ML031130480

Supplement to Request for Amendment to Technical Specifications Associated with Refueling Interlocks, Specifications 3/4.10.A and D

ML031130480
Person / Time
Site:	Pilgrim
Issue date:	04/16/2003
From:	Bellamy R Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2.03.047
Download: ML031130480 (4)

Text

Entergy Nuclear Operations, Inc Entergy Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 Mike Bellamy Site Vice President April 16, 2003 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

SUBJECT:

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 Supplement to Request for Amendment to Technical Specifications Associated With the Refueling Interlocks, Specifications 3/4.1 0.A and D

REFERENCES:

1. Entergy letter, Request for Amendment to Technical Specifications Associated With the Refueling Interlocks, Specifications 3/4.10.A and D, dated August 18, 2002

2. Entergy letter, Supplement to Request for Amendment to Technical Specifications Associated With the Refueling Interlocks, Specifications 3/4.10.A and D, dated March 26, 2003 LETTER NUMBER: 2.03.047

Dear Sir or Madam:

By the References 1 and 2 Entergy Nuclear Operations, Inc. (Entergy) proposed to amend the Pilgrim Station Operating License, DPR-35. Discussions with the NRC staff have identified additional information was necessary to facilitate review and approval of the requested changes.

The attached supplementary information does not impact Entergy's conclusion in Reference 1 that the proposed amendment does not involve a significant hazards consideration.

Please contact Mr. Bryan Ford, Licensing Manager, at (508) 830-8403, if you have any questions or require additional information.

I declare under penalty of perjury that the foregoing is true and correct. Executed on this 16th day of April 2003.

Sincerely, fb~t- ,i-Robert M. Bellamy 203047 Nrj \

Entergy Nuclear Operations, Inc. Letter Number: 2.03.047 Pilgrim Nuclear Power Station Page 2

Attachment:

1. Supplemental Information - 1 page cc: Mr. Travis Tate, Project Manager Office of Nuclear Reactor Regulation Mail Stop: 0-8B-1 U.S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville, MD 20852 U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Pilgrim Nuclear Power Station Mr. Steve McGrail, Director Mass. Emergency Management Agency 400 Worcester Road Framingham, MA 01702 Mr. Robert Walker Radiation Control Program Executive Offices of Health and Human Services 174 Portland Street, 5t Floor Boston, MA 02114 203047

ATTACHMENT 1 Supplemental Information 203047

Supplemental Information In a conference call on April 16, 2003 it was identified that the following information was needed to complete the review of the requested changes.

1. Currently, when maintenance is performed which could impact the operability of the refueling interlocks, the appropriate parts of the Technical Specification surveillance procedure (Pilgrim procedure 8.10.1) is performed prior to declaring the equipment operable. This practice of using the Technical Specification surveillance procedure to verify operability following maintenance that may have affected the ability of the equipment to perform its Technical Specification function is not being changed by the implementation of the proposed Technical Specification requirements.

2. The reactor mode switch discussed in Specification 3.1 0.A is monitored by the plant staff in several ways. First, when the source range monitors (SRMs) or intermediate range monitors (IRMs) are required to be operable the position of the reactor mode switch is monitored and recorded once per shift. Also, the reactor mode switch position is checked and documented as part of the control room shift turnover. In addition to these checks, inappropriate switch movement during a refueling outage would be annunciated to the control room staff by RPS actuations if the reactor mode switch was moved to the RUN or SHUTDOWN positions.

3. As discussed in the Technical Specification Bases, all control rods must be fully inserted when fuel is being loaded into the reactor core.

203047