ML16277A677

From kanterella
Jump to navigation Jump to search

Summary of Public Meeting with Entergy Nuclear Operations, Inc. Regarding the Proposed Closure Plant for Generic Safety Issue 191, Assessment of Debris Accumulation on Pressurized Water Reactor (PWR) Sump Performance
ML16277A677
Person / Time
Site: Palisades Entergy icon.png
Issue date: 10/11/2016
From: Jennivine Rankin
Plant Licensing Branch III
To:
Entergy Operations
Rankin J
References
CAC MF8386
Download: ML16277A677 (4)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Ocotber 11, 2016 LICENSEES: Entergy Nuclear Operations, Inc.

FACILITIES: Palisades Nuclear Plant

SUBJECT:

SUMMARY

OF SEPTEMBER 28, 2016, PUBLIC MEETING WITH ENTERGY NUCLEAR OPERATIONS, INC. REGARDING THE PROPOSED CLOSURE PLAN FOR GENERIC SAFETY ISSUE 191, "ASSESSMENT OF DEBRIS ACCUMULATION ON PRESSURIZED WATER REACTOR (PWR) SUMP PERFORMANCE" (CAC NO. MF8386)

On September 28, 2016, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives of Entergy Nuclear Operations, Inc.

(ENO) and their contractor at NRC Headquarters, Rockville, Maryland. The purpose of the meeting was to discuss the licensee's closure plan for generic safety issue (GSI) 191, "Assessment of Debris Accumulation on Pressurized Water Reactor (PWR) Sump Performance," at Palisades Nuclear Plant (PNP). The meeting notice and agenda are located in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML16251A086.

The licensee presented information on the background, basis, and content of the proposed application, which is available at ADAMS Accession No. ML16277A621.

The licensee plans to use the "Risk over Deterministic" (RoverD) closure method and highlighted the different process steps required to execute this closure method. This included the use of the CASA Grande software, thermal hydraulics analysis, probabilistic risk assessment, testing, and licensing actions. The NRC staff queried the licensee about several aspects of the proposed closure plan and provided feedback. The staff was most interested in the methodology that would be used to identify limiting debris loads because of the variety of materials and the large amounts of fiber and calcium silicate in the PNP containment. The NRC staff had a number of questions related to the test methodology proposed by the licensee to estimate chemical effects. The presentation indicated that initial analysis from corrosion testing at Ohio State University predicted about 25 percent of the amount of chemical precipitates that currently approved methods predict. The staff stated that any plant-specific aluminum corrosion results need to be evaluated in the context of the available knowledge base, including WCAP-16530, "Evaluation of Post-Accident Chemical Effects in Containment Sump Fluids to Support GSl-191," WCAP-17788, "Comprehensive Analysis and Test Program for GSl-191 Closure (PA-SEE-1090)," Argonne National Lab results, and other plant specific tests. The staff acknowledged the importance of retaining some conservatism in the overall chemical effects evaluation to account for uncertainties. The licensee intends to request future pre-application meetings with the NRC staff to discuss chemical corrosion findings, strainer testing methodology, and the content of the associated license amendment request. The licensee invited the NRC staff to visit the corrosion test facility at Ohio State University. Ultimately, the licensee plans to submit a license amendment request in the fourth quarter of 2018. No regulatory decisions were made at the meeting.

The public was invited to listen to the meeting and was given an opportunity to communicate with the NRC after the business portion, but before the meeting was adjourned. Members of the public participated by telephone. All comments and questions were addressed before adjourning the meeting. No public meeting feedback forms were received.

A list of meeting attendees is enclosed.

Please direct any inquiries to me at 301-415-1530, or Jennivine.Rankin@nrc.gov.

~\'VL-L~~

IsJnnivine K. Rankin, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-255

Enclosure:

List of Attendees cc w/encl: Distribution via Listserv

LIST OF ATTENDEES SEPTEMBER 28, 2016, PUBLIC MEETING WITH ENTERGY NUCLEAR OPERATIONS, INC.

GENERIC SAFETY ISSUE 191 CLOSURE PLAN FOR PALISADES NUCLEAR PLANT Licensee Attendees*

A. Hazelhoff, Entergy Nuclear Operations, Inc. (ENO)

0. Gustafson, ENO S. Mongeau, ENO B. Letellier, Alion Science J. Leavitt, Alion Science U.S. Nuclear Regulatory Commission P. Klein, NRR/DE/ESGB M. Yoder, NRR/DE/ESGB S. Smith. NRR/DSS/SSIB V. Cusumano, NRR/DSS/SSIB A. Russell*, NRR/DSS/SSIB C. Pfefferkorn, NRR/DRA/APLA J. Peralta, NRR/DE/ESGB G. Makar, NRO/DEIA/MCB J. Rankin, NRR/DORL/LPL3-1 Public E. Fulhage*

M. Keegan*

T. Sande*

E. Federline*

M. Lewis*

J. Hawley*

J. Tezak*

  • by audiobridge. Several other licensee staff from ENO also participated by audiobridge.

Enclosure

Meeting Notice ML16251A086 Summary ML16277A677 Handouts ML16277A621 OFFICE NRR/DORL/LPL3-1 /PM NRR/DORL/LPL3-1 /LA NRR/DE/ESGB/BC NAME JRankin SRohrer JPeralta DATE 10/04/16 10/04/16 10/04/16 OFFICE NRR/DORL/LPL3-1/BC NRR/DORL/LPL3-1 /PM NAME DWrona JRankin DATE 10/11/16 10/11/16