IR 05000397/1983021
| ML20024C343 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/28/1983 |
| From: | Dodds R, Feil R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20024C339 | List: |
| References | |
| 50-397-83-21, NUDOCS 8307120537 | |
| Download: ML20024C343 (5) | |
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S. NUCLEAR REGULATORY COMMISSION
REGION V
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-Report No.
50-397/83-21 Docket No.
50-397 License No.
CPPR-93
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Licensee:
Washington Public Power Supply System P. O. Box 968
,Richland, Washington 99352 Facility Name:
Washington Nuclear Project No.2 (WNP-2)
Inspection-at:
WNP-2 Site, Benton County, Washington Inspection conducted:
May 1983
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Inspector:
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R. A. Feil, Senior Res'ident Inspector D6te Signed
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l Approved By:
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R. T. Dodds, Chief D6te Signed Reactor Projects Section No.1 Gummary:
Inspection during May 1983 (Report No. (50-397/83-21)
Areas Inspecteg Routine, unannounced resident inspection of preoperational tes.t procedure review and witnessing, fuel receipt and storage, and independent inspection effort. The inspection involved 67 inspector-hours onsite by the NRC operations resident inspector.
Results: No items of noncompliance or deviations were identified.
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DETAILS
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Persons Contacted
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Washington Public Power Supply System (WPPSS)
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- G. K. Afflerbach, Assistant Plant Manager
. *G. L. Blackburn, Test Group Manager C. J. Becker, Shift Manager R. J. Talbert, Senior Engineer
- J. J. Bufis,. Test Group Manager R. A. Burk, Test Engineer
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C. A..Cauthon, Planning / Scheduling Supervisor J. W.' Dabney, Operations Engineer
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W. S. Davison, Test Group Supervisor J. F. Demelo, Test Engineer W. J. Holle, Test Group Supervisor
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- L. D.-Kassakatis, Test Group Manager R. B. Koch, Test Group Supervisor i
R. L. Koenigs, Test Group Supervisor G. T. Larson, Administrative Supervisor G. R. Lawrence, Test Group Supervisor J. D. Martin, Plant Manager
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F. J. Mizell,-Test Engineer
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~C. M. Powers,, Reactor Engineering Supervisor
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M. A.:Schmitz, Test Engineer
-*Uenotesthosepresentatmonthlyexitmeeting.
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The inspector conferred.with other licensee and contractor personnel during the report period.
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2.
General'
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The inspector observed'activitiesDin progress and facility status during
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, general'inspe'ctions and, tours of the facility.
Particular note was made
of housekeeping,* protection' of equipment, and component and valve
. identification.
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The. inspector attended several management. status and operational meetings
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with the licensee and contractor personnel during the inspection period.
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No items of noncompliance or deviations were identified.
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3.
Preoperatidnar Test Procedure Review Reactor Recirculation System (RRS)
The inspector reviewed Preoperational Test Procedure No. 3.0-A, Reactor Recirculation System..The inspector verified that the procedure had been
-written and. approved in accordance with the FSAR, Regulatory Guide 1.68,
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'and other regulatory and licensee requiremer.ts. The inspector identified some minor discrepancies in the procedure.. The licensee stated that appropriate changes would be made.
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No items of noncompliance or deviations were identified.
4.
Preoperational Test (PT) Witnessing a.
Control Rod Drive System PT 13.1-A The inspector witnessing portions of the control rod scram time testing. The testing consisted of withdrawing individual control rods to position 48, recording accumulator pressure, observing position indication, and then recording the actual control rod speed. The inspector verified that (1) tests were conducted by qualified personnel utilizing properly installed test equipment, (2)
appropriate data was collected and/or recorded, and (3) tests were conducted utilizing approved procedures.
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Standby Liquid Control System (SLC) PT 10.0-A The inspector witnessed attempts to conduct the Standby Liquid Control System injection tests for Systems A and B.
The inspector verified that procedures, personnel and test equipment were appropriate for the tests. The test for SLC
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failed because the pump did not start. All other system components operated as required. The pump failed because the three amp slow blow fuse in the pump control circuit failed. The ' test for SLC 'B'
failed because the pump stopped after four minutes of operation. The pump stopped because a five amp quick blow fuse _in the pump control circuit failed after the squib valve shorted following firing. The licensee is evaluating the problem with the Architect Engineer. The licensee intends to test either SLC A or SLC B in its ' entirety following resolution of the pump failure (fuse) problem.
No items of noncompliance or deviations were identified.
5.
System Lineup Test Witnessing
Standby Power Supply System
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The inspector observed some testing on Diesel Generator B conducted-in accordance with System Lineup Test S47.1-6, Starting Reliability Tests' of Standby Diesel Generators A and B.
The tests were being conducted as-required by Regulatory Guides 1.68 and 1.108.
The diesel generator failed in Test No. 35.
A lockout ar.d overspeed trip occurred on the attempted start. The licens'e could not determine the failure mode. The licensee repeated several restarts of the diesel generator without failure. The licensee performed electrical and mechanical checks in the DG in an attempt to ascertain the problem. No anomalies were identified.
The licensee subsequently tested the diesel generator. All 35 required starts were determined to be valid and successful.
No items of noncompliance or deviations were identified.
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Fuel Receipt and Storage The first shipment of 28 fuel assemblies arrived at WNP-2 on May 23, 1983. The inspector verified that the licensee inspected the fuel assembly shipping containers for external damage for outer and inner
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container seal integrity and radiation. A radiation work permit had been prepared and health physics procedures were in place for the fuel receipt. The inspector verified that fuel handling procedures were utilized and necessary documentation prepared.
The fuel assembly containers were unloaded in Warehouse No.5.
The inner container, with two fuel assemblies, was removed from the outer container and loaded onto a flatbed truck. After four inner containers were loaded onto the truck, they were transported to the crane bay in the reactor building. The lists were removed from the inner containers. The inner containers, without lids, with their fuel assemblies were fitted in the lif ting basket and hoisted to the refueling floor. The fuel assemblies were removed from their inner containers and placed in the inspection stand on the refueling floor. The assemblies were inspected in accordance with the procedure, channeled, and placed in the dry spent fuel pool.
No items of noncompliance or deviations were identified.
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Preoperational Test Program The following significant activities of the preoperational test program occurred during this report period, a.
Testa Completed PT 7.1 HPCS - Mechanical PT 7.2 IIPCS - Electrical
SLT 104.0-3 Security System Shop Test
PT 107.0-A Reactor Building Crane
SLT 47.1-6 Standby Diesel Generator B Reliability Starts b.
Other Significant Activities Receipt of first fuel shipment
MSIV disassembly and inspection complete
CRD restraint steel installed
Westinghouse personnel repairing turbine' blades
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7.
Management Meeting The inspector met with the licensee's representatives (denoted in paragraph 1) on June 7,1983, to discuss the results of the inspection efforts and to receive a status report on the preoperational test program.
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