ML17319B509
| ML17319B509 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/02/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17319B508 | List: |
| References | |
| NUDOCS 8209140026 | |
| Download: ML17319B509 (7) | |
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~o UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 57 TO FACILITY'OPERATING LICENSE NO.
DPR-58 AND AMENDMENT NO.
41 TO FACILITY OPERATING LICENSE NO.
DPR-74 INDIANA AND MICHIGAN ELECTRIC COMPANY DONALD C.
COOK NUCLEAR "PLANT UNIT NOS.
1 AND 2 DOCKET NOS.
50-315 AND 50-316 INTRODUCTION By letter dated April 7, 1982, as supplemented by letters dated June ll, 1982, June 30, 1982, and July 8, 1982, the Indiana and Michigan Electric Company (the licensee) proposed changes to the Technical Specifications appended to Facility Operating License Nos.
DPR-58 and DPR-74 for the Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2.
The proposed changes consist of changes to permit stoI age of Exxon fuel with a uranium enrichment of 3.84 weight percent of U-235 in the new and spent fuel storage racks.
The acceptability of these changes from a safety standpoint are discussed below.
A separate Safety Evaluation Report will address the request for a power increase.
DISCUSSION AND EVALUATION Indiana and IIichigan Electric Company has proposed revision of Technical Specifications to increase the enrichment of fuel permitted to be stored in the new and spent fuel storage racks to accommodate the Exxon Nuclear Company (ENC) designed fuel which is to be used.in Cycle 4.
The present Technical Specification limit on enrichment is 3.5 weight percent U-235 with an axial loading of 44.22 grams of U-235 per axial centimeter.
The most reactive ENC design assembly has an enrichment of 3.84 weight percent with an axial loading of 43.29 grams of U-235 per centimeter.
The r'eduction in axial loading is the result of smaller diameter pellets in the ENC design which increases the ll water to fuel ratio and thus the reactivity of the assembly.
B209140026 82090>
PDR ADOCK 05000315 P
The spent fuel pool racks were installed in 1980.
They were designed by Exxon and are described in Reference 1 along with the criticality analysis (also performed by Exxon).
The NRC evaluation of the.,racks and the criticality analysis is presented in Reference 2.
That elaluation concludes that acceptable analysis methods which have been verified by comparison with experiment were used.
The same methods are used for the present analysis.
In particular the use of the CCELL code for performing sensitivity studies is the same for both sets of analyses.
The effective multiplication factor. for the spent fuel pool when loaded with the most reactive Exxon fuel assemblies is 0.946 at the 95 percent confidence level if nominal enrichment and boron loading values are used.
All other parameters are taken at their worst case values including pool water temperature which is assumed to be 4 degrees Centigrade.
If maximum enrichment and minimum boron loading (at the 95 percent confidence value) are considered the value is 0.949 including all uncertainties.
This meets our acceptance criterion of less than or equal to 0.95 and is acceptable.
The fresh fuel racks at the D.
C.
Cook facility were also reanalyzed for the more reactive Exxon fuel.
The KENO IV code was used to,obtain the effective multiplication factor as a function of moderator density.
The maximum array size (12 rack modules) was used (ie.,
an infinite array was not assumed as was done for the spent fuel racks).
The effect of the concrete reflector around the stoppage pit Was included.
The'resultarit effective multiplication factor was 0.920 at full water density for the highest reactivity Exxon fuel for the maximum enrichment at the 95 percent confidence level.
This meets our acceptance criterion of 0.95 for this
'uantity and is acceptable.
The effect of flooding the racks with low hydrogen density moderator (water spray, foams, etc.)
was examined by calculating the pool effective multiplication factor as a function of water density.
This value first decreases as water density is reduced then increases
- again, reaching'
a secondary peak at approximately 5 percent water density, and decreases again as the density. is further lowered.
The value of the effective multiplication factor at the secondary peak was 0.849 which meets our acceptance criterion of less than or equal to 0.98 for this quantity and is acceptable.
Based on the discussion presented above we conclude that any number of fuel assemblies of the Exxon increased reactivity design having a uranium enrichment of less than or equal to 3.84 weight percent U-235 may be stored in the spent fuel storage racks.
We further conclude that up to 12 of the rack modules in the fresh fuel storage pit (i.e., the whole pit) may be loaded with these assemblies.
We further conclude that proposed Technical Specifications 5.6.1.2-for Units 1
and 2 and Specification 5.3.1 for Unit 2 are acceptable.
References 1.
Letters:
American Electric Power to NRC dated November 22, 1978, January 22,
- 1979, and April 16, 1979.
2.
Amendment No.
32 to Facility Operating License No. DPR-58 and Amendment No.
13 to Facility Operating License No.
DPR-74 for the D.
C.
Cook Nuclear Plant, Unit Hos.
1 and 2 dated October 16, 1979.
ENVIRONMENTAL CONSIDERATION We have determined that the amendments do not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmenta'l impact.
Having made this determination, we have further concluded that the amendments involve an action which is insignificant from the standpoint of environmental impact'and, pursuant to 10 CFR 51.5(d)(4),
that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of these amendments.
CONCLUSION We have concluded, based on the considerations discussed above, that:
(1) because the amendments do not involve a significant decrease in the probability or consequences of an accident previously evaluated, do not create the possi-bility of an accident of a type different from any evaluated previously, and do not involve a significant reduction in a margin of safety, the amendments do not involve a significant hazards consideration, (2) ther e is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manner, and (3)'uch activities will be conducted in compliance with the Commission's regulations and,the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public, Dated:
September 2, 1982 Principal Contributor:
Walter Brooks
t t
UNITED STATES NUCLEAR REGULATORY COMMISSION 7590-01 DOCKET NOS.
50-315'AND 50-316 INDIANA AND MICHIGAN ELECTRIC COMPANY NOTICE OF ISSUANCE OF AMENDMENTS'TO FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Conmission (the Commission) has issued Amendment No.
57 to Facility Operating License No. DPR-58, and Amendment No.
41 to Facility Operating License No.
DPR-74 issued to Indiana and Michigan Electric Company (the licensee),
which revised Technical Specifications for operation of Donald C.
Cook Nuclear Plant, Unit Nos.
1 and 2 (the facilities) located in Berrien County, Michigan.
The amendments are effective as o$ the date of issuance.
The amendments revised the Technical Specifications to permit storage of Exxon fuel with a uranium enrichment of less than or equal to 3.84 weig'ht percent of U-235.
The application for the amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the 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 amendments.
Prior public notice of these amendments was not required since the amendments do not involve a significant hazards consideration.
The Commission has determined that the issuance of these amendments 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 enviornmental impact appraisal need not be prepared in connection with issuance of these amendments.
For further details with respect to this action, see (1) the application for amendments dated April 7,1982, as supplemented by letters dated June 11,
- 1982, June 30, 1982, and July 8, 1982, (2) Amendment Nos.
57 and 41 to License Nos.
DPR-58 and DPR-74, and (3). the Commission's related Safety 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.
and at the Haude Reston Palenske Hemorial Library, 500 Market Street, St.
- Joseph, Michigan 49085.
A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, I
\\ f D.C.
20555, Attention:
Dir ector, Division of Licensing.
Dated at Bethesda, Haryland, this 2nd day of September, 1982.
FO E NUCL AR GULATORY COMMISSION ven A.
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