ML20096F241

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Safety Evaluation Supporting Amends 157 & 139 to Licenses NPF-4 & NPF-7,respectively
ML20096F241
Person / Time
Site: North Anna  
Issue date: 05/06/1992
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20096F239 List:
References
NUDOCS 9205200308
Download: ML20096F241 (3)


Text

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,i NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20656

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 157 AND 139 TO FACILITY OPERATING LICENSE NOS. NPF-4 AND NPF-7 VIRGINIt ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE NORTH ANNA POWER STATION. UNITS NO. 1 AND NO. 2.

DOCKET NOS. 50-338 AND 50-339 1.0 it{JRODUCTION By letter dated November 7, 1991, the Virginia Electric and Power Com)any (the licensee) proposed changes to the Technical Specifications (TS) for tie North Anna Power Station, Units No. 1 & No. 2 (NA-1&d). The proposed TS changes would remove language describing, or committing to, any previous operator training programs to reflect the fact that the training programs at NA-1&2 have been accredited and developed using a systems approach to training (SAT) in accordance with Generic Letter (GL) 87-07, "Information Transmittal of Final Rulemaking for Revisions to Operator Licensing - 10 CFR 55 and Conferming Amendments." These changes would also delete reference to the

-March 28, 1980 NRC letter and substitute the licensee's SAT-based accredited training programs.

2.0 DISCUSSION NA-1&2-received accreditation for initial and requalification training of licensed operators and senior operators on October 24, 1985. Accreditation for the Shift Technical Advisor Training Program was received on August 26, 1987.

GL 87-07 requires written notification from the licensee that the substitute programs are accredited and, in the case of the requalification training program, certified to be based on SAT. Written notification of the accreditation of the NA-1&2 operator training programs was made to the NRC in accordance with GL 87-07 by the licensee's letter dated March 20, 1989.

3.0 Technical Specification Chanaes The changes described below are strictly administrative in nature and consistent with the guidance in NUREG-1262.

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IS 6.3.1 This TS would delete the reference to the March 28, 1980 NRC letter and substitute the raquirements of 10 CFR Part 55.59(c) and Part 55.31(a)(4) for the previous licensed ope"ator, senior operator and Shift Technical Advisor training rec.atrements.

The March 28, 1980 NRC letter is made obsolete by the implemente, ion of the proposed accredited and certified training program per GL 87-01.

TS 6.4.1 This TS would be modified to redefine the responsibilities of the Manager-Nuclear Training. As a result, the responsibility for ensuring retraining and replacement programs will meet or exceed the requirements of 10 CFR Part 55.59(c) and Part 55.31(a)(4) would be added to this TS.

Section 5 of ANS 3.1 - (12/79 Draft) is still required for replacement and retraining prog)ams for non-licensed facility staff.

In addition, a footnote would be added to reference any exceptions that the QA Topical Report may take from ANS 3.1.

4.0 EVALUATION The proposed changes would remove language describing, or committing to, any previous operator training programs since the training programs at NA-l&2 have been accredited and certified in accordance with GL 87-07, "Information Transmittal of Final Rulemaking for Revisions to Operator Licensing - 10 CFR 55 and Conforming Amendments." The proposed changes delete reference to the March 28, 1980 NRC letter and substitute the licensee's training programs (including Shift Supervisor, Assistant Shift Supervisor, Control Room Operator

- Nuclear, and Shift Technical Advisor) for the previous training requirements.

The NA-1&2 training programs are accredited and certified as permitted by GL 87-07. Therefore, the staff finds the TS changes to be acceptable.

5.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Virginia State official was notified of the proposed issuance of the amendments.

The State official had no comment.

6.0 ENVIRONMENTAL CONSIDERATION

These amendments relate to changes in recordkeeping, reporting or administra-tive procedures or requirements.

Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).

Pursuant to 10 CFR 51.229), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

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7.0 CONCLUSION

The Comission 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 Comission's regulations, and (3) the issuance of the amendments will not be inimical to the comon defense and security or to the health and safety of the public.

Principal Contributor:

Leon B. Engle Date:

Pay 6,1992


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