ML17332A899
| ML17332A899 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/22/1995 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17229B435 | List: |
| References | |
| NUDOCS 9508290266 | |
| Download: ML17332A899 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO.
DPR-58 AND AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO.
DPR-74 INDIANA MICHIGAN POWER COMPANY DONALD C.
COOK NUCLEAR PLANT UNIT NOS.
1 AND 2 DOCKET NOS. 50-315 AND 50-316
1.0 INTRODUCTION
The NRC issued Generic Letter (GL) 90-02, "Alternative Requirements for Fuel Assemblies in Design Features Section of Technical Specifications,"
on February 1,
1990, to propose a line-item improvement to plant Technical Specifications (TS) by providing alternate requirements for fuel assemblies in the design features section of the TS.
The GL states that, on a plant-specific basis, "the staff has approved changes to these requirements that provide flexibi'Iity for improved fuel performance by permitting timely removal of fuel rods that are found to be leaking during a refueling outage or are determined to be probable sources of future leakage."
The NRC issued Supplement 1 to GL 90-02 on July 31, 1992, to clarify the limitations on the application of NRC-approved analytical methods related to fuel assembly reconstitution.
Supplement 1 also withdrew and replaced the model TS recommended in the initial GL 90-02 to be consistent with realistic reconstitution configurations.
The model TS change in GL 90-02, Supplement 1,
is also reflected in NUREG-1431, "Westinghouse Standard Technical Specifications Westinghouse Plants,"
September
- 1992, the improved Standard Technical Specifications (iSTS).
By letter dated May 25, 1995, the Indiana Michigan Power Company (the licensee) requested amendments to the Technical Specifications (TS) 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 amendments would allow fuel reconstitution in accordance with NRC-approved methodologies.
The reconstitutions may be performed under the provisions of 10 CFR 50.59 provided that the required safety analyses are performed with NRC staff-approved methodologies, which are applied to assembly configurations that lie within the scope of the reviewed fuel lattice configurations.
The'icensee supplemented the requested amendments on June 30, 1995, to propose TS wording which more completely followed the guidance in the NRC GL.
The June 30 supplement was within the scope of the original application and did not affect the staff's initial proposed no significant hazards considerations determination.
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- 2. 0 EVALUATION The proposed amendments would modify TS Section 5.3. 1, "Fuel Assemblies," to allow "limited substitutions of zirconium alloy or stainless steel filler rods, in accordance with NRC-approved applications of fuel rod configurations."
The licensee states that any reconstitution performed will be done in accordance with an already approved methodology, or a specific methodology will be submitted for NRC approval.
The licensee repeated in its submittal the staff definition of an NRC-approved methodology as provided in GL 90-02, Supplement 1:
The staff considers an NRC-approved methodology to be any methodology that the NRC staff has explicitly approved in a written safety evaluation or a plant-specific technical bases.
That NRC-approved methodology must be used only for the purpose and the scope of applications specified in the reviewed document as approved or modified in the NRC approval documentation.
The licensee's submittal is consistent with the wording proposed in NRC Generic Letter 90-02, supplement 1 and incorporated into the iSTS.
The proposed change would allow the licensee to perform fuel reconstitution only as allowed by methodologies previously approved by the NRC.
Therefore, the change only obviates the need for a TS amendment every time leaking or potentially leaking fuel is identified.
The definition of an NRC-approved methodology as provided in GL 90-02, Supplement 1,
and reiterated by the licensee assures that the proposed reconstitution has been adequately reviewed by the staff prior to implementation.
In addition, the change requires the licensee to show by tests or analyses that the reconstituted fuel assemblies comply with all fuel safety design bases.
While the licensee may place lead test assemblies that have not completed representative testing in non-limiting core regions, the proposed change allows this only in non-limiting core regions (i.e., where the lead test assembly does not become the assembly with least thermal margin to either the Departure from Nucleate Boiling or Linear Heat Generation Rate design limits at any time during its cycle life) and where analyses, using NRC approved methodologies, show that these assemblies comply with all fuel safety design bases.
Based on the above, the staff finds the proposed changes to be acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendments.
The State official had no comments.
- 4. 0 ENVIRONMENTAL CONSIDERATION The amendments change the requirements with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation
exposure.
The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration and there has been no public comment on such finding (60 FR 35081).
Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
5.0 CONCLUSION
The staff has 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, (2) such activities will be conducted in compliance with the Commission's regulations and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public Principal Contributor:
John Hickman Date:
August 22, 1995
Pi DATED.
August 22, 1995'l AMENDMENT'O. 199 TO j'QCILIT'( OPERATING LICENSE NO. DPR-58-D.
C.
COOK-UNIT I AMENDMENT NO.
184 TO FACILITY OPERATING LICENSE NO. DPR-74-D.
C.
COOK-UNIT 2 i
Docket File PUBLIC PDI II-I Reading E.
Adensam (e-mail )-
J.
Hannon C. Carpenter C. Jamerson J.
Hickman (2)
OGC G. Hil.l, IRH (4)
C. Grimes, 0-llF23 R.
C. Jones, Jr.
ACRS (4)
W. Kropp, RIII SEDB (e-mail) 1
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