ML15275A357

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Shearon Harris, Unit 1-Acceptance of Requested Licensing Action for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
ML15275A357
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 10/08/2015
From: Barillas M C
Plant Licensing Branch II
To: Waldrep B C
Progress Energy Carolinas
Barillas M C, NRR/DORL, 415-2760
References
TAC MF6583
Download: ML15275A357 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Benjamin C. Waldrep Site Vice President Shearon Harris Nuclear Power Plant 5413 Shearon Harris Rd. M/C HNP01 New Hill, NC 27562-0165 October 8, 2015

SUBJECT:

SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION FOR TECHNICAL SPECIFICATION CHANGE REGARDING RISK-INFORMED JUSTIFICATION FOR THE RELOCATION OF SPECIFIC SURVEILLANCE FREQUENCY REQUIREMENTS TO A LICENSEE CONTROLLED PROGRAM (TAC NO. MF6583)

Dear Mr. Waldrep:

By letter dated August 18, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15236A265),

Duke Energy Progress, Inc. (Duke Energy) requested an amendment to the Technical Specifications (TSs) of Renewed Facility Operating License No. NPF-63 for Shearon Harris Nuclear Power Plant, Unit 1. The proposed amendment would revise the TSs by relocating specific surveillance frequencies to a licensee-controlled program with the adoption of Technical Specification Task Force Traveler-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control -RITSTF [Risk-Informed Technical Specification Task Force] Initiative Sb." Additionally, the change would add a new program, the Surveillance Frequency Control Program, to TS Section 6, "Administrative Controls."

On September 16, 2015, the U.S. Nuclear Regulatory Commission (NRC) staff held a conference call with members of your staff to discuss insufficiencies identified during the acceptance review of the amendment request.

Specifically, the amendment did not adequately provide the facts and observations (F&Os) from the peer reviews and gap assessments of the internal events probabilistic risk assessment (PRA) which are open, not met, or met at capability category I, nor explain how the F&Os were dispositioned for this application.

The NRC staff requested that Duke Energy provide an overview of the changes in the internal events PRA that occurred after the 2007 peer review and clarify whether any of these changes qualify as a PRA upgrade that would require a focused scope peer review. By letter dated September 18, 2015 (ADAMS Accession No. ML 15259A435),

you were informed of the above insufficiencies and informed that the license amendment request would need to be supplemented by September 30, 2015. By letter dated September 29, 2015 (ADAMS Accession No. ML 15272A443),

supplemental information was submitted by Duke Energy. The NRC staff has reviewed the supplemental information and concluded that it does provide technical information in sufficient detail to enable the staff to (1) perform its detailed technical review, and (2) make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of the public health and safety and environment.

B. Waldrep 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.

If you have any questions, please contact me at (301) 415-2760 or Martha.Barillas@nrc.gov.

Docket No. 50-400 cc w/enclosure:

Distribution via Listserv Sincerely, Martha C. Barillas, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation B. Waldrep 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.

If you have any questions, please contact me at (301) 415-2760 or Martha.Barillas@nrc.gov.

Docket No. 50-400 Sincerely,

/RA/ Martha C. Barillas, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc w/enclosure:

Distribution via Listserv DISTRIBUTION:

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