ML20035F946
| ML20035F946 | |
| Person / Time | |
|---|---|
| Site: | Perry |
| Issue date: | 04/16/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035F943 | List: |
| References | |
| NUDOCS 9304230107 | |
| Download: ML20035F946 (3) | |
Text
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UNITED STATES i
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WASHINGTON. D.C. 2055541001 N.v....f SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 47 TO FACILITY OPERATING LICENSE NO. NPF-58 THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.
PERRY NUCLEAR POWER PLANT. UNIT NO. 1 DOCKET NO. 50-440
1.0 INTRODUCTION
By letter dated February 26, 1993, the Clevelend Electric Illuminating Company (CEI) and Centerior Service Company submitted a request for a change to the Perry Nuclear Power Plant, Unit 1 Technical Specifications (TS).
The requested amendment would allow temporary relief from the requirements of Administrative Controls Technical Specification Section 6.3.1, " Unit Staff Qualifications," to permit a specific individual to assume the active duties t
of Manager, Perry Operations Section, within the Perry Nuclear Power Plant Department (PNPPD), without currently holding a Senior Reactor Operator (SRO) license on PNPP, Unit 1.
The temporary relief was requested for a limited period of time during which the SR0 license qualification would be met.
2.0 EVALUATION Regulatory Guide (RG) 1.8, Revision 1-R, endorses, with exception, the criteria for selection and training of the nuclear power plant personnel contained in ANSI N18.1-1971, " Selection and Training of Nuclear Power Plant t
Personnel. " ANSI Standard N18.1-1971 states that the Operations Manager shall hold an SR0 license at the time of appointment to the position.
PNPP TS 6.3.1 states, in part, that each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions.
PNPP Updated Safety Analysis Report, Table 13.1-1 lists the equivalent Perry staff titles to the ANSI N18.1-1971 positions. Table 13.1-1 lists both the Manager, Operations Section and the Superintendent, Plant Operations as equivalent ANSI N18.1-1971 Operations Manager positions, although the footnote to the table denotes the Manager, Operations Section as the position that fills the ANSI N18.1-1971 position with additional staff positions and ANSI equivalents, which identify the depth and qualifications of the Perry staff. The Superintendent, Plant Operations satisfies all the ANSI N18.1-1971 qualification requirements for the position of Operations Manager (including the SR0 license requirement), reports directly to the Manager, Operations Section, provides direct supervision of the Shift Supervisors and is available to assist the Manager, Perry Operations Section, on an as-needed basis.
9304230107 930415 PDR ADOCK 05000440 P
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The staff has reviewed the proposed TS change, which adds a one-time exception i
to the requirement for the Manager, Perry Operations Section to hold an SR0 license until issuance of an SR0 License upon completion of the August 1995 license examination based on the following criteria:
(1)
The qualifications of the individual selected for the Manager, Perry f
Operations Section position reflect the experience described in ANSI-N18.1-1971 for such a managerial position. The individual has over 17 years commercial nuclear power plant experience and has held SRO licenses on both Davis-Besse Nuclear Power Station and Three Mile Island Unit 1 Nuclear Power Station.
(2)
The individual will be included in the.next scheduled Senior Reactor Operator / Reactor Operator training and examination program currently scheduled to begin in June 1994 and will sit for the next scheduled SR0 license examination scheduled for August 1995.
(3)
The individual will receive PNPP specific Boiling Water Reactor (BWR) technology training as soon as practicable following appointment to the position of Manager, Perry Operations Section.
I Based on the above criteria, the staff has determined that the licensee's proposed change to the PNPP TS is acceptable. The licensee has provided adequate justification with consideration to potential safety-significance for such a change.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Ohio State official _was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change in 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 needs to be prepared in connection with the issuance of the amendment.
5.0 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
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, activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
B. Wetzel Date: April 16,1993 i
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