ML20008E280
| ML20008E280 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/20/1980 |
| From: | Dunn C DUQUESNE LIGHT CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-79-14, TAC-42636, NUDOCS 8010240498 | |
| Download: ML20008E280 (4) | |
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October 20, 1980 15219 United States Nuclear Regulatory Commission Office of Inspection and Enforcement Attn: Boyec H. Grier, Regional Director Region I 631 Park Avenue King of Prussia, Pennsylvania 19406
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Supplemental Information Concerning IE Bulletin 79-14 Gentlemen:
The purpose of this letter is to identify the present status of activities associated with IE Bulletin 79-14 for Beaver Valley Unit #1.
All physical inspections of the piping and the quality control records have been completed.
All piping systems have been reanalyzed and all modifications to supports on piping systems which are required to prevent or mitigate the consequences of an accident will be completed prior to startup.
Any modifications which are required to assure that code allowable stresses will not be exceeded during a seismic event on miscellaneous seismic Class I systems will be completed as operation of the plant permits.
Included in this latter category are lines in the boron recovery system or normal letdown path external to the containment.
The Oneite Safety Committee has reviewed each of these conditions and has determined that a loss of function on these lines will not impair the ability to pLice the plant in a safe cold shutdown condition.
1 We are continuing to evaluate the effects of each material substitution which have been identified and the effects on the nozzle loads on the equip-
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ment. Code Class 1 nozzS have been evaluated as acceptable by the Architect-Engineer and have been submitted to the vendor for concurrence.
A listing of Code Class 2 and 3 nozzles to be evaluated is attached as.
We believe that the original schedule provided to you in our August 14 letter may have been somewhat optimistic. A final report on the results of our efforts on Bulletin 79-14 will not be available for submittal prior to 7
March, 1981.
O y I
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1 Beaver Valley Power Station, Unit #1 Docket No. 50-334 Supplemental Information Concerning IE Bulletin 79-14 Page 2 Wa, therefore, request an extension of the time for completion of this work referenced in your November 1, 1979 letter to permit startup of the plant prior to the completion of the evaluations of the previously discussed items, namely, materials review and nozzle loadings. We intend to continue working on these items to achieve completion in accordance with our August 14, 1980 letter. Due to dependence upon the availability of qualified engineers and the timely submittal of information from vendors, we cannot commit at this time to full completion prior to March 31, 1981.
We would like to clarify that our intent is to utilize the interim criteria under which the station was returned to power in August, 1979 to define operability of systems and equipment required by technical specifi-cations. We have not requested to be relieved of tha requirement to bring the plant to a cold shutdown condition in the event of occurrence of a seismic event that is equal to or greater than.0lg.
We shall provide you with written notification of each application of this criteria including the originally calculated value and code or vendors allowable value for the component or support to which this interim criteria is being applied.
It should be understood that further evaluation will be performed to determine whether more refined calculations should be performed. Prior to requesting approval from vendors for the final calculated loads on their equipment, we will have already performed a preliminary evaluation and have every reason to believe that the equipment. vendor will grant approval. With the exception of equipment nozzles, we have not utilized the interin criteria as the basis for acceptability of any equipment or system.
If you have further question with regard to this matter, please contact my office.
Very truly yc rs,
/ /k/ Lb'11-. -
C. N. Dunn cc: Donald A. Beckman Service Resident Inspector U.S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077
< U.S. Nuclear Regulatory Commission Document Management Branch Washington, D.C.
20555
Enclosure l' Small Bore Nozzle (2-1/2 to 6 In.) To le Evaluated No. of Equipment Nomenclature Mark No.
Nozzles 1
Control Room River Water Cooling Coil VS-E-14A 6
Control Room River Water Cooling Coil VS-E-14B 6
Diesel Generator Heat Exchanger EE-E-1A 5
Diesel Generator Heat Exchanger EE-E-1B 1
Volume Control Tank CH-TK-2 3
Seal Water Filter CH-FL-3 2
Seal Water Heat Exchanger CH-E-1 2
Neutron Shield Tank Cooler NS-E-1 1
RV Supp. Neutron Shield Tank RC-ES-1 2
Containment Air Recire. Cooldag Coils VS-E-1A (1 thru 12) 24 Containment Air Recire. Coolisg Coils VS-E-13 (1 thru 12) 24 Containment Air Recire. Cooling Coils VS-E-1C (1 thru 12) 24 Degasifier Recirculation Pump BR-P-7A 1
Degasifier Recirculation Pump BR-P-7B 1
Degasifier Heat Exchanger BR-EV-2A 2
Degasifier Heat Exchanger BR-EV-2B 2
Control Room A/C Condenser Unit VS-E-4A 3
Control Room A/C Condenser Unic VS-E-4B 3
Steam Generator RC-E-1A 3
Steam Generator RC-E-1B 2
Control Room A/C Unic VS-AC-1B 6
CRDM Shroud Cooling Coils VS-E-2A-1 4
CRDM Shroud Cooling Coils VS-E-2B 2
CRDM Shroud Cooling Coils VS-E-2C 2
CRDM Shroud Cooling Coils VS-E-2B-1 1
CRDH Shroud Cooling Coils VS-E-23-2 1
CRDM Shroud Cooling Coils VS-E-2C-1 1
CRDM Shroud Cooling Coils VS-E-2C-2 1
Excess Letdown Heat Exchanger CH-E-4 2
Reactor Coolant Pump Motor RC-P-1B 3
Reactor Coolant Pump Motor RC-P-1C 1
Stator Oil Cooler Outlet 2
Lube Oil Cooler 1
Boron Injection Tank SI-TK-2 1
Reactor Coolant LA Pump Seal Pot RC-TK-3A 2
Reactor Coolant 1B Pump Seal Pot RC-TK-3B 2
Reactor Coolant 1C Pump Seal Pot RC-TK-3C 2
Emergency Diesel Generator EE-EG-2 2
Lube Oil Cooler 2
Luhe 011 Cooler 2
Lube 011 Strainer 2
Lube Oil Cooler 4
Stator Cooler 6
Primary Plant Demineralized Water Storage Isolation VV1-15A-Q 3
,.. (cont.)
Small Bore Nozzle (2-1/2 to 6 In.) To be Evaluated Page 2 l
No. of Ecuipment Nomenclature Mark No.
Nozzles High Head Safety Injection Pump CH-P-1A 1
High Head Safety Injection Pump CH-P-1B 1
Righ Head Safety In.iection Pump CH-P-lC 1
Cesium Ion Removal Heat Exchanger BR-I-1A 2
Cesium Ion Removal Heat Exchanger BR-I-1B 2
Coolant Recovery Filter BR-FL-1A 1
Coolant Recovery Filter BR-FL-13 1
Condenser Air Ejector CN-EJ-1A 1
Condenser Air Ejector CN-EJ-13 1
Refueling Water Storage Tank QS-TK-1 1
Primary Drain Transfer Pump DG-P-1A 1
Primary Drain Transfer Pump DG-P-1B 1
Primary Drain Transfer Accumulator DG-TK-1 1
Refueling Water Storage Tank Cooler QS-E-1A 1
Refueling Water. Storage Tank Cooler QS-E-1B 1
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