ML20106D570
| ML20106D570 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/08/1984 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20106D571 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 GL-83-37, GL-83-43, NUDOCS 8410260052 | |
| Download: ML20106D570 (2) | |
Text
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Telephone (412) 4564000 Nuclear DMsion s
$iEpp*n*g ' rt, PA 150774004 October 8, 1984 tih b
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Director of Nualear Reactor Regulation UnitedStaterfuclearRegulatoryCommission Attn: Mr. Steveo A. Varga, Chief Operating Reactors, Branch No.1 Division of Licensing Washington, DC 20555
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Reference:
Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Proposed Operating License Change Request No. 94 Gentlemen:
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Three (3) originals and thirty-seven (37) copies of an Application
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,- for Amendment to our Operating License to incorporate the applicable 1
" requirements of NUREG-0737 specified by Generic Letter 83-37.
2)
Forty (40) copies of documents designated Attachments A and B which setforth the change in technical specifications and its safety k
evaluation.
Our initial response to the generic letter dated December 7, 1983 forwarded an information copy of the changes that we had identified to comply with the NUREG-0737 requirements and stated that following OSC and ORC review, we would forward the applicable changes for your review.
During the Duquesne (s
Light Company review, it was determined that the following deviations from that
,i submittal were cppropriate:
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1)
Section 3.3.3.7 Chlorine Detection Systems was to be revised to follow the standard technical specification requirements by requiring oi21y two instead of the presently required three operable chlorine
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detectors. This was proposed to reduce the number of LER's on this equipment.
This change is no longer required since the reporting requirements will be revised by Technical Specification Change No. 90 submitted in response to Generic Letter 83-43.
Therefore, Section l.(
3.3.3.7 was removed from this proposed change.
f 2)
Tables 3.3-11 and 4.3-7 Accident Monitoring Instrumentation were to be revised to include the Containment Wide Range Pressure
,fd instruments. This change is no longer required since we have i
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8410260052 841008 003 PDR ADOCK 05000334 P
r-I eav:r Valley Power Station, Unit No. 1 B
. Dock 5t No. 50-334, License No. DPR-66 i0perating License Change Request No. 94 Page 2
' determined that the containment pressure instruments are presently specified in Table 3.3-3 Engineered Safety Feature Actuation System Instrumentation and control room indication is provided to the operator.. Therefore,.the Containment Wide-Range Pressure instruments
-have.been removed from the above tables since it would be redundant to list these instruments on the accident monitoring as well as ESF
-tables.
3)
Section 3.4.12 Reactor Coolant System-Vents has been added to this proposed change to reflect the system installed by DCP-295.- The limiting condition for operation deviates from the standard technical specification by incorporating a~ note ** "The valves may be operated for venting operations and leak testing." This will allow the valves
.to perform the -intended function.
Action statement "a" has been revised by adding "The provisions of Specification 3.0.4 are not applicable." This will allow entry into an operational mode with one vent path inoperable.as permitted by Action statement "a".
4)
Section 6.8.4 has been revised by changing the title from Post-Accident Sampling to Post-Accident Monitoring since this more adequately-describes the program.
A license amendment application fee of $150.00 will be submitted under separate cover in accordance _with 10 CFR 170.
Very tr ly yours, J.
. Carey Vice President, Nuclear