IR 05000482/1986026
| ML20207L657 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek |
| Issue date: | 12/30/1986 |
| From: | Hunnicutt D, Greg Pick NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20207L642 | List: |
| References | |
| 50-482-86-26, NUDOCS 8701120297 | |
| Download: ML20207L657 (6) | |
Text
o.
,.
APPENDIX U.S. NUCLEAR REGULATORY COMISSION
REGION IV
NRC Inspection Report:
50-482/86-26 License:
NPF-42 Docket:
50-482 Licensee:
Kansas Gas and Electric Company P. O. Box 208 Wichita, Kansas 67201 Facility Name: Wolf Creek Inspection At:
Burlington Kansas Inspection Conducted:
October 14-16 and November 17-21, 1986 Inspector:
WW hM"M l'l3b
-
G.A.Pf;tk(#eactorSafetyBranch Reactor Engineer, Operations Date Sectihn, Approved:
$// k ~u n u d
/J-/30/5'd
~
D. M. Hunnicutt, Chief, Operations Section Date
'
Reactor Safety Branch Inspection Summary.
Inspection Conducted October 14-16 and November 17-21, 1986 (Report 50-482/86-26)
Areas Inspected:
Routine, unannounced inspection of complex surveillance tests and surveillance test procedures and records.
Results: Within the areas inspected, no violations or deviations were identified, bb K $hhe2 PDR
-
I
..
,
-2-DETAILS
1.
Persons Contacted Kansas Gas and Electric Company
- G. J. Per.dergrass, Licensing Engineer
'
.
- R. Logsdon, Site Chemist
- J. A. Zell, Manager, Nuclear Training
- F. T. Rhodes, Plant Manager
- G. Boyer, Deputy Plant Manager
!
- C, E. Parry, Superintendent, Quality Engineer
- M. H. Megehee, Compliance Engineering
- J. L. Blackwell, Fire Protection Coordinator
- K. M. Thrall, Sr. Engineering Supervisor
- C. M. Estes, Superintendent of Operations
+*W. M. Lindsay, Supervisor Quality System
- J. A. Bailey, Interium Site Director
- A. A. Freitag, Manager, NPR-WC
- M. Nichols, Plant Superintendent
- J. Ives, Site Health Physicist
- K. R. Peterson, Lead Engineer, Licensing
+*H. G. Williams, Superintendent of Regulatory, Quality, and Administrative Services
,
+ H. K. Chernoff, Licensing Engineer NRC
+*J. E. Cummins, Senior Resident Inspector
+*G. A. Pick, Reactor Engineer
- R. P. Mullikin, Project Inspector
+*B. L. Bartlett, Resident Inspector
+ Attended exit interview on October 16, 1986.
- Attended exit interview on November 21, 1986.
2.
Surveillance The NRC inspector verified that the Surveillance Technical Specification (STS) test procedures listec' below were properly approved in accordance with Wolf Creek Generating Station (WCGS) Administrative Procedure ADM 07-100, Revision 28, " Preparation, Review, Approval and Distribution of WCGS Procedures," dated January 16, 1986:
STS Number Revision Title Date l
BG-001
Doron Injection Flow Path Verification 05-23-85
!
.
.-
-
.
.
. -
.
.
-
.
o...
-3-SF-001
Control and Shutdown Rod Operability 05-29-86 Verification
WL-001
Weekly Surveillance Logs 06-03-86 RE-012
QPTR Determination 11-12-85 i
CR-001
Shift Log For Modes 1, 2 & 3 05-16-86 IC-230
Analog Channel Operational Test of the Balance of Plant Engineered 10-07-86 Safety Features Actuation System
PE-022
Steam Generator Tube Inspection 10-07-86
!
ML-001
Monthly Surveillance Log 07-08-86 EP-001
Safety Injection Accumulator 05-10-85 j
Discharge Valva Test i
BG-002
ECCS Valve Check And System Vent 09-30-86
.
MT-044
Containment Tendon Inspection 06-18-85
I EN-001
Containment Spray System Valve 07-16-85 Verification AL-103
Turbine Driven AUX FW Pump Inservice 02-04-86 Pump Test ADM 04-020
Chemistry Surveillance Program 09-30-86
'
MT-019
125 VOC Class IE Quarterly Battery 06-25-85 i
Inspection NB-005
Breaker Alignment Verification 04-22-85
,
Electric Motor Driven Fire Pump 02-24-86 1FP01PA Monthly Operation IC-818
Protectowire Trip Actuating Device 08-15-85 Operational Test For Zones 201, 202,
203, 204, 205, 206, 215, 216, 217, 218, and 220 t
.
The NRC inspector examined the technical content of the procedures listed
!
below and verified that testing of systems and components ensured compliance with the requirements specified in Technical Specifications (TS).
]
The procedures included:
prerequisites, precautions and limitations for i
the surveillance specified, acceptance criteria, and instructions to assure systems and components were restored to operation.
,
.
.
I
.- -
-
-
-
- -
-
-
__
_ _- _ _ - __ _ __ _
....
-4-BG-001
Boron Injection Flow Path Verification 05-23-85 SF-001
Control and Shutdown Rod Operability 05-29-86 Verification WL-001
Weekly Surveillance Logs 06-03-86 RE-012
QPTR Determination 11-12-85 CR-001
Shift Log For Modes 1, 2 & 3 05-16-86 IC-230
Analog Channel Operational Test 10-07-86 Of The Balance Of Plant Engineered Safety Features Actuation System PE-022
Steam Generator Tube Inspection 10-07-86 ML-001
Monthly Surveillance Log 07-08-86 EP-001
Safety Injection Accumulator Discharge 05-10-85 Valve Test BG-002
ECCS Valve Check And System Vent 09-30-86 EN-001
Containment Spray System Valve 07-16-35 Verification
.AL-103
Turbine Driven AUX FW Pump Inservice 02-04-86 Pump Test MT-019
125 VOC Class 1E Quarterly Battery 06-25-85 Inspection FP-602
Electric Motor Driven Fire Pump 02-24-86 1FP01PA Monthly Operation IC-818
Protectowire Trip Actuating Device 08-15-85 Operational Test For Zones 201, 202, 203, 204, 205, 206, 215, 216, 217, 218, and 220 The NRC inspector reviewed completed test data for the listed procedures on the dates specified.
The tests were in conformancq with TS and rocedural requirements, the test reviews were conducted per ADM 02-300, p' Surveillance Testing," and tests were performed within specified TS frequencies.
_-
-..
-5-STS Surveillance Number Title Dates SF-001 Control and Shutdown Rod Operability 04-07-86 Verificatior.
05-05-86 06-11-86 07-01-86 08-04-86 RE-012 QPTR Determination 09-10-86 09-17-86 09-24-86 10-01-86 10-08-86 10-21-86 EP-001 Safety Injection Accumulator Discharge 05-24-86 Valve Test 06-24-86 07-25-86 8-25-86 9-25-86 BG-002 ECCS Valve Check And System Vent 05-23-86 06-23-86 C7-23-86 08-23-86 09-23-86 AL-103 Turbine Driven AUX FW Pump Inservice 05-29-86 Pump 06-29-86 07-28-86 08-29-86 09-28-86 MT-019 125 VDC Class IE Quarterly Battery 07-10-85 Inspection 10-16-85 01-15-86 04-13-86 07-23-86 IC-230 Analog Channel Operational Test of the 01-27-86 Balance of Plant Engineered Safety 02-25-86 04-01-86 05-02-86 05-30-86 07-07-86 08-04-86 09-04-86 10-10-86 11-10-86 k
..
..
a u.
-6-
,
While reviewing the completed STS MT-019, dated October 16, 1985, the NRC inspector observed that the value of the average specific gravity (SG) for battery NK-11 was out-of-specification per the procedure.
The NRC inspector expressed some concerns, in that, according to the Surveillance Test Routing Sheet (STRS) the post-test review had, apparently, failed to identify any problem.
This is an Unresolved Item (482/8626-01) awaiting a safety significance determination of this information in a subsequent
,
inspection.
3.
Complex Surveillance Test The NRC frcpector verified that STS KJ-001A, Revision 3, " Integrated DG and Safeguards Actuation Test-Train A" provided:
a specific title and revision number with each page clearly identified as to revision number and page number; a purpose including what TS the procedures completion would satisfy; means for coordinating various group activities and verification and sign-off of actions; independent verification on critical steps; short, concise and clear instructions with ample space for recording of data on data sheets; acceptance criteria specified as ranges that were compatible with TS requirements; for alignment of individual equipment (valves, breakers, relays, etc.) with unique nomenclature; information regarding the correct direction of activation, and the means for system restoration.
The NRC inspector verified that some of the intended items validated within STS KJ-001A and/or KJ-0018 were emergency diesel generator; capability to reject its largest load while maintaining voltage and frequency; load shedding and sequencing during loss of offsite power and/or safety-injection; ability to operate for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 110 percent of design loading; and full load time, voltage and frequency requirements.
No violations or deviations were identified.
4.
Unresolved Item An unresolved item is one about which nore information is required to determine whether the item is acceptatle or is a violation.
One unresolved item is identified in paragraph 2.
5.
Exit Interview The NRC inspector met with those persons as indicated in paragraph 1, on October 16, 1986, and November 21, 1986.
At this meeting, the scope of the inspection and the findings were summarized.