ML19274E563
| ML19274E563 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/23/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Bixel D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| Shared Package | |
| ML19274E564 | List: |
| References | |
| NUDOCS 7904090183 | |
| Download: ML19274E563 (3) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMisslON e '.j, f'
5.(h, M i h WASHINGTON, D. C. 20555
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March 23,1979
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Pccket No. 50-155 Mr. David Bixel Nuclear Licensing Administrator Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201
Dear Mr. Bixel:
The Commission has issued the enclosed Amendment No.24 to Facility Operating License No. DPR-6 for the Big Rock Point Plant.
The amendment consists of changes to the Technical Specifications in response to your request dated January 26, 1979.
The amendment changes Section 5.1.2 of the Technical Specifications by replacing the current description of control rod assemblies with wording consistent with our February 1978 draft Standard Technical Specifications for the Big Rock Point Plant.
' The current Tec.;ical Specifications contain unnecessary descriptive design details in many sections because they were originally written-in 1964 before any standard formats had been established.
Design details concerning sheath thickness, number of filled tubes, number of solid tubes, wall thickness, etc. do not involve limiting conditions of operation, safety limits or concerns nomally reviewed by the Commission.
Limiting Conditions for Operation and Surveillance Requirements concerning: reactivity differences between actual and predicted control rod configuration, operability requirements, maximum scram insertion times, withdrawal and insertion sequences, maximum rod reactivity worths, maximum reactivity worth of notch movements, scram accumulator requirements, drive to rod coupling requirements, position indication requirements, and requirements for control rod drive thimble support structures are specified in other sections.
You requested this change prior to issuance of the Standard Technical Specifications, which would have made the change automatically, because one of the control blades needs to be replaced c'uring the current refueling outage.
The replacement blade is a type II blade.
This type of blade was approved for use in the Big Rock Point reactor by the Commission on February 11, 1965, and was in use during the period of February 1965 until February 1971.
The current Technical Specifi-cation only describes type I and type iia blades and therefore use of a type II blade is not permitted.
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- 'r. David Bixel March 23,1979 We have concluded that the proposed change is administrative and acceptable for the following reasons
(1) existing requirements concerning materials and active length and poison material are not changed, (2) the appropriate limiting conditions for operations and surveillance requirements are not changed, (3) the replacement 71ade is a spare blade that was previously reviewed and approved
'cr use in the reactor, and (4) the proposed change is consistent with our recommended requirements of the Standard Technical 1pecifications to be applied to the Big Rock Point Plant.
The amendment is administrative in nature and does not authorize a change in effluent types or total amounts nor an increase in power level, and will not result in any significant environmental impact.
Having made this determination, we have further concluded that the amendment involves an action which is insi' 'ficant from the standpoint of environmental impact and pursuant.o 10 CFR 151.5(d)(4) that an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
Since the amendment is adminhtrative in nature, it does not involve significant new safety information of a type not considered by a previous Commission safety revicw of the faciiity.
It does not involve a significant' increase in the probability or consequences of an accident, does not involve a significant decrease in a safety margin, and therefore does not involve a significant hazards con-sideration.
We have also concluded that there is reasonable assurance that the health and safety of the public will not be endangered by this action and that the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
A copy of the related Notice of Issuance is also enclosed.
Sincerely, fW
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Dennis L. Ziemann,; Chief Operating Reactors Branch #2 Division of Operating Reactors
Enclosures:
1.
Amendment No. 24 to License No. DPR-6 2.
Notice of Issuance cc w/ enclosures:
See next page
Mr. David Bixel March 23,1979 cc w/ enclosures:
Mr. Paul A. Perry, Secretcr, U. S. Enviror.nental erotection Consuners Power Company Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region V Office ATTN:
EIS CCORDIf1ATOR Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Power Company Chicago, Illinois 50604 212 West Michigan Avenue Jackson, Michigan 49201 Hunton & Williams George C. Freenan, Jr., Esquire P. O. Box 1535 Richnond, Virginia 23212 Peter W. Steketee, Esquire 505 Peoples Building Grand Rapids, Michigan 49503 Charlevoix Public Library 107 Clinton Street Charlevoix, Michigan 49720 Chairman County Board of Supervisors Charlevoix County Charlavoix, Michigan 49720
- 0ffice of the Governor (2)
Room 1 - Capitol Building Lansing, Michigan 48913 Director, Technical Assessment Division Office of Radiation Programs (AW-459)
U. 5. Environmental Protection Agency Crystal Mall #2 Arlington, Virginia 20460
- (w/cy of CPCo filing dtd.1/26/79)
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