in accordance with guidance provided in U.S.

Nuclear Regulatory Commission (NRC) Generic Letter (GL) 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits. 2 In order to implement a PTLR, requesting licensees are required, among other things, to propose to (1) use NRC-approved methodology to develop the PTLR, (2) describe how the neutron fluence is calculated, and (3) provide the values of neutron fluences that are used in the adjusted reference temperature calculation.

PSEG proposes to implement Revision 1-A to Licensing Topical Report (LTR) SIR-05-044, Pressure-Temperature Limits Report Methodology for Boiling Water Reactors. 3 Regarding reactor vessel neutron fluence, Table 1-1 of the LTR states, Fluence methods and results must comply with RG 1.190 and have NRC approval for use with this LTR. In the March 27, 2017, license amendment request, PSEG indicates that the fluence calculations were performed using the RAMA Fluence Methodology. The description provided is not sufficiently detailed to permit the NRC staff to review the fluence calculations and make a conclusion regarding their adherence to RG 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, guidance.

In addition, the NRC reviewed the Hope Creek licensing basis and determined that the presently approved PT Curves are based on General Electric fluence methods, as reviewed and 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML17086A363 2 ADAMS Accession No. ML031110004 3 ADAMS Accession No. ML13277A557

approved by the NRC staff in Hope Creek license amendment No. 157. 4 Therefore, the use of the RAMA Fluence Methodology to develop PT Curves is a change in methodology from the current licensing basis at Hope Creek. As such a detailed review of the RAMA Fluence Methodology for Hope Creek has not been performed by the NRC staff.

As stated in Office Instruction LIC-109, Acceptance Review Procedures, 5 it is the policy of the Office of Nuclear Reactor Regulation (NRR) to review an application to amend a license for completeness and acceptability for docketing. The quality of a requested licensing action (RLAs) has a significant impact on the amount of NRC staff's resources expended in the review process. When an application lacks critical information necessary for the NRC staff to complete its review, an excessive amount of NRC staff time is spent gathering this information. As a result, time spent on RLAs that are unacceptable for review results in longer review periods for the RLA and adversely impacts the resources and schedules of other acceptable RLAs. In accordance with LIC-109, and in conjunction with GL 96-03 and RG 1.190, the NRC staff has completed the acceptance review of the license amendment request, and has concluded that the description of the fluence calculations provided do not include sufficient information to enable the NRC staff to make an independent assessment regarding their adherence to RG 1.190 guidance. to the March 27, 2017, license amendment request provides a reference (Reference 4) to the fluence calculation supporting the PTLR, as follows:

TransWare Report No. EPR-HC1-001-R-002, Revision 0, Hope Creek Nuclear Generating Station Unit 1 Reactor Pressure Vessel Fluence Evaluation at End of Cycle 19 with Projections to 56 EFPY, March 30, 2016, SI File No. 1600507.201.

Provide this reference for NRC staff review.

4 ADAMS Accession No. ML043080359 5 ADAMS Accession No. ML16144A521