ML17326B235
| ML17326B235 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Cook |
| Issue date: | 05/20/1986 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML17326B234 | List: |
| References | |
| GL-83-28, GL-84-15, NUDOCS 8605300339 | |
| Download: ML17326B235 (4) | |
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il ENCLOSURE SAFETY EVVOFfTOH REPORT GENERIC L T 83-28,
.l.
AND 3.2.3 S
NEN L
H S
ET -.EL DONA K
L KT.:5-5 1
INTPODUCTION AND
SUMMARY
Generic Letter 83-28 describes intermediate term actions to be taken by licensees and applicants to address the generic issues raised by the two ATMS events that occurred at Unit 1 of Salem Nuclear Power Plant.
This report 1s an evaluation of the responses submitted by Indiana and Michigan Electric Company, the licensee for the Donald C.
Cook Nuclear Power Plant, Units 1,2 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 h
test requirements in existing Technical Specifications which can be demonstrated to dearade rather than enhance safety.
Appropriate changes to these test re-quirements, with supporting iustification, shall be submitted for staff approval.
8605300339,'8hOMO'DR ADOCKi050003i5 P
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~ EVALUATION The licensee for the Donald C.
Cook Nuclear Power Plant responded to these requirements with submittals dated November 4, 1983
, April 10, 1985 Decem-2 3
ber 9, 1985, and a Telecon of March 26, 1986 For Item 3.1.3, the licensee 4
5 stated that there were no post-maintenance testing requirements in Technical Specifications for the reactor trip system which degraded safety.
- However, for Item 3.2.3, the licensee identified post-maintenance testing of the diesel generators as being perceived to degrade safety.
This specific concern is being addressed by the licensee and the staff independently of this review as part of the resolution of the concerns of Generic Letter 84-15.
No other post-maintenance tests were identified by the licensee that may degrade safety.
CONCLUSION Based on the licensee's statement that no post-maintenance test requirements for the reactor Trip System were found in Technical Specifications that degraded
- safety, we find the licensee's responses acceptable for Item
- 3. 1.3 of Generic Letter 83-28.
In the response for Item 3.2.3, the licensee identified post-maintenance testing of the diesel generators as being degrading to safety.
This concern will be resolved during the review of the concerns of Generic Letter 84-15 and we find this acceptable.
No other post-maintenance tests were identified that may degrade safety, therefore, we conclude that the licensee's responses are acceptable for Item 3.2.3 of Generic Letter 83-28.
REFERENCFS 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 ATMS Events (Generic Letter 83-28)," July 8, 1983.
2.
Indiana and Michigan Electric Company letter tn NRC, M. P. Alexich to D.
G. Eisenhut, Director, Division of Licensing, NRC, "Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2, Docket Nos.
50-315 and 50-316, Licensee Nos.
DPR-58 and DPR-74, Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events,"
November 4, 1983, AEP:
NRC: 0838A.
3.
Indiana and Michigan Electric Company letter to NRC, M. P. Alexich to H. 4. Denton, Director, Office of Nuclear Reactor Requlation,
- NRC, "Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2, Docket Nos.
50-315 and 50-316, Licensee Nos.
DPR-58 and DPR-74, Generic Letter 83-28, Additional Information Reauested in Response to Generic Letter 83-28,"
April 10,
- 1985, AEP:NRC;0838H.
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Indiana and Michigan Electric Company letter to NRC, M. P. Alexich to H.
R. Denton, Director, Office of Nuclear Reactor Regulation,
- NRC,
. "Generic Letter 83-28, Additional Information on Items 3. 1.3 and 3.2.3, December 9, 1985.
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