ML20244A669
| ML20244A669 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/14/1979 |
| From: | Dunn C DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19273B971 | List: |
| References | |
| IEB-79-01, NUDOCS 7906180601 | |
| Download: ML20244A669 (2) | |
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'/nited S t at es %cicar Regulatory Cm:91ss!cn Direstof, Divisten of Reactor Operaticas ir.*q u e t kn j
Otfice of Inspectton and Enforce:ent h*aihington, D. C.
20555 P.eference:
Beaver Valley Pc er St ition, t' nit *:o. 1 Docket No. 50-334 License No. DPR-65 Response To IE Bulletin 7')-01 d
Gentler.en:
'ie love evapleted our revica of IE Eulletin 79-01 and have Jctermined the follwing:
1.imit Swi tches, The type limit switches described in the Bulletin have been replaced consistent with our response to IE Bulletin 78-04 A review has determined that none of the additional model numbers deteribed in the Bulletin are installed on safety related valves in Beaver Valley Power Station.
cualifica!!cn Occu entatien of Sifety Related Electrical Ecut :~ent 1.
Safety related el ctrical equi pent is qualified by any of 3everal docu.cntatica -cans:
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a.
Letter of compliance from equipment manuf acturers based upon r
I specification requirceents.
b.
Test reports f rom equipe.ent manuf acturera or other utilities' i
for similar type aquipment.
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c.
Analysis of equiptnent by equipment manuf acturers or other utilities for similar type equipment.
2.
All safety related electrical equip ~ent, except for the following, wrs /st-r.ined to b Tviiiiled In accordance with the above:
's. Terrinal boxes located within containment will encounter a sudden high pressure increase due to a LOCA or a main steam line bresk.
Calculations show that the boxes ay deform under this sudden pressure increase.
In order to a sure that all such boxes are not damaged due to a sudden preasure increase, all safety related terminal boxes wt11 be drilled for pressure equalization prior to station startup.
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Ranl m ir.spectiens of several safety relar.ed ter..inal b es within containment and the main steam valve cubiele shewed j
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- .;rt lengths of SIS wires cennecting the device frem tSm terminal box to the load device were of various manufacturers, all of which did not have adequate qualification documentation.
These short lengths of SIS wires will be replaced with properly
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documented qualified materials during the refueling outage.
The station feels justified in operating the. plant for the l
following reasons:
The primary consideration for SIS wire is the long term radiation effect on the wire.
Since the plant f
has only operated for a short period of time, and since the
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radiation 1cvels have been low, any deterioration of the wire j
has been minimal.
Since the plant is only scheduled to operate for an additional short period of time until the refueling outage, the probability of failure would be minimal.
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Tour Icyc1 transmitters located below Elevation 697' 9" wi thin containment will be subject to that maximum high water level.
These level transmitters are qualified except for subr.erged 3
operation.
Therefore, these level transmitters will be relocated above the maximum water level during the refueling outage.
These transmitters are steam generator level transmitters.
These transmitters are not used for operator indication during an accident and, therefore, the station feels justified in operating until the refueling shutdown.
The documentation for the safety related ciectrical equipment is enclosed.
The method of review and its supporting data is available at the plant.
The supplement to this Bulletin (79-01A) has been received.
The action requested in Item 1 will be ccmpleted by July 31, 1979 and the information requested in Ites 2 will be submitted by September 30, 1979.
1 If you have any questions regarding this response, please contact my office.
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Very truly yours, j
1 O _._
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,m C. N. Dunn Vice President, Operations i
C.alo. ora cc:
Unit,ed States Nuclear Regulatory Cetmission Region 1 631 Park Avenna King of Prussia, Pennsylvania 19406
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