ML20215E012
| ML20215E012 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 10/07/1986 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20215D977 | List: |
| References | |
| GL-83-28, NUDOCS 8610140392 | |
| Download: ML20215E012 (3) | |
Text
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O ENCLOSURE SAFETY EVALUATION REPORT g
GENERIC LLITER 83-28. ITEMS 3.1.3 AND 3.P.3 POST-MAINTENANCE TESTING (RTS COMPONENTS, ALL OTHER SAFETY-RELATED COMPONENTS)
CALLAWAY PLANT, UNIT I DOCKET NO. 50-483 INTRODUCTION AND
SUMMARY
I Generic Letter 83-28 describes intermediate term actions to be taken by licensees and applicants to address the generic issues raised by the two ATWS events that occurred at Unit 1 of Salem Nuclear Power Plant.
This report is an evaluation of the responses submitted by Union Electric Company, the licensee-for the Callaway Plant, Unit I for Items 3.1.3 and 3.2.3 of the Generic letter. The actual documents reviewed as part of this evaluation are listed in the references at the end of this report.
The requirements for these two items are identical with the exception that Item 3.1.3 applies these requirements to the Reactor Trip System components and Item 3.2.3 applies them to all other safety-related components. Because of this similarity, the responses to both items were evaluated together.
REQUIREMENT Licensees and applicants shall identify, if applicable, any post-maintenance test requirements in existing Technical Specifications which can be demonstrated to degrade rather than enhance safety. Appropriate changes to these test re-quirements, with supporting justification, shall be submitted for staff approval.
e610140392 e61007 DR ADOCK 05000 83
. 1 EVALUATION The licensee for the Callaway Plant, Unit I responded to these requirements with 2
a submittal dated November 18, 1983. The licensee's response given in this sub-mittal did not address the concerns of these items. Following discussions with the staff, the licensee submitted additional response dated August 12, 1986.
In this submittal, the licensee stated that there were no post-maintenance testing requirements in Technical Specifications for either reactor trip system or other safety-related components which degraded safety.
CONCLUSION Based on the licensee's statement that no post-maintenance test requirements were found in Technical Specifications that degraded safety, we find the licensee's responses acceptable for Items 3.1.3 and 3.2.3 of Generic Letter 83-28.
REFERENCES 1.
NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits,
" Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983.
i 2.
Letter, D. F. Schnell, Union Electric Company, to H. R. Denton, USNRC, dated November 18, 1983.
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. C REFERENCES (CONT.)
3.
Letter, D. F. Schnell, Union Electric Company, to H. R. Denton, USNRC, dated August 12, 1986.
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