ML14042A043

Request for Additional Information Regarding Safety Limits to Resolve Pressure Regulator Fail-Open Transient License Amendment Request

ML14042A043
Person / Time
Site:	Pilgrim
Issue date:	02/18/2014
From:	Nadiyah Morgan Plant Licensing Branch 1
To:	Dent J Entergy Nuclear Operations
Morgan N
References
TAC MF1382
Download: ML14042A043 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 18, 2014 Mr. John Dent, Jr.

Site Vice President Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508

SUBJECT:

PILGRIM NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION REGARDING SAFETY LIMITS TO RESOLVE PRESSURE REGULATOR FAIL-OPEN TRANSIENT LICENSE AMENDMENT REQUEST (TAC NO. MF1382)

Dear Mr. Dent:

By letter dated April 5, 2013, Entergy Nuclear Operations, Inc. submitted a license amendment request (LAR) to reduce the reactor dome pressure from 785 pounds per square inch gauge (psig) to 685 psig in Technical Specification (TS) Safety Limits 2.1.1 and 2.1.2, and associated TS bases to resolve the potential to violate these limits during a pressure regulator failure open transient for Pilgrim Nuclear Power Station.

The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). Per your request, the NRC staff is requesting a response to the RAI within 60 days of February 4, 2014.

If you have any questions regarding this issue, please contact me at (301) 415-1016.

Sincerely, Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION REGARDING PRESSURE REGULATOR FAILURE-OPEN TRANSIENT LICENSE AMENDMENT REQUEST ENTERGY NUCLEAR GENERATION COMPANY ENTERGY NUCLEAR OPERATIONS, INC.

PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 By letter dated April 5, 2013, Entergy Nuclear Operations, Inc. submitted a proposed license amendment request (LAR) that would reduce the reactor dome pressure from 785 pound per square inch gauge (psig) to 685 psig in Technical Specifications (TSs) 2.1.1 and 2.1.2 Safety Limits, and associated TS bases for Pilgrim Nuclear Power Station.

In order to complete its review, the Nuclear Regulatory Commission staff requests further information on the following items:

1. Please justify that the data used for development and verification of the GEXL critical power correlation are still valid for the proposed lower pressure range to 685 psig.

2. Provide a detailed description of the analytic analysis for the pressure regulator fail open Anticipated Operational Occurrence transient to support the proposed LAR, including a sequence of events in relation to the set point for turbine control valves, safety relief valves, and main steam isolation valves to justify that the event causes the Critical Power Ratio to increase.

Enclosure

February 18, 2014 Mr. John Dent, Jr.

Site Vice President Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508

SUBJECT:

PILGRIM NUCLEAR POWER PLANT- REQUEST FOR ADDITIONAL INFORMATION REGARDING SAFETY LIMITS TO RESOLVE PRESSURE REGULATOR FAIL-OPEN TRANSIENT LICENSE AMENDMENT REQUEST (TAC NO. MF1382)

Dear Mr. Dent:

By letter dated April 5, 2013, Entergy Nuclear Operations, Inc. submitted a license amendment request (LAR) to reduce the reactor dome pressure from 785 pounds per square inch gauge (psig) to 685 psig in Technical Specification (TS) Safety Limits 2.1.1 and 2.1.2, and associated TS bases to resolve the potential to violate these limits during a pressure regulator failure open transient for Pilgrim Nuclear Power Station.

The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). Per your request, the NRC staff is requesting a response to the RAI within 60 days of February 4, 2014.

If you have any questions regarding this issue, please contact me at (301) 415-1016.

Sincerely, Ira/

Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC RidsNrrDoriLpl1-1 RidsNrrPMPilgrim LPL 1-1 R/F RidsNrrLAKGoldstein RidsAcrsAcnw&mMaiiCenter RidsNrrDoriDpr RidsRgn1 MaiiCenter T. Huang, NRR RidsOGCMaiiCenter RidsNrrDssSrxb ADAMS Accession No.: ML14042A043 *See dated memo **Via email OFFICE LPLI-1/PM LPLI-1/LA DSS/SRXB LPLI-1/BC NAME NMorgan KGoldstein CJackson BBeasley DATE 02/11/2014 02/11/2014** 1/30/2013* 02/18/2014 OFFICIAL RECORDS COPY