ML031260647

10 CFR 50.46(a)(3)(ii) Annual Report

ML031260647
Person / Time
Site:	Pilgrim
Issue date:	04/29/2003
From:	Riggs W Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2.03.065
Download: ML031260647 (2)

Text

Entergy Nuclear Operations, Inc.

Entergy Pilgnm Station 600 Rocky Hill Road Plymouth, MA 02360 William J. Riggs Director, Nuclear Assessment April 29, 2003 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Docket No.: 50-293 License No.: DPR-35 10 CFR 50.46(a)(3)(ii) Annual Report

REFERENCES:

1. Entergy letter to U.S. NRC, dated March 19, 2002, Pilgrim 10 CFR 50.46(a)(3)(ii) Report for 2001

2. Entergy letter to U.S. NRC, dated July 10, 2002, 10 CFR 50.46(a)(3)(ii) Report

3. GE Nuclear Energy Report NEDC-31852P, "Pilgrim Nuclear Power Station SAFER/GESTR-LOCA Analysis," Rev. 2 LETTER NUMBER: 2.03.065

Dear Sir or Madam:

This letter submits the annual report required by 10 CFR 50.46(a)(3)(ii).

For the year ending 2001, Reference 1 reported two error notifications received by Pilgrim Station concerning the ECCS-LOCA analyses. The report included the licensing basis peak clad temperature (PCT) for the two fuel types used in cycle 14 operation: GE1 1 (9x9 design) and GE14 fuel (10x1o design). After Reference 1 was submitted, an error that impacted the Pilgrim Station licensing basis PCT for GE1 1 fuel was identified and reported in Reference 2.

After the submittal of Reference 2, two errors and one change in the accepted evaluation model were identified by General Electric/Global Nuclear Fuel in three 10 CFR 50.46 notification letters, each dated August 26, 2002. The errors and change had no impact on the Pilgrim Station licensing basis PCT for GE1 1 or GE14 fuel. No other notifications were received for the remainder of 2002 and fuel cycle 14 that ended with the 2003 refueling outage.

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I-, 1 Entergy Nuclear Operations, Inc. Letter Number: 2.03.065 Pilgrim Nuclear Power Station Page 2 Although the error reported in Reference 2 did not affect compliance with 10 CFR 50.46(b) requirements, a reanalysis of the Pilgrim Station LOCA analysis was conducted as part of the core reload for the 2003 refueling outage that began in April 2003. Beginning with startup from the 2003 refueling outage for cycle 15 operation, the reanalysis (Reference 3) established a new licensing basis PCT for GE1 1 fuel (2120 degrees F) and GE14 fuel (2130 degrees F).

Please contact Bryan Ford, (508) 830-8403, if there are any questions regarding this subject.

Sincerely, 7/

VW.J. Riggs DWE/dd cc: Mr. Travis Tate, Project Manager Mr. Hubert J. Miller Office of Nuclear Reactor Regulation Regional Administrator, Region 1 Mail Stop: 0-8B-1 U.S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission 475 Allendale Road 1 White Flint North King of Prussia, PA 19406 11555 Rockville Pike Rockville, MD 20852 Senior Resident Inspector Pilgrim Nuclear Power Station 203065