ML20036A170
| ML20036A170 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/21/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20036A166 | List: |
| References | |
| 50-395-93-09, 50-395-93-9, NUDOCS 9305100135 | |
| Download: ML20036A170 (2) | |
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t ENCLOSURE 1 NOTICE OF VIOLATION y
South Carolina Electric & Gas Docket No.:
50-395 V. C. Summer Nuclear Station License No.:
NPF-12 During a NRC inspection conducted on March 1-31, 1993, violations of NRC requirements were identified.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1993), the violations are listed below:
A.
TS 3.9.4 requires, in part, that during refueling operations, each reactor building penetration providing direct access from the reactor building atmosphere to the outside atmosphere be either:
(1) Closed by an isolation valve, blind flange, or manual valve, or (2) Be capable of being closed by an operable automatic Reactor Building Purge and Exhaust isolation valve.
Contrary to the above, on March 20, 1993, during refueling operations, reactor building (RB) penetration N0ZZ 600-12 was inadequate in that there was free communication between the RB atmosphere and the outside atmosphere through this penetration.
This free communication was discernible by daylight shining through the penetration and by a steady stream of air blowing out from the penetration.
j This is a Severity Level IV violation (Supplement I).
B.
10 CFR 50, Appendix B, Criteria III, requires, in part, that measures shall be established to assure that the design basis for safety-related components are' correctly translated into drawings.
Measures shall also be established for the selection and review for suitability of application of materials, parts, equipment, and processes that are i
essential to the safety-related functions of systems and components.
j Contrary to the above, on March 18, 1993, the selection and review for suitability of the E7012 series relays for the 62EFSA&B applications were inadequate.
E7012 series relays are time delay on pick-up, whereas the intended design required a time delay on drop-out. The 62EFSA&B applications were designed to send open signals to valves XVG 2802A&B under certain accident conditions. These valves are located in the steam supply lines to the TDEFW pump. The function of these valves is to provide positive isolation in the event of a main steam break. The incorrect selection of E7012 series relays for the 62EFSA&B applications resulted in an open signal to the valves under non accident conditions, which was not in accordance with design.
The design basis drawing for relays 62EFSA&B, B-208-032 EF30A, had two errors. The drawing indicated that the location of relay 62EFSB was 4
panel XCP-6111, while the actual location was panel XCP-6112, and the l
drawing incorrectly depicted the " shelf state" of relays 62ESFA&B contacts 1-5 and 2-6 as being open.
This is a Severity Level IV violation (Supplement I).
9305100135 930421 PDR ADOCK 05000395 G
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South Carolina Electric & Gas 2
Docket No.:
50-395 1
V. C. Summer Nuclear Station License No.: NPF-12 l
Pursuant to the provisions of 10 CFR 2.201, South Carolina Electric & Gas is l'
hereby required to submit a written statement or explanation to the U.S.
Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555, with a copy to the Regional-Administrator, Region II, and a copy to the NRC Resident Inspector, V. C. Summer Nuclear Station, within 30 days of the
.i date of the letter transmitting this Notice of Violation (Notice). This reply j
should be clearly marked as a " Reply to a Notice of Violation" and should i
include for each violation:
(1) the reason for the violation, or, if j
contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to~ avoid further violations, and (4) the date when full j
compliance will be achieved.
If an adequate reply is not received within the time specified in this Notice, an order or demand for information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause l
is shown, consideration will be given to extending the response time.
Dated at Atlanta, Georgia this 21st day of April 1993