IR 05000313/1988013
| ML20153F078 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/02/1988 |
| From: | Bundy H, Mckernon T, Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20153F076 | List: |
| References | |
| 50-313-88-13, 50-368-88-13, NUDOCS 8805100227 | |
| Download: ML20153F078 (5) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
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NRC Inspection Report:
50-313/88-13 Operating Licenses:
OPR-51-50-368/88-13 NPF-6.
Docket:
50-313 50-368
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Licensee:' Arkansas Power & Light Company (AP&L)
P.O. Box 551 Little Rock, Arkansas 72203
Facility Name:
Arkansas Nuclear One (AN0), Units 1 and 2 Inspection At:
ANO, Russellville, Arkansas Inspection Conducted:
April 18-22, 1988 Inspectors:
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H. F. Bundy, Reactor' Inspector, Test Programs Date
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Section, Division of Reactor Safety Yl f/e // /
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T. O. McKernon, Reac~ tor Inspector, Test Programs Date
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Section, Division of Reactor Safety
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Accompanied By:
W. C. Seidle, Chief, Test Programs Section Division of Reactor Safety on April 20-22, 1988 l
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Approved:
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W. C. Seidle,(Jhief, Test Programs Section Date Division of Reactor Safety j
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8805100227 880506 PDR ADOCK 05000313 Q
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-2-Inspection Summary Inspection Conducted April 18-22, 1988 (Report 50-313/88-13; 50-368/88-13)
Areas Inspected:
Routine, unannounced inspection of the licensee's modification testing program and the program for testing piping support and restraint systems.
Results: Within the two areas inspected, the licensee's programs, procedures, and records of completion appeared to satisfy all requirements.
No violations or deviations were identified.
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-3-DETAILS
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1.
Persons Contacted AP&L J. M. Levine, Executive Director, Nuclear Operations
- S. M. Quennoz, Plant General Manager
- P. Michalk, Licensing Specialist
- M, C. Cole, Surveillance Testing Coordinator
- M. Durst, Project Engineering Superintendent
- D. Crabtree, Engineering Programs Supervisor
- R. Lane, Engineering Manager
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- A. McGregor, Engineering Services Superintendent
- R. Oxner, Engineering Services
- J. L. Taylor-Brown, Quality Control / Quality Engineering Superintendent
- R. Wewers, Work Control Center Manager
- L. Humphrey, General Manager, Nuclear Quality
- H. Greene, Superintendent, Quality Assurance
- D. Lomax, Plant Licensing Supervisor
- E. Ewing, General Manager, Plant Support
- D. Howard, Manager, Licensing
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5. Smith, Senior Engineer (Modification Testing)
J. Gobell, Mechanical Maintenance Engineer B. E. Williams, Supervisor, Engineering
- B. Baker, Manager, Plant Modifications
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J. McWilliams, Manager, Maintenance NRC
- R. V. Azua, Reactor Inspector
- D. L. Kelley, Reactor Inspector
- J. I. Tapia, Project Engineer
- R. Haag, Resident Inspector
- W. Johnson, Senior Resident Inspector
- W. C. Seidle, Chief, Test Programs Section
The NRC inspector also interviewed other licensee personnel during the inspection.
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- Denotes those attending the exit interview on April 22, 1988.
2.
Modifications Testing (72701)
The objective of this part of the inspection was to ascertain whether the
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licensee's modification testing program for new or modified structures, systems, and components involving a licensing amendment was in conformance with regulatory requirements, applicable license amendments, Technical
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-4-Specifications (TS), industry codes and standards endorsed by the licensee, and detailed design documentation.
The NRC inspector reviewed the following documents to ascertain that the licensee had established appropriate administrative controls:
Procedure 6010.001, Revision 0, "Design Change Package (DCP)
Development"
Procedure 6030.01, Revision 1, "Installation Plan" To determine proper implementation of modification testing plans and procedures and appropriate documentation of results, the NRC inspector reviewed the following completed DCPs:
85-2039, "Reactor Trip Emergency Feedwater Actuation Bypass"
83-2215, "RG 1.97 MSIV Position Indication" 86-1099, "RCP P-32 A, B, C, D Seal Modification"
83-1157, "RG 1.97 Safety Relief Valve Indication" No violations or deviations were identified in this area.
3.
Testing Piping Suppport and Restraint Systems (70370)
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Document Review The purpose of this part of the inspection was to determine whether the licensee's program for installation, operation, and testing of pipe and component support systems was in accordance with the licensee's TS. The NRC inspector reviewed the following snubber
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functional testing results and testing program procedurcs:
Procedure 1306.03, Revision 10. "Visual Inspection, VT-3 and VT-4L of Snubbers," dated February 12, 1988;
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Procedure 1306.023, Revision 3. "Snubber Functional Testing Per i
VT-4," dated February 12, 1988;
Procedure 1306.30 Revision 0, "Visual Inspection of Snubbers "
dated June 13, 1986; and
Functional Test Rccords:
Unit 1 Exam No.
Component No.
M-1002
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MW-167A 101 H-0601 104 H-0604 152 H-0652 153 1MS-5-H6 Unit 2
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Exam No.
Component No.
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M-0052
M-1062 l
M-0059
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H-1268 143 M-0143 379 M-0379 The above test records and procedures were reviewed to verify the following attributes:
Surveillances and the frequency of surveillances of pipe supports
and restraints for safety-related piping were in conformance with the TS; Records were properly maintained and evaluated; and
An effective snubber infonnation data base was in place and
afforded easy, prompt access to past snubber functional test records, b.
Walkdown During the inspection, the NRC inspector conducted a walkdown inspection of a sampling of snubbers on the steam supply system emergency feedwater turbine. The snubbers were observed for visual indications and compliance with the installation configuration drawings.
Within the scope of this inspection, no violations or deviations were l
identified.
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4.
Exit Interview
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The NRC inspectors inet with licensee representatives denoted in
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paragraph 1 on April 22, 1988, and summarized the scope and findings of the inspection. The licensee did not identify as proprietary any of the
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materials provided to, or reviewed by, the inspectors during the inspection.
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