IR 05000348/1981028
| ML20040C117 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/16/1981 |
| From: | Skinner P, Upright C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20040C109 | List: |
| References | |
| 50-348-81-28, 50-364-81-31, NUDOCS 8201270284 | |
| Download: ML20040C117 (7) | |
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NUCLEAR REGULATORY COMMISSION
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o 101 MARIETTA ST., N.W SUITE 3100 o
ATLANTA. GEORGIA 30303
Report Nos. 50-348/81-28, 50-364/81-31 Licensee: Alabama Power Company P. O. Box 2641 Birmingham, Alabama 35291 Facility Name:
Farley Docket Nos. 50-348, 50-364 License Nos. NPF-2, NPF-8 Inspection at Farley site near Dothan, Alabama Inspector: k h [ YJt> M si k
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Approved by:
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C. M. Upright,,Sjfc~tip/ Chief Date SYgned Engineering Ig;$ectiod Branch Engineering and Technical Inspection Division SUMMARY Inspection on November 30 - December 4,1981 i
Areas Inspected This routine, unannounced inspection involved 38 inspector-hours on site in the areas of licensee action on previous enforcement matters, nonroutine reporting program, maintenance, calibration, organization and administration, onsite review committee, and licensee action on previously identified inspection items.
Results-Of the-seven areas inspected, no violations or deviations were identified.
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8201270284 811218 PDR ADOCK 05000348 G
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REPORT DETAILS 1.
Persons Contacted Licensee ' Employees R. Berryhill, Systems Performance Superintendent T. Cherry, I&C Supervisor
- D. Culver, Safety Audit and Engineering Review G. Hairston, Plant Manager J. Hudspeth, Document Control Supervisor J. McGowan, Manager-Safety Audit and Engineering Review
- C. Nesbitt, Technical Superintendent
- R. Rogers, Technical Support supervisor
- W. Ware, Supervisor-Safety Audit _and Engineering Review
- J. Woodard, Assistant Plant Manager Other licensee employees contacted included. technicians, opr.:rators, and office personnel.
NRC' Resident Inspectors
- W. Bradford, Senior Resident Inspector
- T. Peebles, Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on December 4, 1981 with those persons indicated in paragraph I above. The licensee acknowledged the inspection findings.
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Licensee Action on Previous Inspection Findings Unresolved items from Inspection Reports 50-348/80-14 and 50-364/80-16 were
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reviewed with respect to corrective action taken by licensee.
.,a.
(Closed) Unresolved Item (348/80-14-4):
Lead Auditor Input to
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Corrective Actions for Nonconforming Items Identified in Quality-Assurance Audits.
The ' inspector reviewed the last five. audits conducted by the Quality Assurance group. The reports contained input from the lead auditor to correct the cited nonconformances either in-the recommendation section of :the audit reports or in the ' comments section of the report.
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b.
(Closed) Unresolved Item (348/80-14-7):
Procedure for Escalation of Audit Findings. The inspector reviewed the procedures used to perform Quality Assurance audits and correct noncontormances as a result of these audits.
Since all audit results are approved by the Vice-President of Nuclear Generation and he is personnally involved in the approval of the resolution of findings, the intent of escalation of audit findings is being accomplished.
c.
(Closed) Unresolved Item (348/80-14-8): Followup of Reaudit of CAR's 366, 375, 401, 469, 471 and 475. The inspector reviewed and evaluated the reaudits of the areas designated. The result appear to be accept-able.
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Unresolved Items Unresolved items were not identified during this inspection.
5.
Nonroutine Reporting Program (90714)
References:
(a)
FNP-0-AP-22, Nonconformance Control / Deficiency Reporting, Revision 2 (b)
FNP-0-AP-30, Preparation and Processing of Incident Reports, Plant Event Reports and Licensee Event Reports, Revision 5 (c)
FNP-0-AP-31, Quality Control Measures, Revision 4 (d)
FNP-0-AP-32, Review of Operating Data, Revision 1 (e)
FNP-0-AP-49, Plant Reporting Requirements, Revision 3 (f)
FNP-0-AP-62, Evaluation of Defects and Noncompliances Potentially Reportable Under 10 CFR Part 21, Revision 0 (g)
FNP-0-AP-65, FNP Nuclear Experience Evaluation Program, Revision 0 The inspector reviewed references (a)-(g) and verified that:
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Administrative controls have been established for prompt review and evaluation of off-normal events
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Administrative controls have been established for review of planned and unplanned maintenance and surveillance testing activities Administrative centrols have been established for reporting safety-
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related events internally and to the NRC l
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Administrative controls contain provisions for recognition and
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reporting events that are covered by 10 CFR 21
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Administrative controls have been established for review and evaluation of vendor bulletins and circulars.
Based on this review, no violations or deviations were identified.
6.
Maintenance (62700)
Reference:
(a) Technical Specifications (b)Section XI, ASME Boiler and Pressure Vessel Code (c)
FNP-0-AP-52, Equipment Status Control and Maintenance Authorization, Revision 0 The inspector reviewed maintenance activities on safety-related systems and components to ascertain whether the activities were conducted in accordance with approved procedures, regulatory guides and industry codes and in conformance with Technical Specification requirements.
The following criteria were used during this review:
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Required administrative approvals were obtained prior to initiating the work Limiting conditions for operation were met while the components were
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removed from service Approved procedures were used where the activity appeared to be beyond
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the normal skills of the craf t
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Activity was accomplished by qualified personnel
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The licensee had evaluated system failures and reported them in accordance with the Technical Specifications
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Written procedures were established for initiating requests for routine and emergency maintenance
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Criteria and responsibilities for review and approval of maintenance requests were established Criteria and responsibilities that form the basis of designating the
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activity as safety or non-safety-related were established Criteria and responsibilities were designated for performing work
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inspection of maintenance activities
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Provisions and responsibilities were established for the identification of appropriate inspection hold points related to maintenance activities
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Methods and responsibilities were designated for performing functional testing of structures, systems or components following maintenance work and/or prior to their being returned to service.
Thirteen completed maintenance activities and associated documents were reviewed. The activities reviewed were the following:
WORK REQUEST NUMBER DATE 34193 10/03/81 40293 09/12/81 40255 10/06/81 24960 12/05/80 25043 12/08/80 44009 08/09/81 43015 06/10/81 34927 06/29/81 42132 07/02/81 36347 03/16/81 4015; 06/26/81 31249 03/02/81 37449 04/12/81 Based on this review, no violations or deviations were identified.
7.
Calibration (56700)
The inspector determined that this inspection area has been reviewed by the NRC resident inspectors during their routine inspections. No problems have been identified and results of their inspections are documented in the resident inspector's monthly reports. No additional inspection is warranted at this time.
8.
Organization and Administration (36700)
References:
(a) Technical Specifications (b)
FNP-0-AP-3, Plant Organization and ResponsiUTlity, Revision 3 The inspector reviewed reference (b) to assure the existing plant organiza-tion is as required by reference (a).
The personal qualifications of the following positions were reviewed during this inspection:
Operations Superintendent Maf rtenance Superintendent
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Technical Superintendent Training Superintendent Assistant Plant Manager Operations Supervisor Reactor Engineer Based on this review, no violations or deviations were identified.
9.
Onsite Review Committee (40700)
References:
(a) Technical Specifications (b) Operations Quality Assurance Policy Manual, Appendix C, Plant Operations Review Committee Charter, Revision 17 (c)
FNP-0-AP-2, Plant Operations Review Committee, Revi-sion 6 The inspector reviewed references (b) and (c) to assure they met the requirements of reference (a).
In addition the resident inspectors frequently attend Plant Operations Review Conmittee (PORC) meetings. The inspector attended one PORC meetinq during this inspection to observe that requirements for membe-ship, quorum, review process and qualifications were met.
Based on this review, no violations or deviations were identified.
10.
Licensee Action on Previously Identified Inspection Items a.
(Closed) Open Item (364/80-16-04)
See response 3.a.
b.
(Closed) Open Item (364/80-16-07)
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See response 3.b.
c.
(Closed) Open Item (364/80-16-12):
Review Remaining Test to be Conducted on Safety Related Systems to Verify Second Signoff of Key Steps.
Discussion with the resident inspector identified that this item was reviewed as part of his review of completed test.
d.
(Closed) Open Item (348/80-16-13):
Review of Control Coordinators Destruction of Controlled Drawings. The Control Coordinator (Central Coordinator) position has been eliminated and all drawings that were assigned to this individual were recalled and destroyed, i
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(Closed) Open Item (348/80-14-17, 364/80-16-17):
Revise Procedure FNP-0-AP-3 to Reflect all Organization and Title Changes Which Became Effective Near the end of March 1980. Temporary Change Notice (TCN) 28 was incorporated into Revision 3 of FNP-0-AP-3 dated October 24, 1980.
f.
(Closed) Open Item (348/80-14-19, 364/80-16-19): Revise 0QA-AP-06 to Incorporate Titles of Organizaticn Changes.
0QA-AP-06 has been reissued as SAER-AP-06. Revision 3 of this procedure was reviewed with respect to organization titles and no discrepancies were noted.
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