ML20093H705
| ML20093H705 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/12/1995 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20093H686 | List: |
| References | |
| NUDOCS 9510200305 | |
| Download: ML20093H705 (2) | |
Text
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-1 UNITED STATES i
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' NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D.C. 30eeH001 f
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS.164 AND 168 T0 i
FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 WISCONSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT. UNIT NOS. 1 AND 2 j.
DOCKET NOS. 50-266 AND 50-301
1.0 INTRODUCTION
i By letter dated April 17, 1995, the Wisconsin Electric Power Company, the 4
licensee, submitted a request for revision to the Point Beach Nuclear Plant (PBNP), Units 1 and 2, Technical Specifications (TS). This submittal would a
l modify TS Section 15.6.2, " Organization," and TS Section 15.6.3, " Facility Staff Qualifications." The requirement for the Operations Manager to hold a an NRC Senior Reactor Operator's (SRO) license would be changed to provide 1
additional staffing flexibility.
2.0 BACKGROUND
PBNP TS 15.6.3.1 currently requires each member of the facility staff to meet or exceed the minimum qualifications of the American National Standards Institute (ANSI) N18.1-1971, "American National Standard for Selection and Training of Nuclear Power Plant Personnel," for comparable positions or as clarified in subsequent TS.
Section 4.2.2 of ANSI N18.1-1971 specifies that "At the time of initial core loading or appointment to the active position the operations manager shall hold a Senior Reactor Operator's License."
ANSI /ANS-3.1-1987, "American National Standard for Selection, Qualification and Training of Personnel for Nuclear Power Plants," expanded the requirements for Operations Manager by stating that the Operations Manager shall either hold an SRO license, have held an SRO license for a similar unit, or be certified as qualified by other criteria. ANSI /ANS-3.1-1987 also states that "If the Operations Manager does not hold an NRC license, the Operations Middle Manager shall hold an NRC Senior Operator's License."
3.0 EVALUATION In order to allow additional flexibility within the'0perations organization, the licensee's proposal incorporates the expanded requirements of ANSI /ANS-3.1-1987 for the position of Operations Manager. Specifically the licensee's proposal would:
9510200305 951012 PDR ADOCK 05000266 p
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Delete TS 16.2.2.g which states that "The Operations Manager shall hold a senior reactor operator license."
2.
Add a new TS 15.6.3.5 which states that "The Operations Manager shall:
- 1) Hold a Senior Reactor Operator license at PBNP; or
- 2) Have held a Senior Reactor Operator license at PBNP or a similar l
unit; or 3) Have been certified at an appropriate simulator for equivalent senior operator knowledge level."
"If the Operations Manager does not hold a Senior Reactor Operator license at PBNP, then an operations middle manager to whom the
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operating crews report shall hold a Senior Reactor Operator license at PBNP."
The staff has reviewed the licensee's proposed changes and determined that they are consistent with the requirements of ANSI /ANS-3.1-1987, Regulatory Guide 1.8, Revision 2, and NUREG-0800, the Standard Review Plan.
Additionally, by specifying that an individual in one of the operations management positions hold an SRO license, the licensee ensures that operations
-management has site-specific, detailed, and relevant technical and systems knowledge. The staff, therefore, finds these proposed changes acceptable.
4.0 STATE CONSULTATION
In accordance with the Comission's regulations, the Wisconsin State official was notified of the proposed issuance of the amendment. The State official had no coments.
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5.0 ENVIRONMENTAL CONSIDERATION
f This amendment changes recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria i
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 this amendment.
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6.0 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 j
activities will be conducted in compliance with the Comission's regulations, i
and (3) the issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public.
Principal Contributor:
R. Laufer Date: October 12, 1995 l
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