ML16102A152
| ML16102A152 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/12/2016 |
| From: | April Pulvirenti Plant Licensing Branch IV |
| To: | Entergy Operations |
| Pulvirenti A | |
| References | |
| CAC MF6366 | |
| Download: ML16102A152 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Site Vice President, Operations Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 April 12, 2016
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE RISK-INFORMED SURVEILLANCE REQUIREMENTS LICENSE AMENDMENT REQUEST (CAC NO. MF6366)
Dear Sir or Madam:
By letter dated June 17, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15170A121), as supplemented by letter dated March 3, 2016 (ADAMS Accession No. ML16063A532), Entergy Operations, Inc. (Entergy or the licensee),
requested an amendment to the technical specifications (TSs) for Waterford Steam Electric Station Unit 3 (Waterford 3). The proposed amendment will modify Waterford 3 TSs by relocating specific surveillance frequencies to a licensee-controlled program with the implementation of Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specification Initiative 5B, Risk-Informed Method for Control of Surveillance Frequencies."
The U.S. Nuclear Regulatory Commission (NRC) staff issued a request for additional information (RAI) by letter dated January 22, 2016 (ADAMS Accession No. ML16015A294), and the licensee provided a response to the RAI in letter dated March 3, 2016. The NRC staff has reviewed the information provided by the licensee and determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with Ms. Leia Milster and others of your staff on April 7, 2016, it was agreed that you would provide a response within 30 days from the date of this letter. Please provide the additional information requested in the enclosure within 30 days of the date of this letter.
If you have any questions, please contact me at 301-415-1390 or via e-mail at April.Pulvirenti@nrc.gov.
Docket No. 50-382
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, April L. Pulvirenti, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING THE RISK-INFORMED SURVEILLANCE ENTERGY OPERATIONS. INC.
WATERFORD STEAM ELECTRIC STATION. UNIT 3 DOCKET NO. 50-382 By letter dated June 17, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15170A121), as supplemented by letter dated March 3, 2016 (ADAMS Accession No. ML16063A532), Entergy Operations, Inc. (Entergy or the licensee),
requested an amendment to the technical specifications (TSs) for Waterford Steam Electric Station Unit 3 (Waterford 3). The proposed amendment will modify Waterford 3 TSs by relocating specific surveillance frequencies to a licensee-controlled program with the implementation of Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specification Initiative 58, Risk-Informed Method for Control of Surveillance Frequencies."
The U.S. Nuclear Regulatory Commission staff (NRC) issued a request for additional information (RAI) by letter dated January 22, 2016 (ADAMS Accession No. ML16015A294), and the licensee provided a response to the RAI by letter dated March 3, 2016. The NRC staff has reviewed the information provided by the licensee and determined that the following additional information is required to complete the review:
RAl-2.01 In its response to RAl-2 by letter dated March 3, 2016, the licensee stated that Fact and Observation (F&O) IE-C6-01 was addressed during a probabilistic risk assessment (PRA) model update and a disposition was provided in Table U-1 of the supplement to Waterford 3 submittal for adopting National Fire Protection Association (NFPA) Standard 805 (ADAMS Accession No. ML13365A325). The response further stated that the current fault tree logic is more thorough than past models and "[t]he current IE fault trees include items in redundant paths (including valves and breakers)."
The response to RAl-2 and the disposition in Table U-1 of the supplement to Waterford 3 NFPA 805 submittal do not indicate whether modelling of other excluded failure modes cited in F&O IE-C6-01, such as "sensors and transmitters and flow diversion paths," were incorporated in the updated PRA model. The NRC staff notes that flow diversion pathways can potentially have impact on initiating event fault tree results. Explain whether the other failure modes cited in the F&O have been addressed in the initiating event fault trees developed for the internal events PRA (IEPRA) and, if they have not been included, justify that this exclusion will not contribute to underestimation of IEPRA risk and impact Surveillance Test Interval evaluations.
Enclosure
- by memo dated OFFICE NRR/DORL/LPL4-2/PM NRR/DORL/LPL4-2/LA NRR/DRA/APLA/BC*
NAME APulvirenti PBlechman SRosenberg (CFong for)
DATE 04/12/16 04/12/16 03/31/16 OFFICE NRR/DORL/LPL4-2/BC NRR/DORL/LPL4-2/PM NAME MKhanna (SKoenick for) APulvirenti DATE 04/12/16 04/12/16