ML20002C575
| ML20002C575 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 10/17/1977 |
| From: | Desiree Davis Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20002C561 | List: |
| References | |
| NUDOCS 8101100507 | |
| Download: ML20002C575 (4) | |
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t-UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET N0. 50-155 CONSUMERS POWER COMPANY NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Commission (the Comission) has issued Amendment No.15 to Facility Operating License No. DPR-6, issued to the Consumers Power Company (the licensee), which revised the license and Technical Specifications for operation of the Big Rock Point Plant (the facility) located in Charlevoix County, Michigan.
The amendment is effective as of its date of issuance.
The amendment:
(1) granted an exemption from the emergency core cooling system (ECCS) failure criterion of 10 CFR Section 50.46, Appendix K, Paragraph I.D.1 as applied to a loss-of-Coolant Accident followed by a concurrent single failure in the redundant core spray system for the 1978 operating fuel cycle, (2) authorized operation of the facility with additional uranium 235 fuel assemblies identified as Reload G-3 for Cycle 15 as replacement for the spent fuel assemblies, and (3) modified limiting conditions of operation and surveillance requirements based upo1 the Commission's review of the licensee's applications and based upon the licensee having complied with the requirements of condition III.d of the Commission's Memorandum and Order dated May 26, 1976.
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The applications for the exemption and amendment comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations.
The Comission has made appropriate findings as required by the Act and the Comission's rules and regulations in 10 CFR Chapter I, which are set forth in' the license amendment.
In connection with item (1) above, Notice of Request for Exemption from Requirements Concerning Emergency Core Cooling System Performance was published in the Federal Register for coments on September 26, 1977 (42 F.R. 48951). No coments were received on this item.
Prior public notice of items (2) and (3) above was.not required since these actions do not involve a significant hazards consideration.
The.Comission has determined that the issuance of this amendment will not result in any significant environmental impact and that pursuant-to 10 CFR 551.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with issuance of this amendment.
For further details with respect to this action, see (1) the application for exemption dated September 15, 1977 (as supplemented by letter dated October 12,1977),(2) the applications for amendment dated December '-
176 (as supplemented by letters dated February 9 and August 17,1977),and April 15,1977 (as supplemented by letters dated April 21, August 12 and 24, and September 26,1977),(3) Amendment No. 15 to License No. DPR-6, (4) the Comission's related Safety Evaluations, and (5) the Commission's Memorandum and Order dated May 26, 1976. All of these items are available for public inspection at the Commission's Public Document Room,1717 H Street, N. W., Washington, D. C. and at the Charlevoix Public Library, I
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..,tf, 'g 107 Clinton Street, Charlevoix; Michigan 49720.
A single copy of items (3) and (4) may be obtained upon request
-addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C.
20555, Attention: Director, Division of Operating Reactors.
Dated at Bethesda, Maryland, this 17th day of' October,1977.
j FOR THE NUCLEAR REGULATORY COMMISSION
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Don K. Davis, Acting Chief Operating Reactors Branch #2 Division of Operating Reactors i
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- //7- [/e/" ~The position of the ring spray.line isolation valves has been changed so that these components are no longer subject to flooding during a LOCA. As a result of this alteration, a relatively compli-cated procedure that had required operator action soon after a LOCA has been eliminated.
Since the likelihood of operator error is high during a high stress condition and for an infrequent situation such f
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'as a LOCA, the deletion of core spray isolation requirements is an fv important addition to the reactor's safety.
..h, The reliability of portions of the ECCS required for long term U
cooling has been improved by the addition of flexible hose that
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f can bymss the underground portion of the fire system. Technical
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gk Specification surveillance requirements have been added to ensure
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3.0 CONCLUSION
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The staff concludes t a NSS provides sufficient D
ECCS cooling water ow with the most limiting single failure and f'/
ble core spray distribution during expected produces an acce LOCA conditions. To ensure the adequate redundant NSS core spray h,<,l performance, removal of power from the backup containment spray y
system valve has been required.
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The staff concludes that granting the requested short-term exemptionQ.v)c E to permit BRP to resume operation, subject to the conditions pd['I;'
specified below, is warranted in view of the staff's assessment of the overall ECCS performance and reliability:
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Prior to the BRP Cycle 16 startup, CPCo must provide an evaluation of the ring spray system demonstrating acceptable p/'/ ~
performance at the anticipated LOCA environments, or modify
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the ring spray system such that acceptable performance is
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achieved, and 2.
If a new core spray sparger design is developed, the hydraulic characteristics of the ECCS must be evaluated to ensure adequate perfonnance of both spray systems considering the most limiting single failure.
We have concluded, based on the considerations discussed above, that the exemption is authorized by law and will not endanger life or property or the common defense and security'and is otherwise in the public interest.
Date:
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