ML18010B113
| ML18010B113 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 06/11/1993 |
| From: | Thomas Farnholtz Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18010B112 | List: |
| References | |
| NUDOCS 9306170415 | |
| Download: ML18010B113 (8) | |
Text
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UNITED STATES I
NUCI.EAR REGULATORY COMMISSION WASHINGTON, D.C. 20555.0001 SAFET EVA UATION BY THE OFFICE OF UCLEAR REACTOR REGULATION R
L ED TO A ENDMENT NO.
37 TO F CILITY OPERATING LICENSE NO.
NPF-63 CAROLINA POWER
& LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1
DOCKET NO. 50-400
- 1. 0 INTRODUCTION By letter dated March 4, 1993, the Carolina Power
& Light Company (the licensee) submitted a request for changes to the Shearon Harris Nuclear Power Plant, Unit 1, Technical Specifications (TS).
The requested changes would allow the training program for licensed personnel to be based on a systematic approach to training.
In response to Generic Letter 87-07, the licensee, in a letter dated,May 24, 1988, stated that their initial and requalification training programs for operators were accredited and based on a systematic approach to training.
The Final Safety Analysis Report (FSAR) was revised accordingly.
This proposed change is a follow-up that would revise the TS to be consistent with the FSAR.
2.0 PROPOSED TECHNICAL SPECIFICATION CHANGES TS 6.4 is being revised to require that the initial and requalification training for licensed personnel is through an accredited program based on the systematic
- approach, as allowed by 10 CFR 55.31, 10 CFR 55.59, and Generic Letter 87-07.
- 3. 0 EVALUATION This is a follow-up request which proposes changes to the TS that would make the TS consistent with the previously revised FSAR in the area of licensed operator initial and requalification training.
The change is permitted by NUREG-1262, "Answers to guestions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators'icenses,"
dated November 1, 1987.
guestion No. 98, Page 23 states that "[there] are a
number of facilities that have a more restrictive requirement in their Technical Specifications than that for which they would have to apply; amending their Technical Specifications to obtain relief is permitted under the rule.
It would be an administrative change in order to conform with the regulation."
Therefore, the staff finds the proposed change acceptable.
4.0 STATE CONSU T TIO In accordance with the Commission's regulations, the North Carolina State official was notified of the proposed issuance of the amendments.
The State official had no-comment.
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ADMINISTRATIVE CON LS
- 6. 4 TRAINING 6.4. 1 A retraining and replacement training program for the unit staff shall be maintained and shall meet or exceed the requirements and recommendations of the September 1979 draft of ANS 3. 1, with the exceptions and alternatives noted in Section 1.8 (Personnel Selection and Training) of the FSAR.
The initial and requalification training for licensed personnel is through an accredited program based on the systematic approach to training, as allowed by 10 CFR 55.31, 10 CFR 55.59, and Generic Letter 87-07.
- 6. 5 REVIEW AND AUDIT 6.5.1 SAFETY AND TECHNICAL REVIEWS 6.5. 1. 1 General Pro ram Control 6.5. 1. 1. 1 A safety and a technical evaluation shall be prepared for each of the following:
a.
All procedures and programs required by Specification 6.8, other procedures that affect nuclear safety, and changes thereto; b.
All proposed tests and experiments that are not described in the Final Safety Analysis Report; and c.
All proposed changes or modifications to plant systems or equipment that affect nuclear safety.
6.5. 1.2 Technical Evaluations 6.5. 1.2. 1 Technical evaluations will be performed by personnel qualified in the subject matter and will determine the technical adequacy and accuracy of the proposed activity. If interdisciplinary evaluations are required to cover the technical scope of an activity, they will be performed.
6.5. 1.2.2 Technical review personnel will be identified by the responsible Manager or his designee for a specific activity when the review process begins.
6.5. 1.3 uglified Safet Reviewers 6.5. 1.3.1 The Plant General Hanager shall designate those individuals who will be responsible for performing safety reviews described in Specification 6.5. 1.4.
SHEARON HARRIS - UNIT 1 6-7 Amendment No. 37
0
ATTACHMENT TO LICENSE AMENDMENT NO. 37 FACILITY OPERATING LICENSE NO.
NPF-63 DOCKET NO. 50-400 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised areas are indicated by marginal lines.
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- 5. 0 ENVIRONMENTAL CONSIDERATIONS This amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements.
Accordingly, this 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 this amendment.
- 6. 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 these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
T. Farnholtz Date:
June ll, 1993
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