ML16305A069

NRR E-mail Capture - Columbia Generating Station - Request for Additional Information Regarding Reactor Steam Dome Pressure License Amendment Request

ML16305A069
Person / Time
Site:	Columbia
Issue date:	10/31/2016
From:	Watford M Plant Licensing Branch IV
To:	Ronnie Garcia Energy Northwest
References
MF8116
Download: ML16305A069 (3)

Text

NRR-PMDAPEm Resource From: Watford, Margaret Sent: Monday, October 31, 2016 8:34 AM To: Garcia, Richard M.

Cc: Klos, John

Subject:

Request for Additional Information Regarding Reactor Steam Dome Pressure License Amendment Request Attachments: Request for Additional Information Re Columbia Reactor Steam Dome Pressure License Amendment Request (MF8116).pdf Good afternoon Mr. Garcia, By letter dated July 12, 2016 (Agencywide Document and Access Management System (ADAMS) Accession No. ML16194A515), Energy Northwest (the licensee) submitted a license amendment request (LAR) for Columbia Generating Station (Columbia). The proposed amendment would reduce the reactor steam dome pressure stated in Technical Specification (TS) 2.1.1 for the reactor core safety limits (SLs). The proposed change addresses a calculation "defect" under Title 10 of the Code of Federal Regulations (10 CFR), Part 21, "Reporting of Defects and Noncompliance,"

concerning the potential to violate the safety limits during a pressure regulator failure maximum demand open (PRFO) transient, reported by General Electric Energy-Nuclear (GE)

Based on the review of the LAR, the U.S. Nuclear Regulatory Commission (NRC) has determined that additional information is required. Please see the formal request for additional information (RAI) in the attached document and submit your response to the RAI by November 30, 2016.

I will be your point of contact on this LAR but please include John Klos in your responses. Feel free to call or email me if you have any questions.

Thank you, Maggie Watford Project Manager, Plant Licensing Branch IV-I Division of Operating Reactor Licensing U.S. Nuclear Regulatory Commission Phone: 301-415-1233 Email: Margaret.Watford@nrc.gov 1

Hearing Identifier: NRR_PMDA Email Number: 3133 Mail Envelope Properties (Margaret.Watford@nrc.gov20161031083300)

Subject:

Request for Additional Information Regarding Reactor Steam Dome Pressure License Amendment Request Sent Date: 10/31/2016 8:33:46 AM Received Date: 10/31/2016 8:33:00 AM From: Watford, Margaret Created By: Margaret.Watford@nrc.gov Recipients:

"Klos, John" <John.Klos@nrc.gov>

Tracking Status: None "Garcia, Richard M." <rmgarcia@energy-northwest.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 1410 10/31/2016 8:33:00 AM Request for Additional Information Re Columbia Reactor Steam Dome Pressure License Amendment Request (MF8116).pdf 78290 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

REQUEST FOR ADDITIONAL INFORMATION (RAI)

REDUCE THE REACTOR STEAM DOME PRESSURE SPECIFIED IN THE TECHNICAL SPECIFICATION 2.1.1, REACTOR CORE SLs COLUMBIA GENERATING STATION (CAC NO. MF8116)

REACTOR SYSTEMS BRANCH (SRXB)

By letter dated July 12, 2016 (Agencywide Document and Access Management System (ADAMS) Accession No. ML16194A515), Energy Northwest (the licensee) submitted a license amendment request (LAR) for Columbia Generating Station (Columbia). The proposed amendment would reduce the reactor steam dome pressure stated in Technical Specification (TS) 2.1.1 for the reactor core safety limits (SLs). The proposed change addresses a calculation defect under Title 10 of the Code of Federal Regulations (10 CFR), Part 21, Reporting of Defects and Noncompliance, concerning the potential to violate the safety limits during a pressure regulator failure maximum demand open (PRFO) transient, reported by General Electric Energy-Nuclear (GE)

The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in the submittal and would like to discuss the following issues to clarify the submittal.

RAI - 1 In Section 1, Summary, of Attachment 1 to the application dated July 12, 2016, the license stated:

GE fuel utilizes the GEXL14 and GEXL17 critical power correlations, with an approved pressure range from 700 to 1400 psia [pounds per square inch absolute] (685 to 1385 psig [pounds per square inch gauge]). Columbia has determined that changing the pressure limits in TS SLs 2.1.1.1 and 2.1.1.2 to 685 psig as permitted by NEDC-32851 P-A, Rev. 5, "GEXL14 Correlation for GE14 Fuel", (Reference 2) and NEDC-33292P, Rev. 3, "GEXL17 Correlation for GNF2 Fuel", (Reference 3), provides greater margin for the PRFO transient, such that the dome pressure will remain above the revised TS 2.1 safety limits.

When converting 700 psia to psig, the lower bound pressure for the GEXL17 and GEXL14 correlations is approximately (700 - 14.7 =) 685.3 psig. As such, the 685 psig value specified in the proposed TS change is slightly outside the pressure range in which the GEXL17 and GEXL14 correlations are valid for GNF2 and GE14 fuel. Please provide further justification for the proposed 685 psig value or propose a revised pressure value for this TS change that is supported by the GEXL17 and GEXL14 correlations (e.g., 700 psia or 686 psig).