ML19273B970
| ML19273B970 | |
| 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-79-1, NUDOCS 7906180601 | |
| Download: ML19273B970 (2) | |
Text
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'Af (412) 456-6000 435 Sixth Avenue Pittsburgn. Pennsylvama June 14,1979 15219 United States Nuclear Regulatory Commission Director, Division of Reactor Operations Inspection Office of Inspection and Enforcement Washington, D. C.
20555
Reference:
Beaver Valley Power Station, Unit No.1 Docket No. 50-334 License No. DPR-66 Response To IE Bulletin 79-01 Gentlemen:
We have completed our review of IE Bulletin 79-01 and have determined the following:
Limit Switches 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 described in the Bulletin are installed on safety related valves in Beaver Valley Power Station.
Qualification Documentation Of Safety Related Electrical Equipment 1.
Safety related electrical equipment is qualified by any of several documentation means:
Letter of compliance from equipment manuf acturers based upon a.
specification requirements.
b.
Test reports from equipment manufacturers or other utilities for similar type equipment.
Analysis of equipment by equipment manuf acturers or other c.
utilities for similar type equipment.
2.
All safety related electrical equipment, except for the following, was determined to be qualified in accordance with the above:
a.
Terminal boxes located within containment will encounter a sudden high pressure increase due to a LOCA or a main steam line break. Calculations show that the boxes may deform under this sudden pressure increase.
In order to assure that all such boxes are not damaged due to a sudden pressure increase, all safety related terminal boxes will be drilled for pressure equalization prior to station startup.
2353 2,34 o
790618h0[
4" Beaver Valley Power Station, Unit No.1 Docket No. 50-334 Response to IE Bulletin 79-01 Page 2 b.
Random inspections of several safety related terminal boxes within containment and the main steam valve cubicle showed that short lengths of SIS wires connecting the device from the terminal box to the load device were of various manufacturers, all of which did not have adequate qualification documentation.
These short lengths of SlS wires will be replaced with properly documented qualified materials during the refueling outage.
The station feels justified in operating the plant for the following reasons: The primary consideration for SIS vire is the long term radiation effect on the wire. Since the plant has only operated for a short period of time, and since the radiation levels have been low, any deterioration of the wire 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.
c.
Four level transmitters located below Elevation 697' 9" within l
containment will be subject to that maximum high water level.
These level transmitters are qualified except for submerged i
I operation. Therefore, these level transmitters will be relocated l
above the maximum water level during the refueling outage. These l
transmitters are steam generator level transmitters. These transmitters are not used for operator indication during an I
accident and, therefore, the statior-. feels justified in operating until the refueling shutdown.
1 The documentation for the safety related electrical 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 completed by July 31, 1979 and the information requested in Item 2 will be submitted by September 30, 1979.
l If you have any questions regarding this response, please contact my office.
Very truly yours, C. N. Dunn Vice President, Operations Enclosure cc: United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 2353 235
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