ML20064M733
| ML20064M733 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/21/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064M727 | List: |
| References | |
| NUDOCS 9403280355 | |
| Download: ML20064M733 (3) | |
Text
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t UNITED STATES i 'lW 3
NUCLEAR REGULATORY COMMISSION i!
WASHINGTON, D.C. 20665-0001
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SAFETY EVALUATION BY THE OFFICE OF NQ LEAR R~ ACTOR REGULATIO.]
RELATED TO AMENDMENT NO. 114 TO FACILITY OPERATING LICENSE NPF-35 AND AMENDMENT NO.108 TO FACILITY OPERATING LICENSE NPF-ji2 DUKE POWER COMPANY. ET AL.
[ATAWBA NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414
1.0 INTRODUCTION
By letter dated January 18, 1994 as supplemented March 8, 1994, Duke Power Company, et al. (the liceasee), submitted a request for changes to the Catawba Nuclear Station, Units 1 and 2, Technical Specifications (TS). The requested ch ages would revise TS 3/4.8.4 to allow the transfer of the contents of TS Tables 3.8-1A and 3.8-18, " Containment Penetration Conductor Overcurrent Protective Devices," for Unit-I and 2, respectively, from the TS to the Selected Licensee Commitments Manual located in Section 16 of the Final Safety Analysis Report) in accordance with the guidance contained in Generic Letter 91-08, " Removal of Component Lists From Technical Specifications." The March 8,1994, letter provided clarifying information that did not change the scope of the January 18, 1994, applic tion and the initial proposed no significant hazards consideration determination.
2.0 EVALUATION The licensee has proposed to remove Table 3.8-1A for Unit 1 and Table 3.8-1B for Unit 2, that are referenced in TS 3/4.8.4, and has proposed to include the following statement for the Limiting Condition for Operation under TS 3.8.4:
Primary and backup containment penetration conductor overcurrent protective device associated with each containment electrical penetration circuit shall be OPERABLE. The scope of these protective devices excludes those circuits for which credible fault currents would not exceed the electrical penetration design rating.
In addition, the licensee has proposed to revise TS 4.8.4 to remove the reference to Tables 3.8-1A and 3.8-18.
The surveillance requirement has been revised to state the fcl!owing:
The above noted primary and backup containment penetration conductor overcurrent protective devices shall be demonstrated OPERABLE:
i 9403280355 940321 PDR ADOCK 05000413 P
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o The licensee has proposed changes to the above TS that are consistent with the guidance provided in Generic Letter 91-08.
In addition, the licensee has provided an updated copy of Bases Section of TS 3/4.8.4.
The licensee has identified that for the devices previously listed in TS Tables 3.8-1A and 3.8-18, corresponding information is also contained in three plant procedures (IP/0/B4971/21 IP/0/B/4971/20, and IP/l&2/A/3530/03) that are subject to the administrative controls provisions of TS 6.8.
The licensee has also committed that these lists of components will also be maintained in a current status in Section 16 of the Catawba Final Safety Analysis Report, Selected Licensee Commitments Manual.
On the basis of its review of this matter, the staff finds that the proposed changes to the TS for the Catawba Nuclear Station, Units 1 and 2, are primarily administrative changes that do not alter the requirements set forth in the existing TS.
Overall, these changes will allow licensees to make corrections and updates to the list of components for 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 South Carolina State official was notified of the proposed issuance of the amendments.
The State of ficial had no comments.
4.0 ENVIRONMENTAL CONSIERAUQN The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements.
The NRC 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 ir. crease 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 (59 FR 7688 dated February 16, 1994). 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 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
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. 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 Contributors:
T. Dunnin9 R. Martin Date:
Kirch 21,1994 e