ML021140484

Documentation of Conference Call Reactor Vessel Head Inspection Activities

ML021140484
Person / Time
Site:	Salem
Issue date:	05/01/2002
From:	Robert Fretz NRC/NRR/DLPM/LPD1
To:	Clifford J NRC/NRR/DLPM/LPD1
Fretz, R, NRR/DLPM, 415-1324
References
TAC MB4574
Download: ML021140484 (4)

Text

May 1, 2002 MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Robert J. Fretz, Project Manager, Section 2 /RA/

Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation

SUBJECT:

DOCUMENTATION OF CONFERENCE CALL REGARDING REACTOR VESSEL HEAD INSPECTION ACTIVITIES FOR SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 (TAC NO. MB4574)

On April 23, 2002, the Nuclear Regulatory Commission (NRC) staff had a conference call with PSEG Nuclear, LLC (PSEG or the licensee) to discuss the results of its reactor vessel head inspection for Unit No. 2 and potential impact of the Davis-Besse control rod drive mechanism (CRDM) inspection findings (see: NRC BULLETIN 2002-01, dated March 18, 2002.) During the April 23, 2002, call, PSEG addressed the following areas.

1. Inspection of the reactor vessel head: PSEG removed all insulation from the reactor pressure vessel (RPV) head, which provided full access, through the aid of an inspection mirror, to all penetration welds. The licensee performed a qualified visual inspection on 100% of the RPVs penetrations, and found no evidence of boric acid residue or any evidence of primary system leakage from these locations.

2. History of boric acid leaks: The licensee stated that there has been no evidence of boric acid leakage since 1987 when there was an occurrence of seal weld leakage that resulted in nine locations of pitting on the surface of the RPV head (reference Generic Letter 88-05).

In conclusion, the Unit No. 2 inspections did not identify any degradation of the reactor vessel head similar to that observed at Davis-Besse. Based on the preliminary findings from Davis-Besse, the inspections performed by the licensee, and the licensee's susceptibility to nozzle cracking, the NRC staff did not identify any issues that needed additional follow-up prior to plant restart. The staff will document its formal review after receiving the licensee'sBulletin 2002-01 response.

Docket No. 50-311

ML021140484 OFFICE PDI-2/PM PDI-2/LA PD1-2/SC NAME RFretz TLClark JClifford DATE 4/26/02 4/30/02 5/1/02