ML20087B197
| ML20087B197 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/24/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20087B190 | List: |
| References | |
| NUDOCS 9201130028 | |
| Download: ML20087B197 (3) | |
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'o, UNI (ED STATES NUCLEAR REGULATOriY COMMIStlON r,,
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 54 TO FACILITY OPERATING LICENSE NO. NPF-42 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482
1.0 INTRODUCTION
By applic6 tion dated February 27, 1991, as supplemented by letter dated September 11, 1991, Wolf Creek Nuclear Operating Corporation.(the licensee) requestedchangestotheTechnicalSpecifications(AppendixAtoFacility Operating License No. NPF-42) for the Wolf Creek Generating Station. The proposed changes would revise Section 6.0 to reflect miscellaneous changes to the administrative controls at the Wolf Creek Generating Station. The September 11, 1991, letter provided clarifying information and minor editorial chenges to the proposed Technical Specification revisions that did not change the initial proposed no significant hazards consideration determination.
2.0 EVALUATION The licensee has made a number of proposed changes to the administrative section of the Technical Specifications. The changes will be discussed sepa rately, The title of the Operations Supervisor found in Section 6.2.2.g is p
being changed to Supervisor Operations. This is being done to maintain consistency with the individual's actual title.
Since this change is administrative in nature, the staff finds this proposed change acceptable.
Section 6.2.2.g currently requires the Su Operations Supervisor as ducussed above)pervisor Operations (formerly to hold a senior-reactor operator (SRO) license. The licensee-proposes to expand this to permit either the Supervisor Operations or the Manager Operations to hold an-SR0 license. The stated " pose of this change is to provide organi-zational flexibility during the licensed operator requalification examination process. Since the proposed change will continue to provide a licensed SRO for supervision of the operating shif t crews, the staff
-finds this change acceptable.
Section 6.1.2 states that the Supervising Operator, under the Shift Supervisor, shall be responsible for the control room comand function.
Table 6.2-1, Minimum Shift Crew Composition, currently makes an improper reference to the Shift Supervisor (SS) as having control room 9201130025 711224 FDR ADOCK 050004S2 P
i 1 comand function. The licensee has proposed correcting this condition by replacing references to the SS under Table 6.2-1 with the Supervising Operator. Since the proposed change corrects an improper reference and does not change the lines of authority, the staff finds this change acceptable.
At the Wolf Creek facility, the SS typically assumes the dual role of SR0/ Shift Technical Advisor.
In addition, the designated SR0 of Table 6.2-1, also serves as the Supervising Operator. This leaves the SS and Supervising Operator as the minimum SR0s on shift.
Table 6.2-1 states that when the Supervising Operator (formerly SS as discussed above) leaves the control room, "an individual (other than the Shift Technical Advisor) with a valid Senior Operator license shall be designated to assume the control room command function." With the SS assuming the dual role of SR0/ Shift Technical Advisor, the above quoted parenthetical phrase would prohibit this individual (i.e., the only remaining SR0 on duty) from isstaing the control room command function. Therefore, the licensee has proposed to delete the parenthetical phrase "(other than the Shift Technical Advisor)." Since this change clarifies an inconsistency within the Technical Specifications and does not preclude an SRO from assuming the control room comand function, the staff finds this acceptable.
On March 25, 1987, 10 CFR Part 55 was amended to upgrade requirements for licensed operator selection, training and requalification.
S t.b-sequently, the NRC issued Revision 2 to Regulatory Guide 1.8, 'Quali-i fication and Training of Personnel for Nuclear Power Plants," which provides a method acceptable to the NRC staff for complying with 10 CFR Part 55. The requirements of 10 CFR Part 55 are more restrictive than Sections A and C of the enclosure to the March 18, 1980 NRC letter to all licensees currently listed in Sections 6.3 and 6 4 of the Tech-nical Specifications. The licensee has proposed replacing the references to the March 18, lid 0 letter with Revision 2 to Regulatory Guide 1.8.
The proposed requirements are more restrictive than the current Technical Specification requirements and they address the requirements of 10 CFR Part 55. Therefore, the staff finda the proposed changes to Sections 6.3 and 6.4 acceptable.
3.0 STATE CONSULTATION
in accordance with the Commission's regulations, the Kansas State official was i
notified of the proposed issuance of the amendment. The State official had i
no connents.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment relates to changas in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
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5.0 CONCLUSION
The Consnission has concluded, based on the_ considerations discussed above, that:. (1) there is reascnable 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 Connission's regulations, and (3) the issuance of the amendn.ent will not be inimical-to the connon defense and security.or to the health and safety of the public.
Principal Contributor: Douglas V. Pickett, PDIV-2/NRR' Date:
December 24, 1991
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