ML20202E326

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Notice of Violation from Insp on 981115-1226.Violation Noted:Licensee Failed to Take Effective Measures to Preclude Repetition of Inadvertent Opening of torus-to-drywell Vacuum Breaker Documented in LER 50-298/97-007
ML20202E326
Person / Time
Site: Cooper Entergy icon.png
Issue date: 01/22/1999
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20202E316 List:
References
50-298-98-08, 50-298-98-8, NUDOCS 9902020382
Download: ML20202E326 (3)


See also: IR 05000298/1997007

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ENCLOSURE 1

NOTICE OF VIOLATION

Nebraska Public Power District Docket No.: 50-298 I

Cooper Nuclear Station License No.: DPR 46

During an NRC inspection conducted from November 15 through December 26,1998, two

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:

A. Technical Specification 5.4.1 requires, in part, that written procedures be established,

implemented, and maintained that meet the applicable procedures recommended in

Appendix A of NRC Regulatory Guide 1.33. Appendix A of NRC Regulatory Guide 1.33

requires procedures for log entries, equipment control (tagging), replacement and repair

of recirculation pump seals, and a plant fire protection program.

Contrary to the above,

1. On December 2,1998, NRC inspectors identified that operators did not

implement the Procedure 2.0.2, " Operations Logs and Reports," Revision 44,

Step 8.8, requirement that the shift supervisor record inoperable Technical

Specification equipment in the Technical Specifications tracking form. As a

result, the operators authorized maintenance on the reactor equipment cooling

system without recognizing or recording that the maintenance would render the

Residual Heat Removal Loop A pumps inoperable.

2. On December 5, NRC inspectors identified that operators did not implement the

Procedure 0.9, " Tagging Orders," Revision 22C3, Step 5.1, requirement to hang

and remove tags in a specified order. As a result, operators did not hang tags

for Valves CS-172, CS-173, and CS-V-14A in the correct order, resulting in the

unintentional draining of approximately 1.4 inches of water from the reactor.

3. On December 13, NRC licensee identified that technicians did not implement

Step 8.2.38 or correctly implement Step 8.2.39 of Procedure 7.2.5.1, " Reactor

Recirculation Pump Seal Cartridge Removal and Installation," Revision 13. As a

, result, they incorrectly installed the thrust collar of the Reactor Recirculation

Pump B seat. The seal subsequently failed.

4. On December 2, NRC inspectors identified that a fire watch failed to implement

the Procedure 0.39, " Fire Watches," Revision 18, Step 8.14, requirement that

combustible materials and openings in walls and floors within 35-foot radius of

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hot water be protected / covered with noncombustible blankets. Inspectors found

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unprotected combustible material and an opening in the floor within a 35-foot

radius of the hot work area.

This is a Severity Level IV violation (Supplement 1) (50-298/98008-01).

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B. 10 CFR Part 50, Appendix B, Criterion XVI, requires, in part, that measures shall be

established to assure that conditions adverse to quality, such as failures, malfunctions,

deficiencies, deviations, defective material and equipment, and nonconformances are

promptly identified and corrected. In the case of significant conditions adverse to

quality, the measures shall assure that the cause of the condition is determined and that

corrective actions will be taken to preclude repetition.

Contrary to the above, the licensee failed to take effective measures to preclude

repetition of inadvertent opening of the torus-to-drywell vacuum breaker documented in

Licensee Event Report 50-298/97-007, " Opening of a torus-to-drywell vacuum breaker."

Specifically, the licensee failed to take reasonable action to prevent inadvertent opening

of the vacuum breaker for all conditions that could reasonably be expected, as

documented in procedures and design documents.

This is a Severity Level IV violation (Supplement 1) (50-298/98008-02).

Pursuant to the provisions of 10 CFR 2.201, Nebraska Public Power District 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 l

the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly I

marked as a " Reply to a Notice of Violation" and should include for each violation: (1) the l

reason for the violation, or, if contested, the basis for disputing the violation or severity level, 1

(2) the corrective steps that have been taken and the results achieved, (3) the corrective steps l

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.

If you contest this enforcement action, you should also provide a copy of your response to the l

Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, l

DC 20555-0001.

Your response will be placed in the NRC Public Document Room (PDR). Therefore, to the

extent possible, the response should not include any personal privacy, proprietary, or

safeguards information so that it can be placed in the PDR without redaction. If personal

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. If you request

withholding of such material, you must 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

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withholding confidential commercial or financial information).' If safeguards information is

necessary to provide an acceptable response, please provide the level of protection described

in 10 CFR 73.21.

In accordance with 10 CFR 19.11, you may be required to post this Notice within two working

days.

' Dated at Ariington, Texas

this 22nd day of January 1999 -

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