ML20059F203
| ML20059F203 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 01/03/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059F201 | List: |
| References | |
| NUDOCS 9401130195 | |
| Download: ML20059F203 (3) | |
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t SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 70 TO FACILITY OPERATING LICENSE NO. NPF-42 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482
1.0 INTRODUCTION
By application dated October 21, 1993, Wolf Creek Nuclear Operating Corporation (the licensee) requested changes to the Technical Specifications (Appendix A to facility Operating License No. NPF-42) for the Wolf Creek Generating Station. The proposed changes would revise Technical Specification 6.3.1 related to the qualification requirements for the position of Manager Operations and Technical Specification 6.5.1.2 related to the required composition of the Plant Safety Review Committee (PSRC).
Technical Specification 6.3.1 has required members of the unit staff to meet or exceed the minimum qualifications of ANSI /ANS 3.1-1978, "American National Standard for Selection and Training of Nuclear Power Plant Personnel." The proposed change would revise the Manager Operations qualification requirements from those listed in the standard (holding a senior reactor operator license) to requiring that the Manager Operations shall hold or have previously held a senior operator license for a similar unit.
The revision to Technical Specification 6.5.1.2 involves replacement of the description of PSRC membership from a list of specific position titles to management responsible for various areas of expertise.
2.0 EVALUATION Technical Specification 6.3.1 currently requires members of the licensee's staff to meet or exceed the minimum qualifications of ANSI /ANS 3.1-1978, "American National Standard for Selection and Training of Nuclear Power Plant Personnel." ANSI /ANS 3.1-1978 Section 4.2.2 requires that at the time of initial core loading or appointment to the position, whichever is later, the operations manager shall hold a senior reactor operator license.
The 1987 revision of ANSI /ANS 3.1 introduced additional flexibility by allowing the operations manager to hold a senior operator license, have held a senior operator license for a similar unit, or be certified as qualified by use of other criteria. ANSI /ANS 3.1-1987 also states that if the operations manager does not hold an NRC license, then the operations middle manager shall hold a senior reactor operator license.
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Section 50.54(1) of Title 10 of the Code of Federal Regulations states those individuals responsible for directing the licensed activities of licensed operators shall be licensed as senior operators.
In the case of Wolf Creek's current organization, this requires that the management level above the shift supervisors, the Supervisor Operations, hold a senior operator license.
The licensee stated that in times of transition, when the Supervisor Operations position might be vacated, qualified personnel with a senior operator license would be available to fill the position.
Technical Specification 6.2.2(g),
which states that either the Supervisor Operations or Manager Operations shall-hold a senior reactor operator license, would also ensure that the control room staff would continue to be supervised by a person with a senior operator license.
The proposed revision to Technical Specification 6.3.1 consists of adding an-item (d) to the list of exceptions to the unit staff meeting the requirements of ANSI /ANS 3.1-1978.
The proposed item (d) requires that the Manager Operations hold or have previously held a senior operator license for a similar unit (pressurized water reactor [PWR]).
The licensee has stated that the Updated Safety Analysis Report (USAR) will be revised to reflect this change in commitment related to ANSI /ANS 3.1-1978.
The staff finds that the proposed Technical Specification 6.3.1 meets the relevant criteria in Standard Review Plan (SRP) Section 13.1.2-13.1.3,
" Operating Organization" and 10 CFR 50.54 and is, therefore, acceptable.
l The proposed change to Technical Specification 6.5.1.2, PSRC Composition, involves the replacement of a list of specific position titles with a paragraph describing the members as managers responsible for various areas of expertise.
The required membership for the PSRC is reduced from the ten l
specific positions listed in the current Technical Specification to a proposed minimum of eight members comprised of the Chairman, designated by the Vice President Plant Operations, six members appointed by the chairman, and a member to be designated by the Vice President Engineering.
The selected members are required to include management responsible for operaticns, maintenance, instrumentation and controls, chemistry, health physics, and engineering.
The proposed change to delete specific title designations from the technical specifications provides flexibility in appointment of members and also eliminates the need for amendment requests as a result of title changes.
The replacement of the specific titles with functional areas ensures that the PSRC will provide interdisciplinary review of its subject matters.
Qualification of personnel is ensured by the technical specification requirements for unit staff, including the managers serving on the PSRC, to meet or exceed the qualification requirements of ANSI /ANS 3.1-1978. Other technical specifications related to the PSRC, such as meeting frequency, quorum requirements, review responsibilities, and record requirements are not affected by the proposed change.
The staff added a clarification to the licensee's proposed' change to Technical Specification 6.5.1.2.
The change consists of including a maximum number of ten PSRC members, including the Chairman, so that the quorum defined in Technical Specification 6.5.1.5, the~ Chairman and four members, continues to represent at least half of the committee.
The staff discussed this I
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clarification with the licensee and the licensee agreed to the staff's requested change. The change does not change the initial no significant hazards consideration determination published in the Federal Reaister on November 24, 1993.
The staff has reviewed the proposed change, as amended, and finds that the criteria of SRP Section 13.4 continue to be met.
The change is, therefore, acceptable.
3.0 STATE CONSULTATIQH In accordance with the Commission's regulations, the Kansas State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment relates to changes 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.
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:
W. D. Reckley Date: January 3, 1994 i