ML16271A205

Request for Additional Information Regarding Request to Delete Technical Specifications Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves

ML16271A205
Person / Time
Site:	Hope Creek
Issue date:	11/02/2016
From:	Carleen Parker Plant Licensing Branch 1
To:	Sena P Public Service Enterprise Group
Parker C, NRR/DORL/LPLI-II, 415-1603
References
CAC MF7709
Download: ML16271A205 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 2, 2016 Mr. Peter P. Sena, Ill President PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

HOPE CREEK GENERATING STATION- REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST TO DELETE TECHNICAL SPECIFICATION ACTION STATEMENT 3.4.2.1.b ASSOCIATED WITH STUCK OPEN SAFETY/RELIEF VALVES (CAC NO. MF7709)

Dear Mr. Sena:

By letter dated May 11, 2016 (Agencywide Documents Access and Management System Accession No. ML16132A374), PSEG Nuclear LLC (PSEG, the licensee) submitted a license amendment request (LAR) for Hope Creek Generating Station (Hope Creek). The LAR proposes to revise Hope Creek's Technical Specification (TS) requirements by deleting TS Action Statement 3.4.2.1.b concerning stuck open safety/relief valves.

The U.S. Nuclear Regulatory Commission staff has reviewed the licensee's application and, based upon this review, determined that additional information is needed to complete our review. On September 22, 2016, a draft of these questions was sent to Mr. Paul Duke of your staff to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. On October 18, 2016, a teleconference was held to clarify the questions. On October 24, 2016, Mr. Duke indicated that PSEG will submit a response within 45 days of the date of this letter.

P.Sena If you have any questions, please contact me at (301) 415-1603 or by e-mail at Carleen.Parker@nrc.gov.

Sincerely,

~ , \>.J-Carleen J arker, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosure:

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REQUEST FOR ADDITIONAL INFORMATION REQUEST TO DELETE TECHNICAL SPECIFICATION ACTION STATEMENT 3.4.2.1.b ASSOCIATED WITH STUCK OPEN SAFETY/RELIEF VALVES PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION DOCKET NO. 50-354 By letter dated May 11, 2016 (Agencywide Documents Access and Management System Accession No. ML16132A374), PSEG Nuclear LLC (the licensee) submitted a license amendment request (LAR) for Hope Creek Generating Station (Hope Creek). The LAR proposes to revise Hope Creek's Technical Specification (TS) requirements by deleting TS Action Statement 3.4.2.1.b concerning stuck open safety/relief valves. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the application and, based upon this review, determined that additional information requested below is needed to complete our review.

TS Action Statement 3.4.2.1.b currently states:

With one or more safety/relief valves stuck open, provided that suppression pool average water temperature is less than 110°F, close the stuck open safety relief valve(s); if unable to close the stuck open valve(s) within 2 minutes or if suppression pool average water temperature is 110°F or greater, place the reactor mode switch in the Shutdown position.

TS 3.6.2.1 Action b.2, also requires the reactor mode switch to be placed in the shutdown position when the suppression chamber average water temperate exceeds 110 degrees Fahrenheit (°F), while in Modes 1, 2, and 3. The licensee states that this action will remain unchanged and provides appropriate remedial action, permitted by TSs, until the limiting condition for operation can be met.

Title 1O of the Code of Federal Regulations (1 O CFR), Section 50.36, "Technical specifications,"

establishes the NRC's regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls.

Request for Additional Information In order for the staff to evaluate the licensee's proposed deletion of TS 3.4.2.1, Action b associated with the subject safety-relief valves (SRVs), the NRC staff requests the following additional information:

1. Since TS requirements are derived from a licensee's licensing basis, please (1) provide documentation/references related to Hope Creek's current licensing Enclosure

basis that requires inclusion of the '2 minute' SRV closure requirement in TS 3.4.2.1.b, and (2) indicate how long this requirement has been in the current TSs.

2. Please provide additional justification (such as operating experience, etc.) for the deletion of the proposed change.

In order for the staff to evaluate the licensee's statement that the requirement for the reactor mode switch to be placed in the shutdown position when the suppression chamber average water temperate exceeds 110 °F while in Modes 1, 2, and 3 will not be changed, the NRC staff requests the following additional information

3. Please clarify when TS 3.6.2.1 Action b.2 applies. Specifically, address the applicable thermal power.

4. For TS 3.6.2.1 Action b, for a stuck open SRV in Modes 1, 2, or 3, how is the requirement to place the mode switch in shutdown accomplished during the allowed time to restore temperature below the maximum average temperature of 95 °F?

P. Sena If you have any questions, please contact me at (301) 415-1603 or by e-mail at Carleen.Parker@nrc.gov.

Sincerely, IRA/

Carleen J. Parker, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosure:

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