ML18100A321

Forwards Relief Request for ISI Program for Unit 2,per 10CFR50.55a(g) for Use During Second Ten Yr Interval,Basis for Relief & Alternate Exams Proposed

ML18100A321
Person / Time
Site:	Salem
Issue date:	04/13/1993
From:	Hagan J Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N93045, NUDOCS 9304210236
Download: ML18100A321 (3)

Text

• O PSIOCie Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department APR 13 1993 NLR-N93045 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

INSERVICE INSPECTION ACTIVITIES SEVENTH REFUELING OUTAGE SALEM GENERATING STATION UNIT NO. 2 DOCKET NO. 50-311 Public Service Electric & Gas Company (PSE&G) hereby submits the attached relief request to the Inservice Inspection Program for Salem Unit No. 2. This relief is submitted in accordance with lOCFR 50.55a(g) for use during the second ten year interval.

PSE&G requests that this relief be approved for use during the currently in progress seventh refueling outage. This outage is scheduled to end May 30, 1993. Similar relief requests to the Inservice Inspection Programs of Three Mile Island and Davis-Besse Nuclear Generating Stations have been approved.

Attachment 1 contains the relief request, basis for relief and alternate examinations proposed.

Should there be any questions with regard to this submittal, please do not hesitate to contact us. -------/ 9304210236 930413 PDR ADOCK 05000311 G PDR The L"\l\\'lT is i11 \\_1ur lunds. I

• 95-2168 REV 11.'91

• Document Control Desk NLR-N93045 C Mr. J. C. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector 2 Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief

• New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 Mr. Emanuel J*. Mossa New Jersey Department of Labor and Industry PO Box 1503, Labor and Industry Building Trenton, NJ 08625 APR 13 1993

• NLR-N93045 ATTACHMENT 1 Relief Request RR-A7 COMPONENT DESCRIPTION Insulated Pressure Retaining Bolted Connections ASME CODE CLASS ASME Section XI Class 1 ASME EXAMINATION REQUIREMENTS In accordance with ASME Section XI, 1986 Edition, Subsection IAW 5242(a); for borated for the purpose of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for visual examinations VT-2. BASIS FOR RELIEF It is the position of PSE&G that it is impractical to conduct VT-2 examinations on Class 1 bolted connections with insulation removed and the system at operating pressure and temperature because: In accordance with Salem Unit 2 Technical Specifications, 3.4.10.1 does not allow pressurization of Reactor Coolant System to nominal operating pressure without heatup. Re-installation of insulation requires exposing personnel to the safety hazard of elevated temperature (550°F) and pressure (2235 psig), which includes a heat stress environment.

The activities will be conducted at the end of the outage and have the effect of extending the outage by a minimum of two days. Boric acid leakage, leaves boric acid crystal residue when it evaporates, therefore, it is not necessary to examine for boric acid leakage in conjunction with a pressure test. ALTERNATE EXAMINATIONS During refueling, outages, when in examination of bolted connections residue with insulation removed. accordance with ASME Section XI. cold shutdown, conduct a visual for evidence of boric acid Corrective action will be in ----I