ML17292A893
| ML17292A893 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/16/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML17292A892 | List: |
| References | |
| 50-397-97-09, 50-397-97-9, NUDOCS 9706190247 | |
| Download: ML17292A893 (1) | |
Text
ENCLOSURE 1 NOTICE OF VIOLATION Washington Public Power Supply System Washington Nuclear Project-2 Docket No.:
50-397 License No.:
NPF-21 During an NRC inspection conducted from April 13 through May 24, 1997, one violation of NRC requirements was identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violation is listed below:
A.
'echnical Specification 3.6.3 required, in part, that while the plant is in Modes 1, 2, and 3, the primary. containment isolation valves in Table 3.6.3-1 be operable.
Additionally, with one or more primary containment isolation valves in Table 3.6.3-1 inoperable, at least one isolation valve is required to be maintained operable in each affected penetration that is open.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the Technical Specification required either:
(1) restore the valve(s) to operable status; (2) isolate each affected penetration by use of at least one deactivated automatic valve; or (3) isolate each affected penetration by use of at least one closed manual valve or blind flange.
Otherwise, HOT SHUTDOWN is required within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Contrary to the above, between December 16, 1993, and March 7, 1994, while the plant was in Mode 1, Valves QS-V-16 and MS-V-19 listed in Table 3.6.3-1 were inoperable in that they could not have performed their intended safety function to close for a limited range of steam line break accidents.
The required actions of the Technical Specification Action Statement were not performed (the valves were closed, but not deactivated).
This is a Severity Level IV violation (Supplement I).
The NRC has concluded that information regarding the reason for the violation, the corrective actions taken and planned to correct the violation and prevent recurrence and the date when full compliance was achieved is already adequately addressed on the docket in the enclosed inspection report.
However, you are required to submit a written statement or explanation pursuant to 10 CFR 2.201 if the description therein does not accurately reflect your corrective actions or your position.
In that case, or if you choose to respond, clearly mark your response as a "Reply to a Notice of Violation," and send it to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region IV, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
Dated in Arlington, Texas, this 16th day of June 1997 9706190247 9706i6 PDR ADQCK 05000397 8