ML20101B416
| ML20101B416 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/14/1984 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8412200300 | |
| Download: ML20101B416 (4) | |
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'Af Telephone (412) 393-6000 Nuclear Division P. O. Bor 4 Shippingport, PA 13077-0004 December 14, 1984
/ Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn: Mr. Steven A. Varga, Chief Operating Reactors Branch No.1 Division of Licensing Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Environmental Qualification of Safety-Related Electrical Equipment Gentlemen:
Pursuant to the requirements of 10CFR50.49, notification is hereby made of several equipment qualification problems that will require an extension of the environmental qualification completion date established in 50.49(g).
10CFR50.49(g) establishes a goal of final environmental qualification of the electric equipment within the scope of 10CFR50.49 by the end of the second refueling outage af ter March 31, 1982 or by March '31, 1985, whichever is earlier.
For Beaver Valley Unit 1, this would be the end of our current outage which started in mid-October and is scheduled for completion on Decem-ber 24, 1984.
Numerous equipment items were scheduled for modification or replacement during this outage and these have been completed.
However, documentation to fully establish qualification must still be obtained from Westinghouse for motors associated with the 1A and 1B Low Head Safety Injection Pumps and the 1A, 18 and 1C Charging Pumps. WCAP 8754 is the Westinghouse qualification document for motors located outside containment.
We are awaiting, from Westinghouse, additional details on these motors related to material traceability, additional testing results and equipment aging assessment.
This information is not expected to be available until mid 1985.
We consider these motors to be qualified for operation based on previous Westinghouse testing and our evaluation of known component materials.
The only outstanding items are the establishment of materials traceability and final aging assessment.
An extension until November 30, 1985 is hereby respectfully submitted for these items. Justifications for continued operation are attached.
Very tr y yours, 8412200300 841214 PDR ADOCK 05000334 PDR J. J. Carey p
Vice President, Nuclear Attachment
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Beaver Valley Power Station, Unit No. 1
~-Docket No. 50-334, Licanse No. DPR-66 Environmental Qualification of Safety-Related Electrical Equipment Page 2 cc: Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Comission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Comission c/o Document Management Branch Washington, DC 20555 Director, Safety Evaluation and Control Virginia Electric & Power Company P.O. Box 26666 One James River Plaza Richmond, VA 23261 Mr. Peter Tam, Project Manager U.S. Nuclear Regulatory Comission Phillips Building Washington, DC 20555
- Mail Stop 438 -
U. S. Nuclear Regulatory Comission Office of Inspection and Enforcement Attn:
Dr. Thomas E. Murley, Regional Administrator Region 1 631 Park Avenue King of Prussia, PA 19406
4 ATTACHMENT JUSTIFICATION FOR CONTINUED OPERATION Westinghouse Motors (79-018 Tab #47)
SI-P-1A Low Head Safety Injection Pump Motor SI-P-1B Low Head Safety Injection Pump Motor Location and Safety Function The-low head safety injection pumps are located outside the containment.
The safety function for the low head safety injection pumps is to provide low pressure safety injection flow following a LOCA.
During the recirculation phase of post-LOCA operation, these pumps also provide flow to the suction of the charging pumps. These pumps may be required to
' provide flow to the suction of the charging pumps following a secondary side break inside containment.
Justification for Continued Operation
-Although. these pump motors are located in an area which is classified as harsh, the DBE temperature service conditions are not severe when compared to the normal and abnormal operational occurance values. The accident radiation service condition is an order of magnitude lower.than the value to which the motor winding was qualified.
The winding formette test referenced in Westinghouse WCAP 8754 and linked to BVPS-1 by Westinghouse letter NS-TMA-2319 establishes validity of _ the partial test data for this equipment. Further review is currently being conducted by Westinghouse to identify any materials considered to be age-degradable. This review will also include an aging assessment of these materials.
p Motor splice materials have now been qualified for 40 years plus post DBA.
Investigation of lubricant-bearing-seal system -has demonstrated a high probability of operation for duration of a 6 month accident.
f Beaver Valley Unit I has the capability to ' cross-tie the Outside Recirculation Spray Pumps to the High Head Charging Pumps which provides additional redundancy for assuring long term integrity of the recirculation flowpath.
No significant degradation of any safety function or misleading information to the operator as a result of failure of equpment under the accident environment resulting from a design basis event will occur.
l
l Westinghouse Motors (79-01B Tab #48)
CH-P-1A,1B,1C Charging Pump Motors Location and Safety Function The charging pump motors _are located outside containment.
Three charging pumps.take a suction from either the Volume Control Tank, 4_
the boron recovery and reactor makeup system,-the Refueling water storage Tank for emergency makeup, the refueling water storage tank for high head safety injection, emergency boration line, or the low head safety injection pump discharge during safety injection recirculation.
Justification for Continued Operation Although thet;e pump motors are located in an area which is classified as harsh, the DBE te'aperature service conditions are not severe when compared to the normal and abnormal operational occurance values. The accident radiation service condition is an order of magnitude lower than the value to which the motor winding was qualified.
The winding formette test
- referenced in Westinghouse WCAP 8754 and linked to BVPS-1 by Westinghouse letter NS-TMA-2319 establishes validity of the partial test data for this equipment. Further review is currently being conducted by Westinghouse to identify any materials considered to be age-degradable. This review will also include an aging assessment of these materials.
Motor splice materials have now been qualified for 40 years plus post DBA.
Investigation of lubricant-bearing-seal system has demonstrated a high probability of operation for duration of a 6 month accident..
Nultiple. diverse ' core injection flow paths are provided by the Low Head Outside Recirculation Spray and High Head Charging Pumps for providing adequate core cooling following the depressurization of the reactor coolant system post LOCA conditions.
No significant degradation of any safety function or misleading information to the operator as a result of failure of equpnent under the accident environment resulting from a design basis event will occur.
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