ML20128A430

Notice of Violation from Insp on 921129-930102.Violations Noted:Procedure S0I-82.2 Not Followed & Periodic Instruction 0-PI-OPS-000-006.0 Inadequate

ML20128A430
Person / Time
Site:	Sequoyah
Issue date:	01/15/1993
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20128A407	List: IR 05000327/1992036 ML20128A403 ML20128A430
References
50-327-92-36, 50-328-92-36, NUDOCS 9302020214
Download: ML20128A430 (2)

Text

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ENCLOSURE 1 NOTICE OF VIOLATION Tennessee Valley Authority Docket Nos. 50-327, 50-328 Sequoyah, Units 1 and 2 License Nos. DPR-77, DPR-79 During an NRC inspection conducted November 29, 1992 through January 2, 1993, violations of NRC requirements was identified. in n .ordance with the

" General Statement of Policy and Procedure for NRC.Eitforcement Actions,"

10 CFR Part 2. Appendix C, the violations are listed _below:

1. Technical S)ecification 6.8.1 requires, in part, that aritten procedures be establisved, implemented and maintained for applicable procedures recommended in Appendix A of Regulatory Guido 1.33, Quality Assurance Program Requirements, Revision 2, february 1978. Appendix A to Regulatory Guide 1.37 requires procedures for equipment control and operation of safety related equipment.

A. Periodic instruction 0-PI-0PS-000-006.0, FREEZE PROTECTION, Rev.

O., identifbs equipment needing freeze protection, identifies the means of nrotection, and provides requirements to ensure equipment operability during the montns needed.

Contrary to the above, Periodic Instruction 0-PI-0PS-000-005.0'was inadequate in that it did not provide for configuration. control of Refueling Water Storage Tank (RWST) immersion heater power supply switches. On December 24, 1992,- it was discovered that handswitch 2-HS-63-132 which controls two of the four RWST immersion heaters was in the OFF position instead the AUTOMA?lc position. This-resulted in the=inoperability of these two Unit 2 RWST_ immersion heaters for an unknown period of time.

B. System Operating instruction 501-82.2 DIESEL GENERATOR IB-8, Rev.

39, specifies the normal position of %e handswitch for the IB1-B and IB2-B diesel generator day tank supply pump to be in the AUTO position.

Contrary to the above, on approximately December 18, 1992, the licensee failed to follow procedure S01-82.2. On December =21, 1992, it was discovered that:the hindswitch for the 181-B and 182-B diesel generator day tank supp!y pump was ir the 0FF position instead of the AUTO position.

This is a Severity Level IV violation (Supplement 1).

2. Technical Specification 4.0.5 delineates inservice inspection and testing requirements of ASME Code class 1, 2, and 3 components. These requirements specify that inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 _.

pumps. and valves shall be performed in accordance with Section XI of the 9302020214 930115 PDR ADOCK 05000327 G l*DR a

l

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2 Tennessee Valley Authority Docket Nos. 50-327, 50-328 Sequoyah, Units 1 and 2 License Nos. DPR-77, DPR-79 ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(1).

A5ME,Section XI Table IWD-2500-1, requires a visual inspection (VT-2) as a part of an inservice pressure test of safety-related components within each of the three inspection periods during each 10 year inservice inspection interval.

Contrary to the above, on December 22, 1992, required pressure tests on various safety-related systems (e.g., containment spray, essential raw cooling water, auxiliary feedwater, safety injection, and spent fuel pit) had not been performed during the second inspection period of the first 10 year surveillance interval. This condition existed since the end of the second inspection period which occurred on September 15, 1991 and February 21, 1992, for Units 1 and 2, respectively.

This is a Severity Level IV violation (Supplement 1).

Pursuant to the provisions of 10 CFR 2.201, Tennessee Valley Authority is hereby required to submit a written statement or explanation to the U.S.

Nuclear Regulatory Commission, ATIN: Document Control Desk, Washington, D.C.

20555 with a copy to the Regional Administrator, Region 11, and a copy to the ,i NRC Resident inspector, Sequoyah, within 30 days nf 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, (?; 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 or 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.

Dated at Atlanta, Georgia this 15th day of January, 1992

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