ML17256A619
| ML17256A619 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 04/01/1983 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17256A620 | List: |
| References | |
| LSO5-83-04-001, LSO5-83-4-1, NUDOCS 8304070225 | |
| Download: ML17256A619 (4) | |
Text
e Docket No. 50-244 LS05-83-04-001 April 1, 1983 DISTRIBUTION VF E
licensee I Oocketj M/0 Pro rietar Enclosure Hr. John E. tlaier, Vice President Electric and Steam Production Rochester Gas
& Electric Corporation 89 East Avenue Rochester, New York 14649
Dear tlr. tlaier:
SUBJECT:
STEAN GENERATOR TUBE SLEEVING REPAIR PROGRAtt R. E. Ginna Nuclear Power Plant N
Lor an NRC PDR JMTaylor Local PDR ACRS (10)
ORB Reading SEPB DCrutchfield HSmith GDi ck JLyons TIppo1 ito FMirag 1 i a OELD By letter dated January 15, 1982, you requested that we review and approve a proposed revision to the Ginna Inservice Inspection
( ISI) program, which would delete the 25 sleeve limitation per steam generator inspection.
Your letter dated August 31,
- 1982, enclosed a Babcock 8 Wilcox Company Proprietary document entitled, "Steam Generator Rapid Sleeving Program Design Verification Report," which contains an analysis and safety evaluation supporting installation of additional sleeves at Ginna.
We have completed our evaluation of your request and its supporting analysis.
Based upon our evaluation, we find that the sleeving repair program method for degraded steam generator tubes to be an acceptable repair alternative to plugging.
Therefore, your request to delete the 25 tube limit per steam generator inspection is approved.
Our review is documented in the enclosed Safety Evaluation.
This evaluation consists of both a non-proprietary and proprietary version.
The proprietary version is being withheld from public disclosure.
Sincerely, CCL
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Encl osure:
Safety Evaluation (Proprietary and Non-Proprietary versions) cc w/Non-Proprietary
Enclosure:
See next page
- Please see previous concurrence page.
Original signed by/
Dennis tl. Crutchfield, Chief Operat)ng Reactors Branch 45
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~ j DISTRIBUTION Docket No. 50-244 Mr. John E. Maier, Vice President Electric and Steam Production Rochester Gas 5 Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Mr. Hafer:
SUBJECT:
STEAI'I GENERATOR TUBE SLEEVING REPAIR PROGRAM R. E. Ginna Nuclear Power Plant W/Pro rietar Enclosure licensee Docket W/0 Proprietary Enclosure N
NRC PDR Local PDR DCrutchfield HSmith GDick JLyons TIppolito FMirag1 i a OELD ELJordan JMTaylor ACRS (10)
SEPB By letter dated January 15, 1982, you requested that we review and approve a proposed revision to the Ginna Inservfce Inspection (ISI) program, which would delete the 25 sleeve limitation per steam generator inspection.
Your letter dated August 31, 1982, enclosed a
(BBW) Proprietary document entitled, "Steam Generator Rapid Sleeving Program Design Verification Report," which contains an analysis and safety evaluation supporting installation of additional sleeves at Ginna.
We have completed our evaluation of.your request and its supporting analysis.
Based upon our evaluation, we find that the sleevfng repair program method for degraded steam generator tubes to be an acceptable repair alternative to, plugging.
Therefore, your request to delete the 25 tube limit per steam generator inspection is approved.
Our review is documented in the enclosed Safety Evaluatfon.
This evaluation consists of both a non-proprietary and proprietary version.
The proprietary version is being withheld from public disclosure.
Your proposed plugging limit for sleeves of 30$ sleeve-wall degradation remains an open item and will be addressed in a separate evaluation.
Sincerely,
Enclosure:
Safety Evaluation (Proprietary and Non-Proprietary versions) cc w/Non-Proprietary
Enclosure:
Dennis H. Crutchfield, Chief Operating Reactors Branch g5 Division of Licensing OFFICE/
SURNAME$
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