IR 05000313/1988007
| ML20151M418 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/12/1988 |
| From: | Barnes I, Singh A, Stewart R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20151M407 | List: |
| References | |
| 50-313-88-07, 50-313-88-7, 50-368-88-07, 50-368-88-7, NUDOCS 8804250050 | |
| Download: ML20151M418 (7) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-313/88-07 Operating Licenses:
DPR-51 50-368/88-07 NPF-6 Dockets:
50-313 50-368 Licensee: Arkansas Power & Light Company (AP&L)
P.O. Box 551 Little Rock, Arkansas 72203 Facility Name: Arkansas Nuclear One (ANO), Units 1 and 2 Inspection At: ANO, Russellville, Arkansas Inspection Conducted: March 7-11, 1988 f
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Inspectors:
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d R. C. StewartT Reactor Inspector, Materials and Date (
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Quality Programs Section, Division of Reactor
- Safety
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A A. Singh, Reactor Inspector, Plant Systems Section Date r
Division of Reactor Safety Accompanying Personnel:
K. C. Dempsey, Mechanical Engineering Branch, Office of Nuclear Reactor Regulation (NRR)
C. B. Ransom, EG&G Idaho, Inc.
Approved:
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I. Barnes, Chief, Materials and Quality Programs Date Section, Division of Reactor Safety Inspection Summary
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Inspection Conducted March 7-11, 1988 (Report 50-313/88-07)
Areas Inspected:
No inspection of Unit I was conducted.
I Results:
Not applicable.
C804250050 880415 PDR ADOCK O',iOOO313 Q
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Inspection Conducted March 7-11, 1988 (Report 50-368/88-07)
Areas Inspected: Routine, unannounced inspection of the inservice testing program for pumps and valves. Subject activities reviewed in this area of inspection included tracking methodology for inservice testing, test procedures and results, inservice testing trend reports, quality assurance audits, and witnessing of an inservice test.
Results: Within the one area inspected, no violations or deviat. ions were Identified.
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DETAILS 1.
Persons Contacted AP&L-
- J. Levine, Executive Director, Nuclear Operations
- D Lomax, Plant Licensing Supervisor
- D. Howard, Manager Special Projects
- P. Michalk, Plant Licensing Engineer
- E. Ewing, General Manager, Plant Support
- J. McWilliams, Manager, Maintenance
- L. Humphrey, General Manager, Nuclear Quality
- 0. Graham, Quality Engineering Supervisor
- S. McGregor, Engineering Supervisor
- R. McWilliams, Engineer
- D. Crabtree, Engineer
- G. Provencher, Quality Assurance (QA) Supervisor
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NRC
- W. Johnson, Senior Resident Inspector C. Harbuck, Resident Inspector
- Denotes those present at the exit interview.
The NRC inspectors also contacted other plant personnel, including operators, technicians, and administrative personnel.
2.
Inservice Testing (IST) of Pumps and Valves (73756)
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The objectives of this inspection were to evaluate the implementation of the ANO, Unit 2 IST program for safety-related pumps and valves, and to assess the adequacy of the testing performed with respect to the guidelines of Section XI of the ASME Code, a.
IST Program Overview The.AP&L IST of pumps and valves, Unit 2. is subject to the requirements of 10 CFR 50.55a(g), Regulatory Guide 1.26, and the ASME Boiler and Pressure Vessel Code,Section XI. Subsections IWP and IWV, 1974 Edition through Winter 1975 Addenda.
The initial 120-month IST program for pumps and valves for Unit 2 was approved by NRR by letter dated June 20, 1985, and is currently being implemented under Revision 3 of AP&L Procedure 1022.7, "ASME Code Section XI, Inservice Testing Program." Unit 2, dated April 14, 1987.
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Administrative guideline documents reviewed by the NRC inspectors included the following:
ASME Boiler and Pressure Vessel Code Section XI, Subsections IWP and IWV,1974 Edition through Winter 1975 Addenda;
Arkansas Nuclear One, Unit 2, Second Ten Year Inservice Testing Program dated December 10, 1982;
Safety Evaluation Report, Pump and Valve Inservice Testing Program, Arkansas Nuclear One, Unit 2, dated June 20, 1985;
J. T. Enos. AP&L, lettor to E. J. Butcher, USNRC, dated September 30, 1985; and
AP&L Procedure 1022.07, ASME Code Section XI Inservice Testing Program, Unit 2, Revision 3, dated April 14, 1987.
During the review, it was observed that the licensee has submitted additional written requests for relief involving diesel generator subsystems, service water pumps, feedwater pump turbine governor valves, and HPSI and LPSI system check valve leak tests.
Those matters were discussed with the licensee representatives and the accompanying NRR representatives and are to be addressed in a subsequent NRR Safety Evaluation Report.
No violations or deviations were identified.
b.
Methodology used in Implementing IST Program The review of the IST program implementation methodology was accomplished by holding a meeting with utility personnel from several utility organizations.
The program documentation was discussed and questions were asked to determine how test scheduling and reporting is performed.
Key people in the IST scheduling and control chain were then interviewed to further clarify this process.
AP&L Procedure 1022.07, Revision 3. "ASME Code Section XI Inservice Testing Program - Unit 2," and 1000.09, Revision 17, "Surveillance Test Program Control," are the two principal administrative control procedures utilized in implementing the Unit 2 IST program. The frequency of component testing is controlled by a handwritten record book and the test schedules are generated weekly by paging through the record book and listing the tests due for the various components.
The NRC inspectors examined a sample selection of 1987 record pages for verification of monthly and quarterly test frequency schedules, in addition to pumps or valves requiring increased test frequencies.
No violations or deviations were identifie _ _
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c.
Review of IST Test Procedures and Test Results
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During the inspection, the NRC inspectors made a random selection of
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AP&L operational test procedures in order to verify that procedures contained reference values and other pertinent attributes prescribed by guideline of the ASME Code of Section XI, Articles IWP/IWV-3000.
Procedures selected included the following:
AP&L Procedure 2104.29, Service Water Pump 2P4A and 2P48 Monthly Test Procedures and Results, dated December 31, 1986,
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Supplements 1A, IB, and IC, tests conducted March 4, 1987, through February 4, 1988;
AP&L Procedure 2104.36, 2DG1 Diesel Generator Monthly Test Procedures, dated April 10, 1987 Supplements 1 and 2, tests conducted December 1, 1987, through January 28, 1988;
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AP&L Procedure 2104.02, Charging Pump 2P-36A Monthly Test
Procedures, dated July 31, 1986, Supplement 1, tests conducted March 3 and September 2, 1987; AP&L Procedure 2104.39, Quarterly HPSI Valve Stroke Test, dated
October 16, 1986 Supplement 4, tests conducted May 22 and
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November 27, 1987.
Supplement 1 pump tests conducted April 15 through November 20, 1987;
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AP&L Procedure 2104.40, Quarterly LPSI and RWT Valve Stroke Test and Injection M0V Limit Test, dated June 10, 1987, Supplements 3 and 4, tests conducted February 12, 1987, through February 13, 1988; AP&L Procedure 2106.06, Monthly 2PSA Test, dated November 3,
1987, Supplement 1, tests conducted November 29, 1987
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December 22, 1987, and January 22, 1988; and l
AP&L Procedure 2102.01, HPSI and LPSI Systems Check Valve Leak
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Test, dated July 28, 1985 Supplement 3, tests conducted
September 9, 1986.
i During the NRC inspectors' review of Administrative
l Procedure 1000.09 Revision 17. "Surveillance Test Program Control,"
and the individual valve and pump test procedures, it was observed
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that the procedures do not clearly specify the corrective action requirements of the ASME Boiler and Pressure Vessel Code,Section XI, paragraphs IWP-3230 and IWV-3410(c)(3). The NRC inspectors observed,
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corrective actions were initiated in accordance with ASME code requirements.
In discussing this observation with the cognitant licensee personnel, the NRC inspector expressed concern in that, lacking procedural specificity, test conductors may not i
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recognize deviations falling within the pump "Alert Ranges" versus
"Required Action Ranges " etc.
The licensee representatives indicated that this matter would be reviewed. This is considered an open item pending NRC review of the licensee procedural actions (368/8807-01).
No violations or deviations were identified.
d.
Test Witness During this inspection, the NRC inspectors observed the disassembly and inspection activities associated with check valve EFW 2A.
In conjunction with the work observation, the NRC inspectors reviewed the following AP&L procedures:
AP&L Procedure 2311.07 Inservice Testing-Valve Visual
Inspection During Refueling Outages, dated March 21, 1985; AP&L Procedure 3108-3, Swing Check Valve Drawing, dated
October 3, 1975; and AP&L Procedure 2402.097, Unit 2 EFW 2A and 2B Disassembly
Inspection / Repair and Reassembly, dated January 11, 1988.
During the NRC inspectors' observation of the disassembly, inspection / repair of the Unit 2 emergency feedwater check valve EFW 2A, it was noted that procedure instructions (Procedure 2402.97) did not require the measurement of the force or torque necessary to operate the valve disk as required by Section XI, paragraph IWV-3520(b)(2) of the ASME Code.
It was later established that the NRR Safety Evaluation Report concerning the AP&L Unit 2 IST program, paragraph 3.2, granted relief from the test frequency specified by the Code, in that the NRC concluded that a valve sampling disassembly inspection utilizing a manual full stroke of the disc is an acceptable method to verify a check valve's full stroke capability.
Because of the configuration of the construction of this particular check valve, torque or force measurements would appear to be impractical, the relief granted should be further clarified.
The licensee representatives indicated that they would clarify this matter with NRR.
This is considered an open item pending further clarification by the licensee (368/8807-02).
In addition to the above, the NRC inspectors reviewed AP&L Procedure 2104.36 "2DG1 Diesel Generator Monthly Test Procedure,"
dated April 10, 1987, in anticipation of witnessing this particular test, however, the test was terminated after an initial start due to a brief lube oil fire in the exhaust heade ______ -_ - - __ _ _ _.
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At the time of the test, fuel elements had been removed from the
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reactor vessel; therefore, the inoperability status of the diesel was not of insnediate concern.
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The. fire was a result of a manifold gasket leak which was to be corrected during the diesel overhaul that was scheduled for this outage. The NRC resident inspector will review this matter prior to plant restart.
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No violations or deviations were identified, e.
IST Trend Reports The NRC inspector reviewed "Inservice Testing Trend Report - Fourth I
~ Quarter 1987" dated January 14, 1988. The purpose of this quarterly report is to indicate IST components and parameters which display significant trends or other noteworthy behavior, including increased test frequencies.
Trends are displayed graphically and incorporate
specific reference parameters for each component. There were no degradation trends noted by the NRC inspector, and the input data
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appeared to be accurate and correlated well with the actual test
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results sampled.
No violations or deviations were identified,
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f.
0A Aucits
During this inspection, the NRC inspectors reviewed the AP&l. QA Audit of the IST program conducted in July 1987.
The audit appeared to be extensive and covered the principal areas of the IST program.
There were no significant findings identified. Discrepancies observed during the audit were dispositioned in a timely manner. QA audits of the IST program are scheduled on a 2-year interval.
No violations or deviations were identified.
This review verified that the licensee has administrative controls and l
procedures to implement the IST program.
Procedural guidance is provided l
to aid the operators in performance of the testing functions.
The tests appear to be performed in accordance with the Section XI of ASME Code requirements.
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4.
Exit Interview l
The NRC inspectors met with the licensee personnel denoted in paragraph 1 l
j on March 11, 1988, and sumarized the scope and finding of the inspection.
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