ML17264A537

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Notice of Violation from Insp on 960324-0504.Violation Noted:On 940822,licensee Made Change in Procedure Described in Updated FSAR Section 12.3.3.2 W/O Prior Commission Approval
ML17264A537
Person / Time
Site: Ginna Constellation icon.png
Issue date: 06/06/1996
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML17264A536 List:
References
50-244-96-03, 50-244-96-3, NUDOCS 9606180400
Download: ML17264A537 (3)


Text

NOTICE OF VIOLATION Rochester Gas and Electric Corporation Ginna Station Docket No. 50-244 License No.

DPR-18 e

During an inspection conducted on April 9-26, 1996, vi.olations 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:

1.

10 CFR 50.59 states that, a licensee may make changes in the procedures as described in 'the safety analysis report, without prior Commission

approval, unless the proposed change involves...an unreviewed safety question.

Contrary to the above, On August 22, 1994, the licensee made a change in the procedure described in the Updated Final Safety Analysis Report (UFSAR) Section 12.3.3.2, without prior Commission approval.

This change was based on a determination that there were no unreviewed safety questions.

The determination that there were no unreviewed safety questions was based on an inadequate design review.

Specifically, Section 12.3.3.2 of the UFSAR was changed in December

1994, reducing the in-plant air monitors in the Auxiliary Building from three to one.

The basis for the UFSAR change was the result of an inadequate air flow design analysis in May 1994 that incorrectly concluded that plant area radiation monitors and the plant vent monitor provided adequate airborne radioactivity monitoring for plant personnel.

This is a Severity Level IV violation (Supplement I) 2.

10 CFR 20. 1501 states that the licensee shall make or cause to be made, surveys that(1) may be necessary for the licensee to comply with the regulations in this part; and (2) are reasonable under the circumstances to evaluate concentrations or quantities of radioactive material.

10 CFR 20. 1802 states that the licensee'hall control and maintain constant surveillance of licensed material that is in a controlled or unrestricted area and that is not in storage.

Contrary to the above, on March 29,

1996, equipment was surveyed by the licensee and determined to be free of licensed material and released.

The equipment arrived at another nuclear power plant on Harch 30,

1996, was surveyed, and was determined to contain up to 35,000 disintegrations per minute (dpm) per 15 square centimeters of licensed material.

This is a Severity Level IV violation (Supplement IV).

Pursuant to the provisions of 10 CFR 2.201, Rochester Gas and Electric Corporation 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 I, 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 9606i80400 960606 PDR ADDCK 05000244 8

PDR

Notice of Violation 2

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4 of Violation (Notice).

This reply should be cle II Dated at King of Prussia, Pennsylvania this 6th day of June, 1996 arly marked as "Reply to a

Notice of Violation and should include.

(I) the reason for the violations, or, if contested, the basis for disputing the violations; (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.

If an adequate reply is not received within,the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked, or why such action as may be proper should not be taken.

Where good cause is shown, consideration will be given to extending the response time.

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.

However, if you find it necessary to include such information, you should clearly indicate the specific information that you desir e not to be placed in the

PDR, and provide the legal basis to support your request for withholding the information from the public.