ML20151U102
| ML20151U102 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/28/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151U097 | List: |
| References | |
| NUDOCS 8808180401 | |
| Download: ML20151U102 (2) | |
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a ueg'o UNITED STATES g
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g NUCLEAR REGULATORY COMMISSION t
t WASHINGTON, D. C. 20666
- ....l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION l
SUPPORTING AMENDMENT NO. 24TO FIyILITY OPERATING LICENSE NO. NPF 4 DETROIT COISON COMPANY WOLVERINE POWER SUPPLY COOPERATIVE, INCORPORATED FERMI-2 DOCKET NO. 50-341
1.0 INTRODUCTION
By letter dated Narch 28, 1988, the Detroit Edison company (DECO or the licensee) requested amendment to the Technical Specifications (TSs) appended i
to Facility Operating License No. NPF-43 for Ferai-2.
The proposed amendment would change TS 3/4.3.7.11, "Radioactive Liquid Effluent Monitoring Instrumenta-tion," TS 3/4.3.7.12. "Radioactive Gaseous Effluent Nonitoring Instrumentation,"
and TS 6.9.1.8, "Semiannual Radioactive Effluent Release Report," *.o modify the i
Action and Table Notations to allow continued use of the release pathways for
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which effluent monitoring instrumentation may not be operable provided that grab samples and analyses and/or flow rate calculations are made at specified frequencies.
The proposed change would also clarify the reporting requirements consistent with the changes requested in TSs 3/4.3.7.11 and 3/4.3.7.12.
2.0 EVALUATION TSs 3/4.3.7.11 and 3/4.3.7.12 currently require termination of all releases, via a pathway for which an effluent monitor is inoperable, after 30 days or 14 days as appropriate regardless of any sampling, analysis or calculational capabilities available at that tio.
This requirement, in most cases, will necessitate a plant shutdown.
The Fenni-2 TSs 3/4.3.7.11 and 3/4.3.7.12 we e, in part, based upon NUREG-0473, "Standard Radiciogical Effluen? Technical Specifications for BWRs," Revision 1 (Standard RETS).
Subsequent to the issuance of the Fermi-2 Operating License, the NRC staff clarified the intent of the RETS, namely, that alternative monitoring techniques may be used, with no restricted time limitations, to assess the effluents should the primary monitoring means not be available.
The RETS 30-day requirement is only intended as a reporting requirement for inoperable instrumentation.
Furthermore, TSs 3/4.3.7.11 and 3/4.3.7.12 contain exclusions from the wpplicability of TS's 3.0.3 and 3.0.4.
This indicates that it was not the staff intention that a plant shutdown be required for situations covered by compensatory actions.
The NRC staff finds that the proposed changes incorparate the wording of present staff gedance and appropriately cover compensatory measures in the event of
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inoperable primary monitoring. Thus, the staff finds that the licensee's proposed changes to their RETS meet the intent of the NRC staff's model RETS for BWRs, NUREG-0473, Revision 2, February 1,1980, and are, therefore, acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
An Environmental Assessment and Finding of No Significant Impact has been issued for this amendment (53 FR ~2808.1, July,;26',' 1988).
4.0 CONCLUSION
We 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.
Principal Contributor: Wayne Meinke Dated:
July 28, 1988 i
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1 7590-01 i
UNITED STATES NUCLEAR REGULATORY COMMISSION DETROIT EDISON COMPANY WOLVERINE POWER SUPPLY COOPERATIVE, INCORPORATED DOCKET NO. 50-341 NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE I
The United States Nuclear Regulatory Comission (the Commission) has issued Amendment No. 24 to Facility Operating License No. NPF-43, issued to the Detroit Edison Company and Wolverino Power supply Cooperative, Inc.
(the licensees), which revised the Technical Specificctions (TSs) for operation of Fermi-2 located in Monroe County, Michigan.
The amendment is effective as of the date of issuance.
The amendment allows continued use of release pathways for which
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effluent monitoring instrumentation is not operable provided grab samples and analysis and/or. flow rate calculations are made at the specified frequencies.
The application for amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (that Act),
and the Commission's rules and regulations.
The Commission has made appropriate findings, as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license 1
amendment.
Notice of Consideration of Issuance of Amendment to Facility Operating
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License and Opportunity for Hearing in connection with this action was published in the FEDERAL REGISTER on May 13, 1988 (53 FR 17130).
No request for hearing or petition to intervene was filed following this notice.
2-Also in connection with this action, the Commission prepared an Environmental Assessment and Finding of No Significant Impact which was published in the FEDERAL REGISTER on July 26,1988 at 53 FR 28081.
For further details with respect to this action, see (1) the application for amendment dated March 28,1988,(2) Amendment No. 24 to License No. NPF-43, and (3) the Commission's related Safety t
Evaluation. All of these items are available for public inspection at the Commission's Public Document Room, 1717 H Street, N.W., Washington, D. C.
20555, and at the Monroe County Library Syshm, 3700 South Custer Road, Monroe, Michigan 48161.
A copy of items (2) and (3) may be obtained upon request addressed to the U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, Attention:
Director, Division of Reactor Projects - III, 1V, V and Special Projects.
Dated at Rockville, Maryland, this 28th day of July FOR THE NUCLEAR REGULATORY COMMISSION
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TheodoreR. Quay,ProjectManager Project Directorate III-1 Division of Reactor Projects - III, IV, V & Special Projects
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