ML20236S448
| ML20236S448 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/19/1987 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20236S447 | List: |
| References | |
| 50-245-87-17, 50-336-87-15, NUDOCS 8711250172 | |
| Download: ML20236S448 (2) | |
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APPENDIX'A pg;p. '
p Northeast Nuclear' Energy Company License Nos. DPR-21/DPR-65 (p
- Millstone. Units.1 and 2.'
Docket Nos.
50-245/50-336 i
'As'a result of;the inspection conducted on July 15-17, 1987, and in accordance with the " General Statement of Policy and Procedure for NRC Enforcement 6
y Actions,".10.CFR Part 2, Appendix C (Enforcement Policy) (1986), the following-l n{3 4
violations were identified:
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(A.
10'CFR-50.49(f)'requir'es' that qualification of each component be based on testing or experience with. identical equipment or with similar equipment f,
with a supporting analysis:to-show that the equipment'to be qualified is Lacceptable.
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'10 CFR 50.49(k) requires, that electr.ical equipment need not be requalified im Lif it'was'previously required.by the Commission to be qualified in accordance h
a
with the " Guideline for Evaluating Environmental Qualification of' Class 1E L
iElectrical?Equipinent in Operating Reactors" (DOR Guidelines).
Section l5.2.2Lof.the D0R Guidelines requires that the type test is only valid for Lequipment identicaliin. design and material construction to the test
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!specimenLand any. deviations should be evaluated.
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Contrary to the above', as of July 17, 1987 the. licensee was not able to
. provide documentation'to establish qualification by test or analysis of e
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. Genera 1' Electric (GE) SIS wire used in Valves 2-SI-651, 2-CH-501 and i
2-SI-644.
F D'
This'is Severity Level IV-(Supplement I) applicable to Unit 2.
'B
.10CFR 50.49(1) requires that replacement equipment be qualified in
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accordance with.the provisions of this section unless there are sound
- reasons to the' contrary.
Contrary to the above, it was observed on July 17, 1987 that the Bishop cable-splice installed on motor operated valve 2-SI-654 on the May 31, 1986
- was not qualified to the requirements of 10 CFR 50.49 and as of July 17, 1987 the licensee had not addressed any sound reasons to the contrary.
1This is Severity Level IV (Supplement I) applicable to Unit 2.
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i10LCFR'50.49(e)(1)requiresthattheelectricequipmentqualification f
- program must include: and be based on the time dependent temperature for L'
the:most-severe Design Basis Accident during or following which this F1 Lequipment is required to remain functional.
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r 8711250172 8711191
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P PDR ADOCK.05000245 S8 vr'FICIAL RECORD COPY IR MILL 87-17/15 - 0004.0.0
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Appendix A 2
Contrary to the above, on July 17, 1987, the Curtis L type terminal blocks used in valve.I-IC-I was not qualified based on the time dependent temperature for the most-severe Design Basis Accident in that the Limitorque Test Report 80119 qualified these terminal blocks only to 312 F, but was used in an application where-the Design Basis Accident temperature was 330 F following which the equipment was required to remain functional.
This -is: Severity Level IV.(Supplement I). applictble to Unit 1.
Pursuant to the provisions of.10 CFR 2.201, Northeast Nuclear Energy Company is hereby required to submit to this office within thirty days of the date of the letter which transmitted this Notice, a written statement or explanation in reply, including: (1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further l..
' violations;'and (3) the date when full compliance will be achieved. Where good cause'is shown, consideration will be given to extending this response time.
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OFFICIAL RECORD COPY IR MILL 87-17/15 - 0006.0.0 11/17/87
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