ML17291A693
| ML17291A693 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/14/1995 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML17291A692 | List: |
| References | |
| 50-397-94-33, NUDOCS 9503200044 | |
| Download: ML17291A693 (3) | |
Text
ENCLOSURE 1
NOTICE OF VIOLATION Washington Public Power Supply System Washington Nuclear Project-2 Docket:
50-397 License:
NPF-21 During an NRC inspection conducted on December 1),
- 1994, through January 21,
- 1995, two 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, the violations are listed below:
Technical Specification (TS) Section 3.3.7.5 states "The accident monitoring instrumentation channels shown in Table 3 '.7;5-1 shall be operable
. With one or more accident monitoring channels inoperable, take the action required by Table 3.3.7.5-1."
Item 27 of Table 3.3.7.5-1 lists "Primary Containment Valve Position" as accident monitoring instrumentation, and references Action 80 as the required action to be performed if one channel is inoperable.
Action 80.a of TS 3.3.7.5 states "With the number of operable accident monitoring instrumentation channels less than the required number of channels shown in Table 3.3.7.5-1, restore the inoperable channel(s) to Operable status within 7 days or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />."
Contrary to the above, as of January 18,
- 1995, primary containment valve position accident monitoring instrumentation was inoperable for greater than 7 days, but the plant was not placed in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Specifically, the valve position indication for PSR-V-X77Al, a primary containment isolation valve, was inoperable from January 6-19,
- 1995, but the plant was not placed in at least hot shutdown.
B.
This is a Severity Level IV violation (Supplement I) (397/9433-02).
TS 6.8, 1 states, in part, "Written procedures shall be established, implemented, and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978."
Regulatory Guide 1.33 paragraph 8.b states that "implementing procedures are required for each surveillance test, inspection, or calibration listed in the technical specifications."
TS 4. 1.3.6.b states "Each affected control rod shall be demonstrated to be coupled to its drive mechanism by
. verifying that the rod does not go to the overtravel position:
anytime the control rod is withdrawn to the 'full out'osition in subsequent operation."
TS 4.3. 1.7.c states "the control rod position indication system shall be determined Operable by verifying:
that the control rod position 9S03200044 9S0314 PDR ADQCK OS000397 9
indicator corresponds to the control rod position indicated by the 'full out'osition indicator when performing Surveillance Requirement
- 4. 1.3.6.b."
The licensee formally implements these requirements by Plant Procedures Hanual Procedure 9.3.9 which specifies the use of rod pull sheets that require signatures in reference to TS 4. 1.3.6.b and 4. 1.3.7.c.
Contrary to the above, as of January 11,
- 1995, on four occasions the licensee did not implement PPH 9.3.9, "Control Rod Development Sequence Withdrawal and Control," Revision 12, which documents the performance of TS Surveillances
- 4. 1.3.6.b and 4. 1.3.7.c.
Specifically:
~
On October 23,
- 1994, Control Rod 06-47 was pulled from Position 00 to 48, but the pull sheet was not signed off for the coupling check or the full-out lights.
~
On October 29,
- 1994, Rod 42-59 was pulled from Position 00 to 48, but the pull sheet was not signed off for the coupling check or the full-out lights.
~
On December 21,
- 1994, Rod 42-03 was pulled from Position 00 to 48, but the pull sheet was not signed off for the coupling check or the full-out lights.
On January 5,
- 1995, Rod 02-19 was pulled from position 46 to 48, but the pull sheet was not signed off for the coupling check or the full-out lights.
This is a Severity Level IV violation (Supplement I) (397/9433-01).
Pursuant to the provisions of 10 CFR 2.201, Washington Public Power Supply System is hereby required to submit a written statement or explanation 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).
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation:
(1) the reason for the violation, or, if 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 compliance will be achieved.
Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response.
If an adequate reply is not received within the time specified in this Notice, an order or a 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 is shown, consideration will be given to extending the 'response time.
Dated at Arlington, Texas, this yPtg day ofg~~
1995