IR 05000267/1982019
| ML20027C993 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/29/1982 |
| From: | Redano R, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20027C989 | List: |
| References | |
| 50-267-82-19, NUDOCS 8210280149 | |
| Download: ML20027C993 (9) | |
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APPENDIX B U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report: 50-267/82-19 Docket: 50-267 License: DPR-34 Licensee:
Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201 Facility Name:
Fort St. Vrain Nuclear Generating Station Inspection At:
Fort St. Vrain Site, Platteville, Colorado Inspection Conducted: August 9-13, August 30-September 3, 1982 Inspector: M [ be 9-29-F#
R.
l. Hedano, Heactor inspector Date ReactorProjectSectionA Approved:
/ 7Sf/ad 9-2 9-E A h
I. P. Westerman, chlet Date ReactorProjectSectionA Inspection Summary Inspection Conducted August 9-13, and August 30-September 3, 1982 (Report 50-26//82-19)
Areas Inspected:
Routine, unannounced inspection of receipt, storage, and handling of equipment and materials program, design change program and mainte-nance practices.
The inspection involved 53 inspection hours by one NRC inspector.
Results: Within the three areas inspected, one apparent violation was identified in one area (failure to maintain test records of safety-related design change, paragraph 4), and no violations or deviations were identifiad in two areas.
(*210280149 821006
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PDR ADOCK 05000267 Q
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Details 1.
Persons Contacted Public Service Company of Colorado 1*M. McBride, Technical / Administrative Services Manager
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- D. Warembourg, Manager of Nuclear Production i*E. Hill, Station Manager 1*L. Singleton, Superintendent of QA Operations
- R. Craun, Supervisor of Nuclear Site Engineering i J. Gahm, Manager of QA R. Husted, QA Auditing Coordinator T. Prenger, QA Engineering Coordinator R. Teel, Storekeeper S. Rodda, QC Inspector D. Glenn, Electrical Engineer i W. Franek, Site Engineering Manager R. Hamblin, Senior Technician R. Burchfield, Results Engineering, Supervisor H. Starner, Site Nuclear Construction Coordinator R. Gunnerson, Engineer W. Craine, Superintendent of Maintenance G. Redmond, Maintenance QC Supervisor i T. Orlin, Superintendent of QA Services i M. Black, Superintendent of Operations
- Denotes presence of the exit interview conducted on August 13, 1982.
iDenotes presence at the exit interview conducted on September 3, 1982.
Other licensee personnel were contacted during the course of the inspec-tion activity.
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2.
Receipt Storage and Handling of Equipment and Materials Program I
The NRC inspector examined the licensee's procedures to ascertain whether adequate administrative controls have been established to assure that the receipt, storage and handling of safety-related material and equipment
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l conformstoregulatoryrequirements.
From the procedures examined, the NRC inspector deterrained that adequate administrative controls exist in the areas of receipt inspection tagging for storage, segregation of nonconforming material, disposit. ion of nonconforming items documentation ofreceiptinspection,storageinappropriateenvironmentalconditions,
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controlled release of stored items, maintenance of stored items, and l
handling of materials.
The procedures examined are listed below.
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Procedure Number Issue Title Date Q-7
Control of Procured Material July 13, 1982 and Services Q-13
Handling Storage and Shipping April 30, 1981 Q-15
Control of Nonconforming Items June 23, 1982 Q-16
Corrective Action System March 31, 1982 The NRC inspector evaluated the licensee's implementation of the afore-mentioned procedures by selecting safety-related items received in the licensee's warehouse and examining the licensee's adherence to procedures for these selected items.
The-receipt inspection, disposition and storage practices for the items listed below were found to conform to licensee's procedural requirements.
Item No.
Description N4266 Instrument Fittings N3760 Compressor Parts N4060 Round Steel N4068 Repeaters and Selectors N4104 Solenoid N4091 Relay The NRC inspector also examined the storage practices for selected items requiring special environmental conditions.
The environmental conditions for the storage of the items listed below were found to conform to the licensee's procedural requirements.
Item No.
Description N4205 Welding Electrodes N3624 Welding Electrodes N3971 Welding Electrodes The segregation and control of nonconforming item N3679 was determined to be adequate by the NRC inspector.
The tagging and marking of each selected item allowed traceability of the item back to its purchase and receipt documents.
All licensee personnel interviewed appeared knowledgeable of the procedural requirements related totheirareaofjobresponsibility.
No violations or deviations were identified in this portion of the inspec-tio.
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3.
Design Changes and Modifications The NRC inspector examined the licensee's design change and modification program to determine whether the implementation of this program conformed to regulatory requirements and the licensee's procedures.
Selected safety-related design change packets, known as change notices (CN) in the licensee's documentation system, were audited to ascertain whether adequate doccaentation exists in the areas of QA review of safety-related changes test procedure review and approval, test results, drawing changes, aoolicable operating procedure changes, 10 CFR 50.59 compliance, and Technical Saecification compliance.
The NRC inspector discovered that in many cases t1e licensee issues construction work packages (CWP) and work authoriza-tions (WA) to accomplish the field wor ( specified in the associated CN.
The first group of selected CN's are design changes which have been fully completed.
A list of these CN's and their associated CWP's or WA's are presented below.
CN Associated Completion-Number CWP or WA No.
Description Date 809 CWP 364 Install Thermal Wells in February 1982 HE Dryer System 809A NA Install Temperature February 1982 Switches in HE Dryer System 300 NA-Install New Fire Detectors November 1981 Rev. A-D 178A CWP 331 Add AP Indicators on September 1981 Condensate Polishers O
973 CWP 396 Change Control Rod July 1981 Sequencing 758 CWP 392 Install Instrument Valves February 1982 on Instrument Legs of Level Indicators to Facilitate Calibration 653 WA 862-73 Install Keyswitch on November 1981 Radiation Monitoring Circuit In examining the above CN's, the NRC inspector noted that there was
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approximately an 18-24 month delay from the time the field work was completed to the time the CN documentation was completed.
It appears that this lag time has been reduced as a result of staffing additions made by
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S the licensee's nuclear design department.
All functional tests (FT's)
examined for the above CN's were technically adequate.
Documented results of the FT for CN 653 were missing.
Technical Specification 7.4.a.3 requires that written procedures be maintained for test activities of safety-related equipment.
Licensee Procedures Q-17, Issue 4 entitled " Quality Records" and Q-11, Issue 3, entitled " Test Control'I also require documentation of test results in sections 4.2.3 and 3.0 respectively.
The absence of documented FT results for CN 653 is a violationoftheaboverequirements(50-267/8219-01).
The second group of CN's examined were those for which field work was completed in the last year but for which document update is still outstand-ing.
A list of those CN's and their associated CWP s is presented below.
CN CWP CWP Completion Number Number Description Date 868
Installation of Charcoal November 1981 Exhaust Filters 1392 281 Installation of Relay in April 1982 Control Rod Drive Circuit 1405 219 Installation of Junction August 1981 Box and Cable 1405A 223 Replacement of Damaged August 1981 Cable 650 115 Installation of Reactor November'1981 Air Thermocouples 713 107 Installation of Steam April 1982 Thermocouples The documentation of the work completed on the above CN's appeared to meet all procedural requirements.
All FT's examined for the above CN's were technically adequate.
While examining the aforementioned CN's, the NRC inspector noted that in some cases the FT's were filed with the CN packet while in other cases they were filed with the CWP or WA associated with the CN.
It appears thatthislackofuniformityinrecordsstoragecoupledwiththesegregated procressing of CN's and CWP s were a proximate cause of the cited viola-tion.
Thelicensee'sQAmanagerinformedtheNRCinspectorthatinAugust of 1980 the processing of CN's and CWP's was changed to give uniform treatment to FT documentation.
It appears that this new processing method has improved the documentation consistency for CWP's completed after August 1980.
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4.
Maintenance The NRC inspector reviewed the records associated with maintenance activities to determine whether:
a.
Required administrative approvals were obtained prior to initiating the work.
b.
Limiting condition for operation were met while the components or system were removed from service.
c.
A) proved procedures were used where the activity appears to be beyond tie normal skills of the worker.
d.
Inspections were made in accordance with the provisions of the licensee's requirements.
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Functional testing and calibrations as necessary were completed prior to returning the equipment to service.
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Quality control records are complete.
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Activity was accomplished by qualified personnel.
h.
If the activity was accomplished by an outside contractor the contractor was controlled in accordance with the licensee,s approved QA program.
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The licensee has evaluated system failures and reported them in accordance with the Technical Specifications.
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Corrective and preventive maintenance records are assembled and stored as part of the maintenance history.
The licensee's implementation of the maintenance program appeared to satisfy the above criteria.
Selected plant trouble reports PTR's)were examinedtodeterminewhetheradequatedocumentationexists(inthefollow-Ing areas:
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Provisions for fire protection / prevention, cleanliness, and house-keeping.
b.
Inspection and hold points.
c.
Testing requirements.
d.
Procedure conforms to the licensee's administrative requirements.
e.
Provisions for return-to-service.
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Provisions for adherence to Technical Specification during the maintenance activity.
g.
Properly specified parts and materials are identified for use in the activity.
h.
Consideration is given to the radiological hazards involved.
A list of the PTR's examined is presented below.
1-410 2-150 2-423 3-123 1-414 2-151 3-27 3-161 1-415 2-184 3-43 3-295 1-412 2-241 3-36 1-425 2-288 3-66 2-23 2-387 3-69 2-116 2-416 3-70 The work performed on the above PTR's appeared to be in conformance with the licensee's procedures and adequately documented.
While auditing PTR's 2-416 and 2-423 for materials traceability, the NRC inspector noted that in some instances material utilization lists were filed with the maintenance procedure used to perform the PTR while in other cases, such lists were filed with the equipment history of the equipment worked on in the PTR. The NRC inspector expressed concern to themaintenanceQCsupervisorthatthisnonuniform, compartmentalized system of maintenance records documentation may lead to problems similar to those experienced in the design change area.
The NRC inspector reviewed the list of outstanding safety-related PTR's and determined that the licensee is performing the maintenance in a timely manner and an excessive backlog of PTR's is not developing.
No violations or deviations were identified in this portion of the inspec-tion.
5.
Exit Interviews Exit interviews were conducted on August 13, 1982, and September 3, 1982, with those persons denoted in paragraph 1 of this report.
At the inter-views, the inspector discussed the findings indicated in the previous paragraphs and the findings obtained from the 17 onsite hours spent evaluating the disposition of outstanding items related to the Manual Class I/ Class II Valve Study.
The licensee acknowledged these findings.
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