ML17321A318
| ML17321A318 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/26/1984 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17321A317 | List: |
| References | |
| NUDOCS 8412060536 | |
| Download: ML17321A318 (6) | |
Text
7590-01 LVlITED STATES NUCLEAR REGULATORY COMMISSION INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NOS.
50-315 AND 50-316 NOTICE OF ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U. S. Nuclear Regulatory Commission (the Commission) is considering issuance of relief from the requirements of ASME Code Section XI and an exemption from the requirements of 10 CFR 50.55a to the Indiana and Michigan Electric Company (the licensee), for the Donald C.
Cook Nuclear Plant, Unit.
Nos.
1 and 2, located in Berrien County, Michigan.
ENVIRONMENTAL ASSESSMENT Identification of Pro osed Action:
The relief will permit the licensee to examine the reactor coolant pump casing welds in a manner different from that prescribed in Section XI of the ASME Boiler and Pressure Vessel
- Code, as. required by 10 CFR 50.55, because of high occupational radiation exposures.
The exemption to 10 CFR 50.55(a)(g)(4) will permit the licensee to utilize a common start date for Unit No.
1 and Unit No.
2 for the inservice inspecting
( ISI) and inservice testing (IST) programs.
The exemption would extend the Unit 1'first ten-year interval by one year and shorten the Unit 2 first ten-year interval by two years.
Relief is also proposed in conjunction with the exemption for the Unit 2 vessel beltline OCN, 05000315 b0536 841128 P
7590-01 examination for the first ten-year interval to be conducted during the mid-'1987 refueling outage using the 1974 edition through summer 1975 addenda as the governing code, for the Unit 2 class 1 and 2 welds remaining from the first interval to Ge. examined at the beginning of the second interval credited to that interval, and for the Unit 2 system pressure tests for the first interval to be conducted during the mid-1987 refueling outage to the 1974 edition through summer 1975 addenda as the governing code.
The relief and exemption with relief is responsive to the licensee's applications dated March 8, 1984 and March 15, 1984 respectively; the latter application supplemented by letter dated May 11, 1984.
The Need for the Pro osed Action:
The proposed relief is needed because.the
"- <t examinations prescribed by the code, visual inspection of the internal surfaces-'and volumetric examinatiop of the welds by radiography,'necessitate disassembly of the pump with high occupational radiation exposures.
The licensee's proposed alternate examinations would ensure that the pump casing welds are in good condition.
The proposed exemption with relief to allow a common start date for the ISI and IST programs for both Units 1 and 2 is needed to allow the use of the same Code Edition and Addenda for both Units, submission of a combined program which significantly decreases preparation and review time, and more efficient implementation of the. programs.
The licensee's proposed exemption with relief would ensure that the overall plant examination programs for both units are consisteht, that the scheduled examinations will proceed during the changeover period as previously planned, and that the Unit 2 beltline and system pressure tests will be done as previously scheduled to the codes currently applicable to this un%..
Cs
r Oo 7590-01 Environmental Im acts of the Pro osed Action:
The proposed relief on the reactor coolant pump casing welds combined with our current knowledge as a
result of experience gained at other.,reactors of the integrity of these we.='s provide a degree of assurance of operability that is equivalent to that prescribed by the ASME Code.
The proposed exemption with relief to provide common start dates for the ISI/IST program for Units 1 and 2 will also provide a degree of assurance that all inspections and testing will
'proceed as previously scheduled with applicable codes being utilized as ll
't determined by the interval dates or for Unit 2, reactor vessel and system pressure
- tests, as currently scheduled with the existing code requirements.
Consequently, the probability of the reactor coolant pump or plant systems not operating properly will not be increased and post-accident radiological releases will not be greater than previously",,determined nor does the proposed relief otherwise affect radiological plant effluents.
The relief associated with the reactor coolant pump casing welds will significantly reduce occupational radiation exposures associated with the examinations.,
Therefore, the Commission concludes that there are no significant radiological environmental impacts associated with the proposed relief and exemption with relief.
With regard to potential non-radiological
- impacts, the proposed relief and exemption with relief involves features located entirely within the restricted area as defined in 10 CFR Part
- 20. It does not affect non-radiological plant 'effluents and has no other environmental impact.
Therefore, the Commission conc:ludes that there are no significant non-radiological environmental impacts associated with the proposed action.
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7590-01 Alternative Use of Resources:
This action involves no use of resources not previously considered in the Final Environmental Statement (construction permit and operating license) for the Donald C.
Cook Nuclear Plant, Unit No~.
1 and 2.
A encies and Persons Consulted:
The NRC staff reviewed the licensee's request and did not consult other agencies or persons.
FINDING OF NO SIGNIFICANT IMPACT The Commission has determined not to prepare an environmental impact
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statement for the proposed relief and exemption with relief.
Based upon the foregoing environmental assessment, we conclude that the proposed action will not have a significant effect on the quality of the.
human environment.
l a'ol"further details'with respect to thi's'~action, see the licensee's applications dated March 8, 1984 and March 15, 1984 (as supplemented May 11, 1984), which are available for public inspection at the Commission s
Public Document
- Room, 1717 H Street, N.W., Washington, D.C., and at the Maude Reston Pal enski Memorial Library, 500 Market Street, St. Joseph, Michigan 49085.
Dated at Bethesda, Maryland this 26th day of November 1984.
FOR THE NUCLEAR REGULATORY COMMISSION Gus C.
- ainas, Assistant Director for Operating Reactors Division of Licensing
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