IR 05000313/1989026
| ML20245K627 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/21/1989 |
| From: | Singh A, Stetka T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20245K578 | List: |
| References | |
| 50-313-89-26, 50-368-89-26, NUDOCS 8907050195 | |
| Download: ML20245K627 (6) | |
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APPENDIX B-
~U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC-Inspection Report:
50-313/89-26
'Oper6 ting _ Licenses: DPR-51 50-368/89-26.
NPF-6 Dockets:
50-313 50-368 Licensee: Arkansas Power & Ligh't Company (AP8L)
P.O. Bcx 551 Little Pock, Arkansas 72203 Facility Name: Arkansas Nuclear One (ANO),-Units 1 and 2 Inspection At: ANO, Russellville Arkansas Inspection Conducted: ' June 5-9, 1989 i
i Inspector:
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A. Singh,~ Reactor Inspettor, Plant Systems Date~
j Section, Division of Reactor Safety Approved:
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T. T.' Stetka, Chief Plant Systems Section Date
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Division of Reactor Safety Inspection Summary Inspection Conducted June 5-9, 1969 (Report 50-313/89-26)
Areas Inspected: Routine, unannounced inspection of the licensee's Technical Specification (TS) required-calibrationprogram,thepreventivemaintenance(PM)
program related to the calibration of plant instrumentation for components not addressed in the-TS and the licensee's action on previously identified inspection-findings.
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Results: Within'the areas inspected, one violation and one deviation were identified. The violation involved the area of calibration for instrumentation not specigcally addressed in the TS. The calibration frequency requirements were not met at~ required by procedures (paragraph 3).
The deviation involved a failure to meet the commitment and implementation date for a new PM program (paragraph 2).
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890705o195 890622 PDR ADOCK 0b000313 G
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The licensee's plant surveillance (PS) cal.ibration program for the control and
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evaluation of installed instrumentation and control (I&C) devices, specified i
by the TS..is effectively being implemented. -An apparent weakness was noted
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in the licensee's training program for the I&C technicians.
Inspection Conducted June 5-9, 1989 (Report 50-368/89-26)
Areas Inspected:- Routine.. unannounced inspection of licensee action on previously identified inspection findings.
j Results: Within the area inspected, one deviation was identified (failure to meet the commitment and the implementation date'for a new PM program, paragraph 2).
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-DETAILS
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Persons Contacted
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- D. B.,Lomax, Plant Licensing Supervisor
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W. Perks Training Manager
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'*C. Zimmerman, Operations Technical: Supervisor. Unit 1 G.- Kendrick, Maintenance 18C Superintendent-l
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- J. D..Vandergrift, Operations Fanager
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E. Ewing,LGeneral Manager,. Plant Supporti
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. R.-Lane Manager, Engineering.-
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- J. Tayler.-Brown, Quality Control Superintendent
- R. Thorton, Licensing.
- N. S. Carns. Director, Nuclear Operations-y
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- A. J. Wrape, Manager EIC Design-Engineering
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- G. R. D'Aunoy Operations.. Unit 2
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- Sh McGregor, Engineering Services. Superintendent, Engineering _ Department'
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'G. T. Jones, General Manager.f ngineering-
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-NRC, Region IV (1
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- R. Haag, Resident. Inspector.
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- W.CA.~. Johnson, Senior Resident Inspector'
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- R. V. Azua, Reactor Inspector
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- H. F. Bundy, Reactor Inspector-
. W. C. Seidle, Chief, Test Programs Section-
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- Denotes those personnel present at:the June 9',
1989, exit interview.-
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J The NRC inspector contacted other AP&L personnel during the performance of
theLinspection.
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Followup on Previous Inspection Item 2.1 (0 pen)! Violation (313/8730-01;368/8730-01):
Inadequate PM' program for l
safety-related components. The NRC inspector reviewed the. licensee's i
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. response to this violation.
In their response, the licensee committed to
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1mplement and complete a:new PM program by October 1988. As of June 9, 1989, the licensee has completed and implemented only about 50 percent of
the PM program.
Failure to meet the commitment date-is. considered to be a Deviation to a commitment made to the NRC.
Desiation!(313/8926-01;368/8926-01):
Failure to complete and implement
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the.new PM program by October.1988.
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3.
Calibration of Plant Instrumentation for ANO Unit 1 (56700)'
This inspection was to ascertain whether,the licensee had developed and implemented a program for the calibration and testing of, plant insttiled I&C devices. This includes the I&C devices specified in the TS and I&C
' devices that are used for.the' operation and testing of equipment, but not specifically addressed in the TS as requiring calibration.
3.1. Calibrations Specified by TS-Calibrations required by TS are controlled as part of the ANO Surveillance Test Program.' The inspector determined that procedures for calibration of plant installed I&C devices are being implemented in accordance with the TS and surveillance test program controls, as described in the AN0's.
Final Safety Analysis Report (FSAR), Sections 7.0 and 9.5 and related commitments to Regulatory Guides and Standards..-TS surveillance and calibrations are further controlled by_ rrocedures 1000.009 and 1001.009,
" Surveillance Test Program," Revision 19 and, " Master Test Control List,"
Revision 14, respectively.
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The NRC inspector reviewed the completed test and calibration procedures-(documentation packages) for surveillance performed during the last 18 months. This review verified:
(a) test documentation was' completed, (b) approved procedures were utilized, (c) acceptance criteria were met, and (d) completed procedures documented "as found" and "as left"
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conditions.
The NRC inspector reviewed the following surveillance test procedures:
Procedure No.
Title Date-1304.001 High Pressure Injection / Low Pressure
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Revision 2 Injection (HPI/LPI) and Reactor Duilding Spray Flow Instrumentation Surveillance Green Channel
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1304.012 Borated Water Storage Tank Level and 09/04/88 i
Revision 11 Temperature Instrumentation Surveillance Test 1304.038 Unit 1 Reactor Protection System Channel B 02/21/89 Revision 2 Test 1304.41 Reactor Protection System Channel A 11/01/88 Revision 16 Calibration
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1304.52 Engineered Safeguards Actuation.
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08/17/87
Revision 10 System (ESAS)l Channel No.1 Calibration l
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In addition, the NRC inspector o5 served a calibration of the reactor protection system being conducteo in accordance with Procedure 1304.038.
The NRC inspector verified that the I&C technicians used the approved procedures and that the calibration was performed in accordance with these procedures. While observing this activity, the NRC inspector noted that there was no documentation available concerning the training and qualification of the individuals performing the calibration. The NRC inspector's discussions with the licensee's representatives indicated that there was no written requirement to document the training and qualification of the 180 technicians. The qualification was determined by the immediate supervisor and approval to perform the test was granted verbally by this supervisor. This is considered to be a weakness in the training program.
No violations or deviations were identified in this part of the inspection.
3.2 Calibrations not Specified by TS The prograrmiatic controls for calibration of installed IEC devices that are not specifically addressed in the TS as requiring calibration, are part of the AN0 PM program. The schedule of calibration and verification for these installed I&C devices is outlined in the ANO, Unit 1 Procedures 1092.179A.006, Revision 5, " Preventive Maintenance Engineering Evaluation" and 1001.004, Revision 1, " Preventive Maintenance Program."
Conditions required to perform calibrations on plant installed instrument devices are further defined in 1000.22 Revision 3. " Preventive Maintenance of Instrumentation." The NRC inspector reviewed the following completed procedures:
Procedure No.
Title Date 1304.119 Waste Gas Surge Tank Instrument Calibration 4/11/88
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Revision 2 1413.013 Pressure Differential Transmitter (PDT) 2131 3/6/89 Revision 1 VEF-38A Inlet Crossover Air Flow i
1412.101 Emergency Diesel Generator (EDG) 2DG1-480V 3/11/89 Revision 0 30 Circuit Breaker Panel 2413.121 Circuit Breakers Heating, Ventilation and 3/22/89 l
Revision 0 Air Conditioning (CBHVAC) Hydrogen Purge Air Flow j
1000.104 Condition Reporting and Corrective Actions 4/30/89 l
Revision 4 j
i The review determined that the test documentation was completed, acceptance
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criteria had been met, the approved test procedures were used, and technical content was acceptable. The licensee used a computerized program for scheduling the conduct of calibrations. Section 7.3 of Procedure 1092.179A.006,
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-6-requires that the calibration schedules and frequencies be established for the safety-related systems which are not addressed in TS. As a result of the NRC inspector's review, it was determined' that two. calibrations were overdue. The two calibrations, which had an 18-month frequency, exceeded
- this f requency by 20 days' including the allowable grace period. The two.
late calibrations were the result of the licensee's untimely approval process in issuing two new procedures.
Failure to meet the calibration frequency as required by Procedure 1092.179A.006 is considered to be an apparent violation.
This finding is considered to have minimal safety significance because the examples appeared to be isolated examples within a generally effective program. Therefore, in accordance with 10 CFR Part 2, Appendix C of the NRC Enforcement Policy, dated October 13, 1988, this violation will not be cited.
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Exit Interview The NRC inspector met with the licensee's representatives denoted in paragraph 1 on June 9, 1989, and summarized the scope and findings of the inspection.
No information was presented to the NRC inspector that was a
identified by the licensee as proprietary.
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