ML20055F547
| ML20055F547 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/03/1990 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20055F546 | List: |
| References | |
| 50-423-90-08, 50-423-90-8, NUDOCS 9007180012 | |
| Download: ML20055F547 (2) | |
Text
7 P.;,
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APPENDIX _A NOTICE OF VIOLATION Northeast Nuclear Energy Company Docket No.
50-423 Millstone Nuclear Power Station Unit 3 License No. NPFa49 As a result cf the inspection conducted on May 3 through June 11, 1990, and u accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10CFR Part 2 Appendix C (Enforcement Policy,1990), the following violations were identified:
A.
Millstone Unit 3 technical specification 6.8.1, requires -in part, that written procedures be established, implemented and maintained, as_
t-recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
'Miin Steam System Operating Procedure, OP 331'6, and Accumulator Low !
Pressure Safety injection, OP 3310B, are procedures recommended by Regulatory Guide 1.33.
(a) OP 3316 states that the main steam isolation-valves (tiSIVs) are to be opened only when the differential pressure across the valves is
-m less than'25 pounds of differential pressure, f
q (b) OP 3310B contains a note prior to section 7.2 which prohibits use'of that.section while in Mode 3.
1 Contrary. to the above, on May 12, 1990, an operator-opened the MSIVs with a 60-70-pound differential pressure.
This decreased: steam generator I
pressure and caused a steam generator swell which-res'J1ted in an -
engineered safety. feature actuation. On May 18, 1990 while in Mode 3, operators filled safety injection accumulators using section 7.2 of OP J
3310B. Operators failed to complete the restoration actions contained'in section 7.2 and as a result lef t redundant trains of intermediate ' pressure -
4 safety injection-inoperable for approximately four hours.
This is a Severity Level IV Violation-(Supplement I).
B.
10 CFR 50.72 (b)(2)(iii states,.in part,... "The licensee shall notify the_NRC as soon a)s practical and, in all cases, within four hours of the occurrence of any event or condition that alone could have prevented the fulfillment of the safety function of structures l
[
or systems that are needed to mitigate the consequences of an accident.
1 L
Contrary to the above, on March 19, 1990, operators discovered that both t
L trains of the auxiliary building ventilation filters were inoperable.
The NRC was not informed of this occurrence until March 28, 1990. On May 18, 1990, operators discovered both trains of the safety injection system were Q
'.J ;
1
- ~ J Appendix A' 2
, i.
inoperable.- This event was' not reported to the NRC untti May 20,-1990.
i Both systems are required to mitigate the consequences of an accident.
'l 8
' This :is a' Severity Level IV Violation (Supplement 1).
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 l
1 the letter which transmits 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 L
cause is shown, consideration will be given to extending this response. time.
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