ML20206R160

Notice of Violation from Insp on 981005-23 & 1211.Violations noted:licensee-established Measures Failed to Assure Prompt Identification & Effective Corrective Action to Address Potential for Core Reactivity Change

ML20206R160
Person / Time
Site:	Fort Calhoun
Issue date:	01/08/1999
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20206R154	List: IR 05000285/1998019 ML20206R148 ML20206R160
References
50-285-98-19, NUDOCS 9901190162
Download: ML20206R160 (2)

Text

I I

i l

l ENCLOSURE 1 NOTICE OF VIOLATION l

Omaha Public Power District Docket No.: 50-285 Fort Calhoun Station License No.: DPR-40 During an NRC inspection conducted on October 5-23, with inoffice review until December 11, 1998, a 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: l Criterion XVI of Appendix B to 10 CFR Part 50 states, in part, measures shall be established to l assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, l deviations, defective material and equipment, and nonconformances are promptly identified and  !

corrected.

Contrary to the above, licensee-established measures failed to assure prompt identification and )

effective corrective action to address a potential for a core reactivity change due to the l inadvertent addition of demineralized water to the reactor coolant system via the post-accident sampling system. Specifically, the licensee was informed on September 19,1994, of the potential for the inadvertent dilution of the reactor coolant system. Subsequently, for three years, the licensee failed to identify that the performance of instrument calibration and normal operating procedures for the post-accident sampling system could lead to a boron dilution event. Specifically, l

• On September 21,1994, the licensee's use of Calibration Procedure IC-CP-01-6713,

" Calibration of PASS Drain Collecting Tank Level Switch LS 6713," Revision 1, led to an unauthorized dilution event of the reactor coolant system, and the event was not identified for more than 21 months. As a result of this event, the NRC cited the licensee for failure to control core reactivity.

. As a result of the NRC citation, on January 7,1997, the licensee initiated corrective action to review for any potential for the introduction of nonborated water to the reactor coolant system during maintenance, testing, and operation of plant systems. This action was closed without identifying any additional potential for boron dilution of the reactor coolant system.

. On November 19,1997, the licensee found it necessary to reinitiate corrective action when it was discovered that a potential still existed to introduce nonborated water to the reactor coolant system through the normal operation of the post-accident sampling system.

This is a Severity Level IV violation (Supplement 1) (50-285/9819-01).

Pursuant to the provisions of 10 CFR 2.201, Omaha 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 9901190162 990108 PDR G ADOCK 05000285 PDR J

0 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 coritested, 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 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 with the basis for your denial to the Director Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001.

Because your response will be 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. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your l

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 L 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 l 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial l information), if safeguards information is necessary to provide an acceptable response, please l 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 of Violation within 2 working days.

Dated at Arlington, Texas this 8th day of January 1999 l

i u

4

-- 4