ML17263B103
| ML17263B103 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/23/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17263B102 | List: |
| References | |
| NUDOCS 9507060342 | |
| Download: ML17263B103 (2) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 U
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. GNN UC POME AT OC 0-T.N TNNTNNNN TTTI NN The Technical Specifications for R.
E. Ginna Nuclear Power Plant state that the inservice inspection of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASHE Code)
Class 1, 2, and 3 components shall
, be performed in accordance with Section XI, of the ASHE Code and applicable Addenda as required by 10 CFR 50.55a(g),
except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i).
Paragraph 50.55a(a)(3) states that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed alter natives would provide an acceptable level of quality and 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.
Pursuant to 10 CFR 50.55a(g)(4),
ASHE Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASHE
- Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components, to the extent practical within the limitations of design,
- geometry, and materials of construction of the components.
The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI, of the ASHE Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations'and modifications listed therein.
The applicable edition of Section XI, of the ASHE Code for the R.
E. Ginna Nuclear Power Plant, third 10-year inservice inspection (ISI)
'nterval is the 1986 Edition.
The components (including supports) may meet the requirements set forth in subsequent editions and addenda of the ASHE Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Commission approval.
Enclosure 9507060342 950623
'DR ADQCK 05000244 P
Pursuant to 10 CFR 50.55a(g)(5), if the licensee determines that conformance with an examination requirement of Section XI, of the ASNE Code is not practical for its facility, information shall be submitted to the Commission in 'support of that determination and a request made for relief from the ASIDE Code requirement.
After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(i),
the Commission may grant relief and may impose alternative requirements that are determined to be authorized by law, will not endanger life, property, or the common defense and security, and are otherwise in the public interest, giving due consideration t'o the burden upon the licensee that could result if the requirements were imposed.
In a letter dated December 15,
- 1992, Rochester Gas and Electric Corporation (RG&E or the licensee) submitted to the NRC its third 10-year interval inservice inspection program plan Requests for Relief Nos.
18-1 and 18-2.
Additional information was provided by RG&E in its letter dated February 16, 1995.
2.0 U
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IONS The NRC staff, with technical assistance from its contractor, the Idaho National Engineering Laboratory (INEL), has evaluated the information provided by RG&E in support of its third 10-year interval inservice inspection program plan Requests for Relief Nos.
18-1 and 18-2.
Based on the information submitted, the NRC staff adopts the contractor's conclusions and recommendations presented in the Technical Letter Report attached.
The proposed alternatives contained in the Requests for Relief Nos.
18-1 and 18-2 are authorized as requested pursuant to 10 CFR 50.55a(a)(3)(ii).
Principal Contributor:
T.K. HcLellan Date:
dune 23, 1995
Attachment:
Technical Letter Report