ML17321A763
| ML17321A763 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/22/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17321A762 | List: |
| References | |
| NUDOCS 8508070305 | |
| Download: ML17321A763 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
70 TO FACILITY OPERATING LICENSE NO.
DPR-74 INDIANA AND MICHIGAN ELECTRIC COMPANY DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 DOCKET NO. 50-316 INTRODUCTION In License Amendment No.
6 issued June 16, 1978, License Condition Number 4 was included as follows:
"A.
Indiana and Michigan Power Company* shall, prior to startup following the next regularly scheduled refueling outage, replace all Foxboro E13D and EllGM transmitters in safety-related circuits inside containment with transmitters qualified by sequential environmental testing in accordance with IEEE 323-1971.
B.
Indiana and Michigan Power Company* shall, prior to October 1, 1978, complete and document for staff review and approval sequential environmental qualification testing in accordance with IEEE 323-1971 of the Barton 764 transmitters used in safety-related circuits inside containments."
By letters dated June 2, 1978, July 21, 1978, August 18, 1978, October 5, 1978 and September 22,
- 1980, Indiana and Michigan Electric Company (the licensee) reported on the replacement of the Foxboro transmitters and qualification of the Barton 764 transmitters in safety related circuits inside containment.
These requirements formed the forerunners to the 10 CFR 50.49 regulation on "Environmental gualification of Electrical Equipment Important to Safety For Nuclear Power Plants."
EVALUATION The licensee has completed the replacement of the Foxboro E13DM and EllGM transmitters in safety-related circuits inside containment with qualified transmitters.
This completes license condition 4A and is acceptable.
The Barton 764 transmitters and the replacement transmitters for the above Foxboro transmitters, among other components, have been the subject of the Environmental gualification Program at the Donald C.
Cook Nuclear Station.
License was amended accordingly.
8508070305'50722 PDR ADOCK 05000316 P
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On January ll, 1985, in a letter from S.
A. Varga to J. Dolan, the NRC approved the Environmental gualification Program for Cook.
The Safety Evaluation enclosed with the letter addressed the proposed resolution of the known deficiencies and concluded that the licensee's program was in compliance with the requirements of 10 CFR 50.49.
On March 1, 1985, in a letter to the licensee, the NRC addressed the latest request for a deadline extension for qualification of equipment at Cook.
One of the items involves relocating specific ITT Barton transmitters to outside of containment.
The Unit 1 transmitters will be relocated in the current ongoing refueling outage.
The Unit 2 transmitters will be relocated during the refueling outage scheduled to begin in November 1985.
The NRC has found this acceptable and so notified the licensee in the March 1, 1985 letter.
SUMMARY
On the basis that the Foxboro transmitters have been replaced and the Barton transmitters are subject to 10 CFR 50.49, are part of the approved Environmental gualification Program at Cook, and approval has been granted for certain Barton transmitters to be relocated outside containment under an approved
- schedule, we find that the licensee has met the requirements of License Condition 4 of Amendment 6 issued June 16, 1978 and this License Condition may be deleted.
This deletion will not affect in any way the current approvals or 10 CFR 50.49 requirements.
ENVIRONMENTAL CONSIDERATION This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Comission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding.
Accordingly, this amendment meets the eligibility criteria fot categorical exclusion set forth in 10 CFR Sec 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
CONCLUSION l<e have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated:
July 2p, lgB5 PRINCIPAL CONTRIBUTOR:
D. Wigginton