IR 05000313/1988011
| ML20154H177 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/10/1988 |
| From: | Kelley D, Seidle W, Tapia J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20154H171 | List: |
| References | |
| 50-313-88-11, 50-368-88-11, NUDOCS 8805250254 | |
| Download: ML20154H177 (9) | |
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Inspection. Report:
50-313/88-11 Operating License:
OPR-51 50-368/88-11 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:
AN0 Site, Russellville, Arkansas Inspection Conducted:
April 18-22,1988 S
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Inspect
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D. L. Kelley, Reactd( Inspec or, Test Programs Odte' '
Section, Division of Reac or Safety
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pi Profect Eligip@pr, Project D#te l-Sec ion Division of Rifactor Projects Accompanying Personnel:
R. V.-Azua, Reactor Inspector, Test Programs Section, Division of Reactor Safety W. C. Seidle, Chief, Test Programs Section Division of Reactor Safety on April 21-22, 1988
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Approved:
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Div blon of Peactor Safety ggg52ggOCK05o00323 254 e80516
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Inspection Summary j
Inspection Conducted April 18-22, 1988 (Report 50-313/88-11)
Areas Inspected:
No inspection of Unit 1 was conducted.
Results:
Not applicable.
Inspection Conducted April 18-22, 1988 (Report 50-368/88-11)
Areas Inspected:
Routine, unannounced inspection of containment integrated leak rate test (CILRT).
Results:
Within the one area inspected, one apparent violation was identified (failure to correctly follow procedures, paragraph 2).
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DETAILS 1.
Persons Contacted AP&L
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- S. M. Quennoz, Plant General Manager
- P. Michalk, Licensing Specialist
- R. Lane, Manager, Engineering
- B. Baker, Manager, Plant Modification >
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- E. C. Ewing, General Manager, Plant Support
- D. B. Lomax, Plant Licensing Supervisor
- R. P. Wewers, Work Control Center Manager-
- D. Howard, Manager, Licensing
- H. Greene, Quality Assurance Superintendent
- S. McGregor, Engineering Services Superintendent
- J. Taylor-Brown, Quality Control / Quality Engineering Superintendent
- J. McWilliams, Maintenance Manager
D. Crabtree, Engineering Program Supervisor, CILRT Test Director
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R. Oxner, Engineering Services, CILRT Test Director Bechtel, Inc.
B. Patel, lead Engineer (CILRT)
L. Young, Lead Engineer (CILRT)
K. Pimentel, Engineer (CILRT)
R. Blum, Engineer (CILRT)
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
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The NRC inspectors also contacted other plant personnel, including operators, technicians, and administrative personnel.
- Denotes those present during the exit interview.
2.
Unit 2 Containment Integrated Leak Rate Test '(70307/70313)
During the week of April 18-22, 1988, the licensee performed a full pressure, short-time duration CILRT on Unit 2.
The NRC-inspectors ~were onsite to observe the test performance.
The NRC inspectors' reviews and observations are detailed below:
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a.
Pretest Reviews and Observations The NRC inspectors reviewed the licensee's CILRT Test-Procedure No. 1092.031, Revisiori 0, to ascertain that the requirements of Unit 2 Technical Specifications, ANSI N45.2, ANSI /ANS 56.8(1981)and
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Bechtel Topical Report BN-TOP-1 had been addressed.
Specific areas within the procedure that were examined were the correlation of the requirements of BN-TOP-1 and the validation of selected valve lineup lists with current. Piping and Instrumentation-Diagrams (P& ids).
The following valve lineup sheets were compared to the system P& ids to verify that the listed test position was correctly identified:
Appendix B, pages 79, 80, and 81 of 130, "Sampling System," P&ID No. 6600-2-M2237, Sheet 1
Appendix B, pages 43 and 44 of 130, "Service Water System," P&ID No. 6600-Z-M2210, Sheet 3.
Appendix B, pages 73 and 74 of 130, "Component Cooling Water.
System," P&ID No. 6600-2-M2234, Sheet 1 The instrument calibration data for the 18 dry bulb temperature-sensors, 6 dewpoint temperature sensors, and 2 absolute pressure sensors were examined to verify that the instrument calibration dates were current and the calibration standards were traceable to the National Bureau of Standards.
The NRC inspectors also inspected the Data Acquisition Station (DAS)
to examint Me licensee and Bechtel logs, review the completed step signoffs c- 'he test procedure, and examine sensor scanning equipment.
Several hours prior to the licensee's final walkdown and containment closure, the NRC inspectors performed an independent walkdown of the Unit 2 containment.
During the walkdown, the NRC. inspectors assessed the general containment readiness for the test, observed the performance of several valves being positioned for test (see Attachment A) and randomly selected several valves for independent test position verification (see Attachment B).
While observing two plant operators positioning valves in the
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containment for the CILRT, the NRC. inspectors noted the ILRT tag
"completed by" and "verified by" signatures were already on the tags prior to any operator action. While observing the operators position Valve 2SA-97, which is accessible.from a platform approximately 5 feet from the floor, the NRC. inspectors noted that only the operator positioning the valve stepped up on the platform.
The NRC inspectors, standing next to the operator who was to verify the valve position, could not verify the valve position from the floor.
The
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operator who was_to verify the valve position did not step up on the platform, yet the test tag with the verifiers signature on 't was hung on the valve.
The tag was hung by the operator who manipulated.
the valve, not the verifier.
The NRC inspectors did verify the valve position as correct by stepping up on the platform and noting the valve stem position.
This action by the plant operator does not appear to meet the intent of what.is generally accepted as independent verification.
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- er evidence of faulty valve position verification was discovered during the random sample of valve positions performed by the NRC inspectors. When examining Valve ZPS-5878 and its associated pipe cap, the NRC inspectors noted the valve appeared to be closed and the pipe cap was in place. The valve lineup sheet and the attached ILRT tag called for the valve to be open and the cap removed for the test.
The signatures and dates on the tag indicated the valve had been positioned and verified correct the day before the NRC inspectors examined it.
This is an apparent violation of the CILRT Test Procedure No. 1092.031, Revision 0, valve lineup and verification requirements.
(50-368/8811-01)
The licensee was informed of this finding and took immediate corrective action.
The corrective action was to position Valve ZPS-5878 correctly and remove the pipe cap.
Further action taken by the licensee was to reverify all valve and associated pipe caps whose test position was valve open and pipe cap removed.
No other violations or deviations were identified, b.
CILRT Test Performance Observations The licensee completed preparations for the CILRT, sealed the containment on April 20, 1988, and comenced containment pressurization at 6:30 p.m.
A reduction of pressurization rate was initiated at approximately 14 psig to perform a walkdown of the
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containment penetration areas.
One valve in the fire system, 2FS-3275, was noted to be slowly filling the balloon attached to-the downstream vent line; this indicated leakage. The licensee quantified the leakage and determined that the leakage would not invalidate the test. The valve was left as is and periodically observed.
The test pressure of 54 psig was attained at 1:55 p.m. on April 21, 1988.
The start of the CILRT was declared at 9:30 p.m. on April 21, 1988.
The test was completed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> later at 5:30 a.m. on April 22, 1988. The flow for the verification test was established at 5:45 a.m. on April 22, 1988, and the test was complete the same day
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at 10:45 a.m.
During the performance of the CILRT and subsequent verification test, the NRC inspectors made several random tours.
During these tours, j
data points, graph plots, and the log books were examined.
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At the completion of the. test, the interim Bechtel report was reviewed. The report indicates acceptable data and conclusions. The NRC inspectors will perform an indepth review of-the.results when the.
final report is issued. The results of this review.will be documented in a later NRC report.
No violations or deviations were identified.
3.
Exit Interview The NRC inspectors met with Mr. S. M. Quennoz, General Manager, Plant Operations, and other members of the AP&L staff on April 22, 1988. At this meeting, the NRC inspectors summarized the scope and finding of the.
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No proprietary information was identified by the licensee.
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ATTACHMENT A i-LIST OF VALVES & OPENINGS THAT NRC INSPECTORS OBSERVED BEING OPEN/ CLOSED BY AN0 PERSONNEL Steam Generator Secondary System / Emergency Feedwater Correct Valve No.
ValveDescription Test Position Normal Position Position 2SGS-1065A 2PP-1065 Isol Closed Closed Yes 2SGS-10658 2PP-1065 Isol Closed Closed Yes and Cap 2SGS-10B
"B" SG Sample Open Open Yes 2SGS-11B
"B" SG Sample Open Open Yes Service Air Syst m 2SA-97 Serv Air Ctmt Isol Cl e.t ed Closed Yes 2C-1 Equip Hatch - All bolts present and torqued.
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ATTACHMENT B LIST OF VALVES
- INSPECTED BY NRC INSPECTORS DURING CILRT VALVE LINEUP VERIFICATION
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Steam Generator Secondary System / Emergency Feedwater Correct V_alve No.
Valve Description Test Position Normal Position Position 2SGS-1015A 2PP-1015 Isol Off.
Closed Closed Yes and Cap
. Closed SG Blowdown Line 2SGS-1015B 2PP-1015 Isol Off Closed Closed Yes and Cap Closed SG Blowdown Line 2SGS-10A
"A" SG Sample Open
.0 pen Yes
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Service Air System 2SA-3028 Serv Air Line Open Closed Yes and Cap PP Isol i
Instrument Air System 2BA-304E In Ctmt PP Isol Open Closed Yes and Cap Chilled Water System - Containment, Turbine, & Auxiliary Buildings 2AC-50 Sup Hdr Isol Closed Open-Yes Chemical and Volume Control System
2CVC-1167 Pump Seal Vent Open Closed Yes 2CVC-1166 Pump Seal Vent Open Closed Yes and Cap Safety Injection System
.2SI-25A 2T-2A Smp Isol Viv Open Open Yes Fuel Pool System 2FP-35 In Ctmt Isol Closed Closed Yes sp+s e
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Hydrogen & Nitrogen Addition System 2N -21 Cont N
2 Sup Isol Open Open Yes Sampling System 2PS-7956 SIT Hdr Vent Closed Closed Yes 2PS-7957 SIT Hdr Vent Closed Closed Yes 2PS-5878 2PP-5878 Isol Open Closed No and Cap
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2PS-73 Closed Open Yes 2PS-5839A PP-5839 Isol Open Closed Yes 2PS-5839B PP-5839 Isol Open Closed Yes Reactor Coolant Pump Connections 2RCP-6008-1
"A" RCP Seal Isol Closed Open Yes 2RCP-6018-1
"B" RCP Seal Isol Closed Open Yes 2RCP-6038-1
"0" RCP Seal Isol Closed Open Yes 1