ML120860147

Request for Additional Information - Pilgrim Nuclear Power Station Revision to Condensate Storage Tank Low Level Trip Setpoint

ML120860147
Person / Time
Site:	Pilgrim
Issue date:	03/26/2012
From:	Richard Guzman Plant Licensing Branch 1
To:	Entergy Nuclear Operations
Guzman R, NRR/DORL 415-1030
References
TAC ME7545
Download: ML120860147 (3)

Text

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

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - PILGRIM NUCLEAR POWER STATION RE: REVISION TO CONDENSATE STORAGE TANK LOW LEVEL TRIP SETPOINT (TAC NO. ME7545)

Dear Sir or Madam:

By letter dated October 28,2011 (Agencywide Documents Access Management System (ADAMS) Accession No. ML11312A051), Entergy Nuclear Operations, Inc. (Entergy), the licensee for Pilgrim Nuclear Power Station, submitted a license amendment request (LAR) to revise its Technical Specifications to increase the condensate storage tank low level setpoint for the interlock to the high-pressure coolant injection pump suction valves.

The Nuclear Regulatory Commission (NRC) staff is reviewing the information provided in that letter and has determined that additional information is needed to support its review. Enclosed is the NRC staffs request for additional information (RAI). The RAI was discussed with your staff on March 22, 2011, and it was agreed that your response would be provided within 45 days of the date of this letter.

Sincerely, Richard V. uzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293

Enclosure:

As stated cc w/encl: Distribution via Listserv

SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION (RA!)

ENTERGY NUCLEAR OPERATIONS. INC.

PILGRIM NUCLEAR POWER STATION REVISION TO TECHNICAL SPECIFICATION FOR THE CONDENSATE STORAGE TANK LOW LEVEL TRIP SETPOINT DOCKET NO. 50-293 The Nuclear Regulatory Commission (NRC) staff is reviewing the Entergy Nuclear Operations, Inc. (Entergy or the licensee) submittal dated October 28, 2011, and has determined that additional information is necessary to complete its review. Please provide a response which addresses the following request for additional information (RAI): "Setpoint Calculation for PS-2390A&B, Condensate Tank Low Level Transfer" of the submitted license amendment request lists the As-Left Tolerance (ALT) value, but does not provide the basis for AL T determination. The NRC staff notes that the proposed revised setpoint is one of the Limiting Safety System Settings (LSSS) listed for the NUREG-1433, Boiling Water Reactor/4 Plants in the Technical Specification Task Force (TSTF)-493, Revision 4, which is described in the Federal Register, Notice of Availability of the Models for Plant Specific Adoption of Technical Specifications Task Force Traveler TSTF-493, Revision 4, "Clarify Application of Setpoint Methodology for LSSS Functions," Vol. 75, No. 90 I Tuesday, May 11, 2010 (75 FR 26294).

1. Describe whether and how you plan to apply the TSTF-493, Revision 4 for this setpoint.

If you do not plan to adopt the TSTF-493, then explain how you will ensure compliance with 10 CFR 50.36 and Regulatory Issue Summary (RIS) 2006-17 by addressing items (2) and (3), below.

2.. As-Found Setpoint Evaluation: Describe how surveillance test results and associated TS limits are used to establish operability of the safety system. Show that this evaluation is consistent with the assumptions and results of the setpoint calculation methodology.

Discuss the plant corrective action processes (including plant procedures) for restoring channels to operable status when channels are determined to be "inoperable" or "operable but degraded." If the criteria for determining operability of the instrument being tested are located in a document other than the TS (e.g., plant test procedure) explain how the requirements of 10 CFR 50.36 and RIS 2006-17 are met.

3. As-Left Setpoint Control: Describe the controls employed to ensure that the instrument setpoint is, upon completion of surveillance testing, consistent with the assumptions of the associated analyses. If the controls are located in a document other than the TS (e.g.,

plant test procedure) explain how the requirements of 10 CFR 50.36 and RIS 2006-17 are met.

Enclosure

March 26, 2012 Site Vice President Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508 SUB..IECT: REQUEST FOR ADDITIONAL INFORMATION - PILGRIM NUCLEAR POWER STATION RE: REVISION TO CONDENSATE STORAGE TANK LOW LEVEL TRIP SETPOINT (TAC NO. ME7545)

Dear Sir or Madam:

By letter dated October 28,2011 (Agencywide Documents Access Management System (ADAMS) Accession No. ML11312A051), Entergy Nuclear Operations, Inc. (Entergy), the licensee for Pilgrim Nuclear Power Station, submitted a license amendment request (LAR) to revise its Technical Specifications to increase the condensate storage tank low level setpoint for the interlock to the high-pressure coolant injection pump suction valves.

The Nuclear Regulatory Commission (NRC) staff is reviewing the information provided in that letter and has determined that additional information is needed to support its review. Enclosed is the NRC staffs request for additional information (RAI). The RAI was discussed with your staff on March 22, 2011, and it was agreed that your response would be provided within 45 days of the date of this letter.

Sincerely, Ira!

Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293

Enclosure:

As stated cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC RidsNrrPMPilgrim RidsNrrLASLittie RidsOGCRp LPLI-1 R/F RidsRgn1 MailCenter RidsNrrDeEicb CPong, NRR ADAMS Accession No.: memo. No substantial chan es made. NRR-088

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