ML20211E253

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Notice of Violation from Insp on 970706-0823.Violation Noted:On 970714,containment Isolation Valve 1-FCV-31C-229 Failed to Exhibit Required Change of Obturator Position & Was Not Repaired or Replaced & Data Not Analyzed
ML20211E253
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 09/22/1997
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20211E201 List:
References
50-327-97-08, 50-327-97-8, NUDOCS 9709300074
Download: ML20211E253 (2)


Text

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Tennessee Valley Authority Docket No. 50 327 Sequoyah Nuclear Plant License No. OPR-77 During an NRC inspection conducted on May 25 through July 5, 1997, a violation of NRC requirements was identified. In accordance with the " General Statement of Policy and Procedures for NRC Enfecement Actions." NUREG 1600, the violation is listed beln.v:

Technical Specification 4.0.5. Inservice Testing Program, requires that inservice testing of ASME Code Class 1. 2, and 3 pumps and valves shall be in accardance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a.

10 CFR 50.55a Codes and Standards. Section (f). Inservice Testing Requirements, paragraph 411 requires that inservice test 1% conducted during the 120 month interval must comply with the requirements in the latest edition and addenda of the Code incorporated by 10 CFR 50,55a Section (b) applicable within 12 months prior to the start of the 120 month interval. 10 CFR 50.55a. Section (b) references OMa-1988 Addenda to the OM 1987 Edition which is the applicable edition and addenda to the code.

ASME/ ANSI OMa-1988 Addenda to ASME/ ANSI OM 1987, Operation and Maintenance of Nuclear Power Plants. Part 10, Section 4.2.1.9, Corrective Actim, Part (a) states. in part, "If a valve fails to exhibit the required change of obturator nosition...the valve shall be immediately declared inoperabic." Part h ) stdtes. " Valves declared inoperable may be repaired, replaced, or the data may be analyzed to determine the cause of the deviation and the valve shown to be operating acceptably."

Contrary to the above, on July 14, 1997, containment isolation valve 1 FCV-31C-229 failed to exhibit the required change of obt;rator position (during three stroke attempts) and it was not repaired, replaced, nor was the data analyzed prior to declaring the valve operable.

This is a Severity Level IV Violation (Supplement I).

9709300074 97092E' PDR ADOCK 05000327 0 PDR

NOV 2 Pursuant to the provisions of 10 CFR 2.201. Sequoyah Nuclear Plant 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 11. and a copy to the NRC Resident inspector at the Sequoyah facility, 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 previously docketed correspondence if the correspondence adequately addresses the required response. If an adequate i reply is not received within the time specified in this Notice, an order or Demand for Information may be issued as to why the license should 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.

Because your response will be places in the NRC Public Document Room (PDR) to the extent possible, it should not include any personal privacy proprietary, or safeguards information so 17 ; 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 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 GR 73.21.

Dated at Atlanta, Georgia this 22nd day of September 1997

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