ML17292B314
| ML17292B314 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/31/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML17292B313 | List: |
| References | |
| 50-397-98-03, 50-397-98-3, NUDOCS 9804080244 | |
| Download: ML17292B314 (6) | |
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 on February 1 to March 14, 1998, four violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violations are listed below:
WNP-2 Technical Specification 6.8.4.a.2 requires integrated leak tests to be performed at refueling cycle intervals or less for those systems designated in Technical Specification 6.8.4.a, including low pressure core spray, high pressure core spray, residual heat removal, reactor core isolation cooling, hydrogen recombiners, process sampling, containment monitoring, and standby gas treatment.
Table 1.1 of Technical Specifications defines a refueling cycle frequency of once per 18 months (550 days).
Technical Specification 4.0.2 does not apply.
Contrary to the above, between April 13, 1984, and March 10, 1997, 27 examples were identified in which integrated teak tests were performed at intervals exceeding 18 months.
This is a Severity Level IVviolation (Supplement I).
B.
WNP-2 Technical Specification 5.5.4.e requires a determination of cumulative and projected dose contributions from radioactive eNuents for the current calendar quarter and current calendar year, in accordance with the methodology and parameters in the Offsite Dose Calculation Manual, at least every 31 days.
Technical Specification 3.0.2 does not apply.
Contrary to the above, between March 10, 1997, and February 1, 1998, 8 examples were identified in which the interval for determining cumulative and projected doses exceeded 31 days.
This is a Severity Level IVviolation (Supplement I).
WNP-2 Technical Specification 5.5.2, "Primary Coolant Sources Outside Containment,"
requires both periodic visual inspections and biennial integrated leakage inspections to be implemented for, in part, the containment monitoring, process sampling, and standby gas treatment systems.
WNP-2 Technical Specification 5.4.1.e requires procedures to be established, implemented, and maintained for all programs specified in Technical Specification 5.5.
9804080244 98033'DR ADQCK OS000397 8
0 Contrary to the above, as of March 14, 1998, Plant Procedure Manual (PPM) 1.5.6, Revision 8, "Leakage Surveillance and Prevention Program," the licensee's procedure for implementing the program under Technical Specification 5.5.2, was incomplete.
Specifically, the procedure failed to identify the periodic visual inspection requirements for the standby gas treatment and process sampling systems.
Additionally, the procedure failed to identify all of the appropriate components to be evaluated for leakage in the containment monitoring, process sampling, and standby gas treatment systems.
This is a Severity Level IVviolation (Supplement I).
D.
10 CFR Part 50, Appendix B, Criterion XVI, "Corrective Action," requires, in part, that measures shall be established to assure that conditions adverse to quality, such as
'ailures, deficiencies, and deviations,- are promptly identified and corrected.
Contrary to the above, from December 4, 1997, to March 6, 1998, the licensee failed to take prompt and adequate corrective action for a condition adverse to quality.
'pecifically, on December 4, 1997, the NRC identified procedural noncompliances in the control of transient combustibles in high radiation areas of the reactor building and the licensee failed to promptly and adequately address personnel knowledge deficiencies in implementing the transient combustible control program. As a result, additional procedural noncompliances in the control of transient combustibles in the reactor building were identified on February 18 and March 6, 1998.
This is a Severity Level IVviolation (Supplement I).
The NRC has concluded that information regarding the reasons for Violations A and B, the corrective actions taken and planned to correct the violations and prevent recurrence and the date when full compliance will be achieved is already adequately addressed on the docket in the attached inspection report (50-397/98-03).
However, you are required to submit a written statement or explanation pursuant to 10 CFR 2.201 ifthe description therein does not accurately reflect your corrective actions or your position.
In that case, or ifyou 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 facilitythat is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
Concerning Violations C and D, '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, ANN: 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 facilitythat 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, ifcontested, the basis for disputing the violation or severity level, (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 willbe achieved.
Your response may reference or include previous docketed correspondence, ifthe correspondence adequately addresses the required response.
Ifan 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.
Ifyou contest this enforcement action, you should also provide a copy of your response to the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001.
Because your response willbe placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction.
Ifpersonal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. Ifyou request withholding of such material, you~
specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial information). Ifsafeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Dated at Walnut Creek, Californi, this 31st day of March 1998
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