ML20127E352
| ML20127E352 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 01/07/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127E330 | List: |
| References | |
| NUDOCS 9301190261 | |
| Download: ML20127E352 (3) | |
Text
UNITED STATES
[, g- 'i NUCLE AR REGULATORY COMMISSION g
t WASHINGTON, D. C. 20555
- %[..h4,$
SAFETY EVALUATION BY THE 0FFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.157 TO FACILITY OPERATINC LICENSE NO. DPR-46 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO.50-29J
1.0 INTRODUCTION
By letter dated May 4,1992, Nebraska Public Power District (the licensee) submitted a request for changes to the Cooper Nuclear Station Technical Specifications (TS).
The requested changes would remove the TS tables that include list of components referenced in individual specifications.
In cddltion, the TS requirements have been modified to remove all references to thess tables.
Finally, the TS have been modified to state requirements in general teret that include components listed in the tables removed from the TS. Guid uce os the proposed TS changes was provided by NRC Generic Letter (GL) 408, Woaon1 of Component Lists from Technical Specifications," dated my G.,
1991.
2.0 EVALVATIOJ The licenset has proposed the removal of Table 3.7.2, " Testable Penetrations with Double G-Ring Seals," and to revise TS 4.7.A.2.f.1 and TS 4.7.A.2.f.2 to remove references to Table 3.7.2.
The licensee has also proposed the removal of Table 3.7.3, " Testable Penetrations with Testable Bellows," as well as to revise TS 4.7. A.2.f.1 and TS 4.7. A.2.f.4 to remove references to Table 3.7.3.
In addition, the licensee has also proposed the removal of Table 3.7.4,
" Primary Containment Testable Isolation Valves," and to revise TS 4.7. A.2.f.1 to remove referencns to Table 3.7.4.
With the removal of the Table of primary containment testable isolation valves, the operability requirements have been stated in general terms that apply to all containment isolation valves including those that are closed or locked closed. These valves are locked or sealed closed consistent with the regulatory requirements for manually-operated valves that are used as containment isolation valves.
Because opening these valves would be contrary to the operability requirements of these valves, the following footnote to the Limiting Condition for Operation under TS 3.7,0.2 has beer p.oposed:
Isolation valves closed to satisfy these requirements may be reopened on an intermittent basis under administrative control.
9301190261 930107 PDR ADOCK 05000298 P
l l
. With the removal of Table 3.7.4, the licensee has proposed to add a new surveillance requirement, TS 4.7,0.1.d.
This new specification was a footnote to Table 3.7.4, which discusses the surveillance requirements for devices installed to limit the opening angle of certain containment isolation valves.
The new surveillance requirement will state as follows:
At least once per operating cycle while shutdown, the devices that limit the maximum opening angle to 60* shall be verified functional for the following valves:
PC-230MV, PC-231HV, PC-232MV, and PC-233MV.
Although GL 91-08 would allow its removal, the licensee has elected to retain Table 3.7.1, " Primary Containment Isolation Valves," in the TS.
However, the licensee has proposed corrections to Table 3.7.1.
Specifically, corrections are proposed for the component identification code (CIC) numbers for the reactor water sample valves and the CIC numbers for the air containment atmosphere dilution (ACAD) valves to indicate they are listed as primary containment valves.
Bo.;use Table 3.7.1 will remain, TS 3.7.D will continue to state as follows:
During reactor power operating conditions, all isolation valves listed in Table 3.7.1 and all instrument line flow check valves shall be operable except as specified in 3.7.D.2.
The licensee has proposed changes to the above TS that are consistent with the guidance provided in GL 91-08.
In addition, the licensee has confirmed that component lists removed from the TS have been updated to identify all components to which the TS requirements apply and are located in controlled plant procedures.
On the basis of its review of this matter, the NRC staff finds that the proposed changes to the TS for Cooper Nuclear Station are primarily administrative and do not alter the requirements set forth in the existing TS.
Overall, these changes will allow the licensee to make corrections and updates to the lists of components to which these TS requirements apply, under the provisions that control changes to plant procedures as specified in the Administrative Controls Section of the TS.
Therefore, the staff finds that the proposed TS changes are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Nebraska State official was notified of the proposed issuance of the amendment.
The State official had no comment.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to a surveillance requirement.
The staff has determined that the amendment involves no significant increase in the amounts, 1
s 4.
1 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 &
proposed finding that this' amendment involves no significant hazards consideration e,J there has been no public comment on such. finding.
Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) (57 FR 30252).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need -
be prepared in connection with the. issuance of this amendment.
5.0 CONCLUSION
The Commission 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 amendment will not be inimical to the common -
defense and security or to the health and safety of the public.
Principal Contributor:
C. Yates Date:
January 7, 1993
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