ML20081G834
| ML20081G834 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/11/1983 |
| From: | Tucker H DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-SSINS-6820 IEB-82-02, IEB-82-2, NUDOCS 8311070199 | |
| Download: ML20081G834 (3) | |
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DUKE POWER GOMPANY
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Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 36303
Subject:
Oconce Nuclear Station Docket No. 50-269
Dear Sir:
In response to IE Bulletin 82-02 dated June 2, 1982, please find attached responses to Items 2 and 4 for Unit 1.
Duke Power provided a response to Items 3 and 5 in our submittal dated July 29, 1982. Responses to Item 1 (for all three Oconee units) and to Items 2 and 4 (for Unit 3 only) were provided in our supplemental submittal dated November 15, 1982. Responses l
to Items 2 and 4 for Unit 2 will be provided following the next refueling outage as specified in the bulletin.
I declare under penalty of perjury that the statements set forth herein are true and correct to the best of my knowledge, executed on October 11, 1983.
Very truly yours, 0 sf k e
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Hal B. Tucker PFG/php Attachment cc:
Mr. J. C. Bryant NRC Resident Inspector Oconee Nuclear Station Mr. John F. Suermann Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 l
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JP0/HBT/PFG October 11, 1983 i
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Item 2
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Threaded fasteners of closure connections, identified in the scope of this bulletin, when opened for component inspection or maintenance shall be removed, cleaned, and inspected per IWA-2210 and IWA-2220 of ASME Code Section XI (1974 edition or later) before being reused.
Response
The components that were inspected during Unit l's latest refueling outage included the following:
- 1) Once Through Steam Generator (OTSG) upper and lower manways.
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- 2) Primary System Code Relief Valves.
- 3) Control Rod Drive Mechanism, bolting assemblies 38 and 53.
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Item 4 4
'T A written report signed under -cath or affirmation under provisions of Section 182a, Atomic Energy Act of-1954 as amended. shall be submitted to,the Regional Administrator of the appropriate NRC Regional Office within,60 days following the completion of t.he outage during which Action Item 2 was performed. The s
report is to include:
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a.
A statement that Action Item i has been completed.
b.
Identification of the specific connections examined as required by Action Item 2.
c.
The results of the examinations performed on the threaded fasteners as required by Action Item 2.
If no degradation was observed for a particular connection, a statement to that effect, identification of the connection, and whether the fasteners were examined in place or removed is all that is required.
If degradation-was observed, the report should provide detailed information.
Response
Sub-Item a As was discussed in our November 15, 1982 submittal, the procedures as t
discussed in the bulletin have been completed and these along-vith a training
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program are on file.
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y Same as was listed in Item 2.
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JP0/HBT/PFG October 11, 1983 Sub-Item c The method and results of the examinations of the components listed in Item 2 are as follow:
Component Inspectica Method Inspection Results 1.
OTSG "A" upper Visual No degradation was observed.
manway bolting All studs were replaced with new studs.due to redesign of fastener.
2.
OTSG "A" lower Visual No degradation was observed.
manway bolting All studs were replaced with new studs due to redesign of fastener.
3.
OTSG "B" upper Visual No degradation was observed.
manway bolting All studs were replaced with new studs.due to redesign of fastener.
4.
OTSG "B" lower Visual No degradation was observed.
- , manway bolting All studs were replaced with new studs due to redesign of fastener.
5.
Primary system Visual No degradation was observed.
code relief Bolting was replaced with valves new bolts per procedure.
6.
CRDM Visual Slight galling of threads was observed for assemblies 38 and 53.
These were replaced with new bolts.
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