ML14183A922
| ML14183A922 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 07/15/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | Young D CAROLINA POWER & LIGHT CO. |
| Shared Package | |
| ML14183A923 | List: |
| References | |
| TAC-MA4635, NUDOCS 9907280090 | |
| Download: ML14183A922 (2) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
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o July 15, 1999 Mr. D. E. Young, Vice President Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2 3581 West Entrance Road Hartsville, South Carolina 29550
SUBJECT:
APPROVAL FOR THE THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN REQUEST FOR RELIEF FOR H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT 2 - ALTERNATE REQUIREMENTS FOR EXAMINING PRESSURE-RETAINING BOLTED CONNECTIONS (TAC NO. MA4635)
Dear Mr. Young:
By letter dated January 19, 1999, Carolina Power & Light (CP&L) Company submitted its third 10-year interval inservice inspection (ISI) program plan for request for relief for H. B. Robinson Steam Electric Plant, Unit 2 (HBRSEP2). CP&L requested relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code,Section XI, paragraph IWA-5250(a)(2), involving "Corrective Measures" during the conduct of a system pressure test. The current request is to permit alternative requirements for examining Class 1, 2, and 3 pressure-retaining bolted connections. The request proposes that if a leakage is discovered at a bolted connection by VT-2 examination during a system pressure test, an engineering evaluation may be performed to determine the susceptibility of the bolting to corrosion and assess the potential for failure.
The NRC staff has reviewed your request and concluded that the proposed alternative, to first evaluate a bolted connection to determine its susceptibility to corrosion before removing and completing a VT-1 examination in accordance with IWA-31 00(a), provides an acceptable level of quality and safety and equivalent protection as provided by the ASME Code at HBRSEP2.
Therefore, the proposed alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for the current interval.
CII 9907280090 990715 POR ADOCK 05000261 PDR CQ 0O
-2 Further details regarding the staff's evaluation and conclusions are contained in the enclosed Safety Evaluation.
Sincerely Sheri R. Peterson, Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-261
Enclosure:
Safety Evaluation cc w/encl: See next page