IR 05000334/1981014
| ML20010B270 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/24/1981 |
| From: | Ebneter S, Sassani A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20010B269 | List: |
| References | |
| 50-334-81-14, NUDOCS 8108140296 | |
| Download: ML20010B270 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 81-14 Docket No. 50-334 License No. OPR-66 Priority
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Category C
Licensee: Duquesne Light Company Post Office Box 4 Shippingport, Pennsylvania 15077 Facility Name: Beaver Valley Power Station, Unit 1 Inspection at: Shippingport, Pennsylvania Inspection conducted:
June 1-5,1981 Inspectors:
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A.D. Sassani, Jr. Reactor Inspector date's'igned
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date signed 9/'tYf0/
Approved by:
ot(Dirud 1A>
Stewart D'. Ebneter, Chief, Plant Systems da'te i(igned'
Section, Engineering Inspecticn Branch Inspection Summary:
Inspection on June 1-5, 1981 (Inspection Report No. 50-334/81-14)
Areas Inspected: Routine, unannounced inspection by a regional based inspector of quality related documentation, records, and work activities associated with Unit No. I mcdifications and instrumentation program including:
electrical and instrumentation work activities, documentation, and records pertaining to procurement, installation, inspection, modifications, and instrumentation pro-gram implementation. The inspection involved 31 inspection hours onsite by one NRC regional based inspector.
Results: No item of noncempliance was identified.
00108140296 810729 PDR ADOCK 05000334-O PDR
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DETAILS 1.
Persons Contacted Duquesne Light Company
- R. Balcerek, Nuclear Engineering and Refueling Supervisor
- G. Beatty, Quality Assurance Engineer
- F.G. Curl, Senior Construction Specialist J. Forney, Instrument and Control Engineer
- R.L. Hansen, Maintenance Supervisor
- J.A. Indovina, Onsite Electrical Engineer G. Kilantonis, Onsite Electrical Engineer
- F.J. Lipchick, Senior Compliance Engineer
- J. Malloy, Quality Assurance Engineer J. Rathke, Instrument and Control Foreman
- J.D. Sieber, Manager, Nuclear Safety and Licensing
- H.M. Siegel, Onsite Engineering Group Supervisor
- S.J. Smajda, Senior Construction Specialist
- J.E. Starr, Senior Engineer R. Swiderski, Construction Superintendent, Nuclear
- N. Tonet, Manager Nuclear Engineering
- J. A. Werling, Station Superintendent U.S. Nuclear Regulatory Commission
- D. Beckman, Senior Resident. Inspector 2.
Auxiliary Feedwater System Modification The requirements for this modification are delineated in NUREG-0578 and NUREG-0737.
The inspector reviewed quality related work activities, documentation, and records relative to the modification to ascertain whether applicable requirements have.been met.
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Documentation reviewed for this determination include:
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Modification Work Procedure, MWP No. 299-1, Revisions 0 and 1 Design Change Package, DCP No. 299, Revision 0, Auxiliary Feedwater Flow Indication Modification.
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MWP No. 299-2, Revision 0 and DCP No. 299, Revision O',
Upgrade of the Auxiliary Feedwater Syste.
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MWP No. 299-3, Revision 0 and DCP No. 299, Revision 0, Mod-
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ification to the Auxiliary Feed Pump Start and Discharge
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Valve Control Circuits.
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Engineering Management Procedure, No. 2.6, Revision 2, Classification of Structures Systems and Components.
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Engineering Management Procedure, No. 2.8, Revision 6, Handling of Design Change Packages.
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QA Procedure, DC-4, Revision 2, Procurement Document Contro.
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QA Procedure, OP-4, Revision 6, Design Change Control.
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QA Procedure, OP-5, Revision 3, Procurement Control.
QA Procedure, OP-9, Revision 1, Technical Procedure Control
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for Operations and Maintenance.
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QA Procedure, OP-10, Revision 3, Maintenance and Modification Planning.
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One Line Diagram,11700-RE-1U-6E-1,11700-RE-1AB-6F-1, and 11700-RE-1AC-6H-1, 120vac Vital Bus.
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Arrangement Drawing, 11700-RE-25MCA-0D-1, 11700-RE-25MCC-00-l 1, and 11700-RE-25MCD-0C-1, Secondary Process Rack.
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FT-FW100 A, B, and C, Calibration Sheets, March 27, 1981.
Instrument Loop Elementary, 11700-RE-21WS-0A-1, Auxiliary
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Cable Termination Slips, IFWEANX004 and IFWEARX001.
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Cable Pull Slips, IFWEANX004 and IFWEARX001.
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Purchase Order No. 2BV-234, Reel No. 112.
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Conduit Drawing, SECO-C-299-1 and 2, Revision 2, Cable Vault Area, Elevation 735 feet.
One Line Diagram,11700-RE-IV-6B-2,125 VDC.
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4 KV Wiring-Diagram, 11700-RE-8AM-6A-1, Sheet 36 and 11700-RE-8Y-8A-1, Sheet 23.
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Feedwater Elementary, 11700-RE-21GZ-2A-1, Sheet 1; 21HA-2A-1, Sheet 2; 21HD-2A-2, Sheet 5; 21HE-2A-2, Sheet 6; and 21HF-1A-2, Sheet _.
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Purchase Order No. BV-1118-13, Auxiliary Relays.
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b.
Areas examined for this determination include:
Flow Indication Power Supplies, Located in Secondary Process
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Racks A, C, and D, Channels I, II, and IV, Elevation 713 feet.
Installed Supports and Conduit Nos. ICX408YB,- 1CX108RC, an'
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ICX308BA, Auxiliary Feedwater Pump Room, Elevation _735 fet
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Installed Auxiliary Relay 3-AFPA, Relay Panel 35R, Emergency
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Switchgear Room, Elevation 713 feet.
During the inspection of Secondary Process Rack D, Channel IV, the inspector observed that instrument No. TRB-RSI508 was not secured in the instrument rack and blank cover plate for location C-4 was not secured to the panel front. The inspector determined that this non safety grade loop was declared inoperative September 19, 1980 and was logged in the Out of Service Log, Sheet 13-4.
However, the licensee could not provide a purchase order number to which the defective RTD was ordered. The inspector indicated-that this loop was for containment sump temperature and although it was not safety grade at this time, it would be upgraded to safety grade in the near future. The inspector indicated that'
this would be an inspection follow up item to determine that the
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devices are secured in the rack and the status of.the purchase order for the RTD.
This item will be the subject of a further review by an NRC in-spector during a subsequent IE inspection (50-334/81-14-01).
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Instrument Program The inspector reviewed quality related documentation relative to the instrument program to ascertain whether applicable requirements have been met.
Documentation reviewed for this determination include:
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Station Administrative Procedure, Maintenance, Chapter 8, Re-vision 2.
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Conduct of Maintenance Ma6ual.
Section Subject Revision
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A General Rules for Implementation
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Corrective Maintenance
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Maintenance Surveillance
E Preventive Maintenance
F Control and Calibration of Measuring Devices
G Material Procurement 5~
K Equipment History File
L Maintenance Planning and Scheduling-
0 Calibration Program.
P Control of Design Changes.
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No item of noncompliance was identified.
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Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the-inspection June 5, 1981.
In addition,-the NRC Senior Resident Inspector, Mr. D. Beckman, attended the meeting.
The inspector. summarized the purpose, scope and findings of the in-spection.
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