IR 05000369/1987007
| ML20207T720 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/06/1987 |
| From: | Belisle G, Runyan M, Shannon M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20207T709 | List: |
| References | |
| 50-369-87-07, 50-369-87-7, NUDOCS 8703240274 | |
| Download: ML20207T720 (4) | |
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F-M Moo 4 UNITE 3 STATES
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Do NUCLEAR REGULATORY COMMISSION
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REGION il n
g ij 101 MARIETTA STREET,N.W.
- e ATLANTA, GEORGI A 30323
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Report Nos.:
50-369/87-07 and 50-370/87-07 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos.:
50-369 and 50-370 License Nos.: NPF-9 and NPF-17 l
Facility Name: McGuire 1 and 2 Inspection Conducted:
February 17 - 20, 1987 Inspectors: ~/I /vY I /
/48 49/
M. Runyan
'Date Signed
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M. Shannon
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'Date Signed Approved by: N kN.
M d!67 G. A. Belisle, Chief 6 Da~te Signed
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Quality Assurance Programs Section Division of Reactor, Safety SUMMARY
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Scope:
This routine, unannounced inspection was conducted in the area of licensee action on previously identified inspection findings.
Results: No violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees M. Boatright, Technical Assistant III J. Crenshaw, Senior Engineer
- R. Gill, Licensing
- W. Houston, Project Manager, Nuclear
- J. Keirnaw, Design Engineering B. Lanier. Assistant Quality Assurance Engineer
- T. Mathews, Design Engineering
- S. McInnis, Compliance
- R. Medlin, Quality Assurance Engineer II
- R. Priors, Design Engineering V.P.
- R.' Weber, Nuclaar Projects NRC Resident Inspector S. Guenther
- Attended exit interview 2.
Exit Interview The inspection scope and details of the inspection were summarized on February 20, 1987, with those persons indicated in paragraph 1 above. The inspector described the items inspected and indicated that all seven items listed as inspector followup items would now be closed.
The following Inspector Followup Items were closed during this inspection, a.
369/85-09-01 and 370/85-10-01 b,
369/85-09-02 and 370/85-10-02 c.
369/85-09-03 and 370/85-10-03 d.
369/85-09-04 and 370/85-10-04 e.
369/85-09-05 and 370/85-10-05 f.
369/85-31-01 and 370/85-33-01 g.
369/84-33-01 and 370/84-30-01 These items are discussed in detail in the body of the report.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection.
3.
Licensee Action on Previous Enforcement Matters
This subject was not addressed in the inspection.
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4.
Unresolved Items
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Unresolved items were not identified during this inspection.
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Licensee Action On Previously Identified Inspection Findings (92701)
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(Closed) Inspector Followup Item 369/85-09-01 and 370/85-10-01:
Failure to Specify Post Modification Test Requirements and Acceptance Criteria The inspector reviewed the following licensee procedures:
i PR 160 Nuclear Station Modification, Revision 6 PR 101 Engineering Calculation / Analysis, Revision 9 II.4.2 Station Modifications, Revised 3-1-87 These procedures are sufficiently detailed to require that post modification test requirements and acceptance criteria are now included in the design change packages.
The revised procedures also give sufficiently detailed instructions for determining and i
documenting test requirements and acceptance criteria, b.
(Closed) Inspector Followup Item 369/85-09-02 and 370/85-10-02:
j Revision to Exempt Change Program,
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The inspector reviewed the Nuclear Station Modification Manual, Revision 3, Section 9.0, Administration of Exempt Changes and i
The revision to the Exempt Change Program
now appears to provide adequate guidance for activities conducted
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under this program. Those items that are exempt changes are listed under Section 9.2.1 in the Nuclear Station Modification Manual.
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(Closed) Inspector Followup Item 369/85-09-03 and 370/85-10-03:
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Revision to Nuclear Safety Evaluation Checklist The inspector reviewed the Nuclear Engineering Section Procedure NMSA-101,10 CFR 50.59 Evaluation of Nuclear Station Modification,
Revision 0, Section 7.1.
This procedure details the decision-making process for 10 CFR 50.59 evaluations. The procedure also documents the specific actions and reviews taken to arrive at a decision.
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(Closed) Inspector Followup Item 369/85-09-04 and 370/85-10-04-Preparation of Working Level Procedures for Technical Services (
Department Staff.
The inspector reviewed the McGuire Nuclear Station Project Services Manual, Revision 0.
Working level procedures for the Project Services Group were found in this manual.
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(Closed) Inspector Followup Item 369/85-09-05 and 370/85-10-05:
Revision to Design Engineering Department Procedure, PR-160.
The inspector reviewed Procedure PR-160, Revision 7.
The original concern was that the name of the group performing the 10 CFR 50.59 review was incorrect.
The group name has changed twice since the problem was originally identified. The Nuclear Safety Analysis Group is now assigned the responsibility for performing the evaluation in PR-160.
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(Closed) Inspector Followup Item 369/85-31-01 and 370/85-33-01:
Preparation of Prohibited Items List.
The inspector reviewed the Duke Power Prohibited Items List. The list is distributed to 48 addressees in various engineering programs and positions.
The list now includes mechanical components and material within nine various classifications. Each of the nine areas includes equipment, problem description, publication originator, publication date, and the effective date, g.
(Closed) Inspector Followup Item 369/84-33-01 and 370/84-30-01:
Implementing Procedures for Compliance Group.
The inspector reviewed a document entitled "McGuire Nuclear Station Periodic Maintenance / Periodic Testing (PM/PT) User Documentation."
This is a desk top user's guide to the PM/PT computer system providing a program description, the methodology to update or insert new data, and a description of the reports which tha system can generate. This document appears to provide enough technical guidance to alleviate the previous situation where handwritten notes were necessary to make the system useable.
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