ML20035C659
| ML20035C659 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/05/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035C656 | List: |
| References | |
| NUDOCS 9304080260 | |
| Download: ML20035C659 (3) | |
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.a y SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FACILITY OPERATING LICENSE NO. NPF-12 SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY VIRGIL C. SUMMER NUCLEAR STATION. UNIT NO. 1 DOCKET NO. 50-395 i
1.0 INTRODUCTION
By letter dated June 22, 1992, South Carolina Electric & Gas Company (the licensee) submitted a request to update their Inservice Inspection Program to use a portion of a later edition of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) at the Virgil C. Summer Nuclear Station, Unit No. 1 (Summer Station). The staff has evaluated the licensee's request in the following section.
l 2.0 EVALUATION The Technical Specifications for Summer Station state that inservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be r
performed in accordance with-Section XI of the ASME Code and applicable addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 50.55a(g)(6)(i).
Paragraph 10 CFR 50.55a(a)(3) states that alternatives to t
the requirements of paragraph (g) may be used when authorized by the NRC if (i) the proposed alternatives would provide an acceptable level of-quality'and i
safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety.
Paragraph 10 CFR 50.55a(g)(4)(iv) permits a licensee to meet the requirements i
set forth in subsequent editions of ASME Code,Section XI, referenced in 10 CFR 50.55a(b) subject to the limitations and modifications listed'therein and subject to NRC approval.
Portions of editions or addenda may be used provided' that all related requirements of the respective. editions or addenda are met.
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2.1 Components
Reactor Coolant Pumps l
2.2 Code Reouirements:
ASME Code,Section XI,1977 Edition including Addenda through Summer-1978, Table IWB-2500-1, Category B-L-2, Item No. B12.20 requires visual, VT-1, inspection of the internal surfaces of pump casings.
Examinations are limited to welds in at least one pump in each group of pumps performing similar functions in the system; e.g., recirculating-t coolant pumps.
9304080260 930405 DR ADOCK 050003
. l Examinations may be performed on the same pump or valve selected for volumetric examination of welds.
2.3 Licensee's Recuest The licensee requests approval to update his Inservice Inspection Program to use a portion of a later edition of ASME Section XI that has been incorporated by reference into 10 CFR 50.55a(b).
l 2.4 Licensee's Basis for Recuest 1)
The required visual inspection is a major ALARA concern since doses are estimated to be 10 to 12 man-rem.
2)
The pump casings are a one piece casting and have no welds; therefore, no volumetric examinations are required. The pumps would be disassembled only for the visual examination of the internal surfaces.
3) 10 CFR 50.55a(b) currently references the 1989 Edition which no longer requires the examination if the pump is not disassembled j
for other reasons.
j 2.5 Alternative Reouirement f
The licensee requests approval to perform a VT-3 visual inspection of the internal surfaces of the pump casing if the pump is disassembled for maintenance or repair as permitted by the 1989 Edition of the ASME Coda.
The 1989 Edition of the ASME Code,Section XI, Tabie IWB-2500-1, Category B-L-2, Item No. B12-20 requires a visual, VT-3, inspection of the internal surfaces of pump casings.
l 3
Examinations are limited to at least one pump in each group of pumps r
performing similar functions in the system, e.g., recirculating coolant:
pumps.
i Examination is required only when a pump or valve is disassembled for maintenance repair or volumetric examination.
Examination of the internal pressure boundary shall be performed to the extent practicable, r
Examination is required only once during the inspection interval.
It should be noted that the Summer Station pumps have not been previously i
disassembled.
t 2.6 pmmarv l
The disassembly, visual inspection and assembly of a reactor coolant pump would result in a significant radiation exposure to plant l
personnel. The subject pumps are operable and would be disassembled for l
the sole purpose of performing the Code-required visual examination of the internal surfaces. The regulations permit the use of porticlis of later referenced editions or addenda of ASME Code,Section XI, :ubject to NRC approval, provided that all related requirements of the i
i
' i respective editions or addenda are met. By rulemaking effective September 8, 1992 (57 FR 34666), the 1989 Edition of the ASME Code,Section XI, was incorporated by reference into 10 CFR 50.55a(b). As an alternative, the licensee proposes to use all the requirements of the B-L-2 Examination Category for visual examination of pump casing from the 1989 Edition.
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3.0 CONCLUSION
Based on the above evaluation, the staff has determined that the licensee's alternative meets the requirements of the regulations to use portions of later referenced editions of ASME Code,Section XI. The licensee's alternative program is the same requirement for pump casings that any licensee that i
updates to thc 1989 Edition would be required to meet. The NRC has i
determined, pursuant to 10 CFR 50.55a (g)(4)(iv), that no relief is required for the licensee's proposed action of using a portion of the 1989 edition of the ASME Code,'which has been incorporated by reference in 10 CFR 50.55a(b).
t Whether all related requirements of the 1989 edition are met is subject to NRC l
Inspection.
Principal Contributor:
M. Hum Date:
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