IR 05000482/1981014
| ML20031G706 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 10/06/1981 |
| From: | Crossman W, Vandel T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20031G702 | List: |
| References | |
| 50-482-81-14, NUDOCS 8110230506 | |
| Download: ML20031G706 (5) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION IV-Report No. STN 50-482/81-14 Docket No. STN 50-482/81-14 Category A2 Licensee: Kansas Gas _and Electric Company Post Office Box 208 Wichita, Kansas 67201 Facility Name: Wolf Creek Generating-Station Inspection at: Wolf Creek Site Inspection conducted: August 1981 Inspector: MMMMz/
/o/6/9/
T. E. Vandel, Resident Reactor Inspector Date Projects Section No. 3 Approved:
4492 W w b so/6/z/
/gqW. A. Crossman, Chief, Projects Section No. 3 Date Inspection Summary Inspection During the Month of August 1981 (Report No. STN 50-482/81-14)
Areas Inspected: Routine, announced inspection by the Resident Reactor Inspector (RRI) including follow-up to previous inspecti7n findings; plant tour observations of NDE inspection, protection of plant electrical class IE breakers, control room annunciator panel check out activities; welding activities on: (1) encapsulation sleeves for RHR isolation valve, (2) grinding on primary loop welds, and (3) cali-bration testing of Automatic Dimetrics welding machine; and electrical relay testing. The inspection activities involved 23. inspector-hours by the Resident Reactor Inspector.
Results: No violations or deviations were identified as a result of the inspection activity.
8110230506 011009 PDR ADOCK 05000482
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DETAILS 1.
Persons Contacted Principal Licensee Employees E. W. Creel, QA Manager, Corporate, Kansas Gas and Electric Company (KG&E)
- N. W. Hottel, QC Supervisor, Startup, KG&E
- J. W. Palermo, Assistant Construction Manager, Kansas City Power & Light Company (KCP&L)
- C. E. Parry, QA Engineer, KG&E
- D. W. Prigel, QA Manager, Wolf Creek Station, KG&E
- R. M. Stambaugh, QA Engineer, KG&E
- R A. Youngs, QA Supervisor, Operations, KG&E Contractor Persennel
- N. J. Criss, Audit Response Coordinator, Daniel International Corporation (Daniel)
- C. Hackney, QA Engineer, Daniel
- Denotes those in attendance during the Resident Inspector's debriefings held on August 13 and 27, 1981.
Other licensee and contractor employees were contacted during the inspection period.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (81-13-01):
Concern regarding the apparent bypassing of an Authorized Nuclear Inspectbr (ANI) inspection witness hold point.
The Daniel Project Quality Manager reviewed the circum-stances regarding the ANI notification for the second liquid penetrant test of the earlier rejected area on the weld prepa_ rations for Weld Joint F 108.
Information provided to the RRI showed that the ANI had been notified of the second test but due to a mix'up in the ANI's logs, he believed that the test had already been witnessed and so indicated that the test was not applicable to the ANI~ hold point.
The NDE Request Tag was signed to that effect.
Only later was it learned about the logging error.
The Lead ANI indicated that their system has been altered to provide a tickler file for hold point inspections that have been rejected as an aid to follow up inspection witnessing.
It is noted that both tests were performed and signed for by the same Level II Inspector and that, in addition, the second test had been witnessed by-a Daniel Level II Inspector.
The RRI stated that he had no further questions concerning this matte.
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3.
Electrical Equipment The RRI observed that a number of overcurrent relays had been removed from Class IE Switchgear NB01 and NB02 leaving tags in their place indicat-ing that the relays had been removed for testing and calibration.
The RRI conducted an inspection of the testing of Overcurrent Releys NB02-13-BN and NB02-13-BW.
The results were as follows:
a.
The RRI reviewed the procedures listed below, that were utilized for the testing of the relays:
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SU6-EL 05-16, Rev.1, dated April 2,1981,
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Induction Disc Overcurrent Relay Type 121AC53B SU6-EL 05-03, Rev. 2, dated April 2, 1981,
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Instantaneous Solenoid Overcurrent Relay Type PJCllAVIA b.
The RRI reviewed the settings utilized for the proper set points for the relays under test in Bechtel Drawing E-01024 (Q), Rev. O, Relay Setting Tabulation and Coordination Curves System NG/PG.
c.
The RRI observed the test unit utilized for the relay tests, Multi-Amp Corp. No. 011609, with calibration sticker indicating the next cali-bration due November 20, 1981.
d.
The RRI observed the testing of relay NB02-13 BN, a GE 12 IAC 53 B812A inverse time relay, with settings range of 1.5-12.
The settings called for were Tap 12, time dial 1.8 and instantaneous trip of 100 Amps.
During testing, all tap settings were checked by the tester and were found to be within the 1 5% value range.
The RRI observed that the tester had some difficulty adjusting the instanta-neous unit to just pickup at the 100 Amp point as required.
e.
The RRI obrarved the testing of relay NB02-13-BW, a GE 12 PJC11AVIA ground current relay with settings of 0.5-2.0.
The relay was adjusted for instantaneous solenoid pickup at 1.0 Amp.
f.
The 9RI reviewed the Quality Assurance Manual of Matsco (Multi-Amp Test 1ng Services Corporation) for approval by the licensee (approved on November 21,1981) and reviewed the Procedure for Qualification and Certification of Field Personnel Assigned to Nuclear Generating
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Stations, Procedure No. 110, Rev. C (approved June 13,1980).
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The certification folder.was also reviewed for the Relay Tester who performed the testing observed by the RRI.
It was established that the Tester h?d been qualified as a Level II Tester and his certification was issued on May 18, 1981.
No violations or deviations were identified.
4.
Piping Welding Activities j
Welding activities observed during the reporting period are outlined below:
a.
Encapsulation sleeve welding, for RHR Isolation Valve TEJ018, was observed by the RRI.
The fitup appeared good and the intermediate pass of welding looked good for Field Weld FW 313 on Drawing IM03EJ02 (Q).
The RRI also reviewed the Weld Control Record (WCR), the Weld Procedure Technique Number N-1-8-BA-1 and the qualifications of the welder (0-104).
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b.
On August 31, 1981, the NRC Inspector observed the grinding of primary coolant Loop 4 Weld Number F-407.
The completed weld cap was being ground down flush and polished in preparation for the preservice and inservice ultrasonic inspection.
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I c.
Calibration testing of Dimetrics Welding Machine No. G II-1270 was
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observed.
A Daniel Level II Calibration Technician was observed taking voltage and amperage readings.
Observed voltage and amperage settings and resulting measured values were as follows:
Amps Settings Measured Values Tolerance
0. 0
+ 10 Amps
53.6 150 147.7 250 242.0 Measured Villivolt Voltage Settings Readings Tolerance
0.0 1 Volt
9.6
11.1 (Conversion
12.0 1V=1.25 mv.)
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5.
Plant Tours One or more plant areas were toured several times during the reporting period to observe general cor.:truction practices, area cleanliness and storage conditions of plant equipment.
Examples of specific observa-tions are as follows:
a.
Ultrasonic testing was observed being performed by a Peabody Testing Level II Inspector on Field Weld F 043 of Drawing IM03EN02 (Q).
This was an ASME Code, Secticn III, Class 3 weld, flange-to-bellows sleeve, where both shear wave and longitudinal inspections were being conducted, b.
The RRI observed that the main incoming feeder breaker (NB0ll2)
for Class IE Switchgear NB01 had been removed from its cubicle and was sitting in the work way area.
It had been covered with a fireproof plastic, but the unit remained susceptible to accidental damage.
The RRI suggested, to the KG&E QA Manager, Wolf Creek Station, that care should be exercised to place the breaker in a protected area away from construction activity when the breaker must be out of its own cubicle.
c.
Control room annunicator panels initiation testing was observed by the RRI.
Checks being made by KG&E Startup personnel were of (1) D-C power, and (2) ES power systems, for signal inputs, response, and clearing of signals.
No violations or deviations were identified.
6.
Exit Meetings The RRI met with licensee representatives identified in paragraph 1 to discuss the various inspection findings on August 13 and 27, 1981.
The RRI also attended a management meeting held at the licensee's Corporate headquarters on August 21, 1981, where results of investi-gation activity were presented by the RIV Investigation Staff.
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