ML20198M340

Notice of Violation from Insp on 971102-1213.Violation Noted:Since Initial Startup of Both Units 1 & 2,procedures 14420-1/2 & 14421-1/2 Inadequate

ML20198M340
Person / Time
Site:	Vogtle
Issue date:	01/12/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20198M315	List: ML20198M309 ML20198M340 ML20198M368 ML20198M686
References
50-424-97-11, 50-425-97-11, NUDOCS 9801200077
Download: ML20198M340 (2)

See also: IR 07100102/2012013

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NOTICE OF VIOLATION

Southern Nuclear Operating Company, Inc. Docket Nos. 50 424 and 50-425

Vogtle Electric Generating Piant License Nos, NPF-68 and NPF-81

8fnits 1 and 2

During an NRC inspection conducted November 2 through December 13, 1997, 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:

Technical Specification (TS) Surveillance Requirement (SR) 3.3.1.4,

Reactor Trip System Instrumentation, requires that a 31-day staggered

Trip Actuation Device Operability Test (TAD 0T) be performed to verify

that the reactor trip breaker and bypass breaker auxiliary and cell

switch contacts, used as P-4 interlock, provide the initiation signal to

Solid State Protection System (SSPS) and turbine Electrohydraulic

Control (EHC) systems.

Procedures 14420-1 " Solid State Protection System and Reactor Trip

Breaker Train A Operability Test.' Revision (Rev.) 27: 14420-2, ' Solid

State Protection System and Reactor Trip Breaker Train A Operability

Test." Rev. 19: 14421-1. " Solid State Protection System and Reactor Trip

Breaker Train B Operability Test." Rev. 8: and 14421-2, ' Solid State

Protection System and Reactor Trip Breaker Train B Operability Test."

Rev 6, provide the necessary guidance to perform tne 31-day staggered

test.

TS SR 3.3.2.9, Engineered Safety Feature Actuation System

Instrumentation, requires that an 18-month TADOT be performed to verify

that the P-4 issignal is generated for both the SSPS and EHC systems.

This test verifies that the P-4 signal is generated from both the

reactor trip and bypass breakers.

Procedure 14752-1 " Reactor Trip System P-4 Interlock Test," Rev. 4: and

14752 2, " Reactor Trip System P-4 Interlock Test," Rev. 4. provide the

test method to verify that the P-4 signal is generated to SSPS from the

reactor tri) and bypass breakers. In addition. Procedures 14752-1/2

test that tie P-4 signal is generated to the EHC from the reactor trip

breaker.

Contrary to the above, since initial startup of both Units 1 and 2.

Procedures 14420-1/2 and 14421-1/2 were inadequate, in that, they failed

to test all auxiliary and cell switch contacts of the reactor trip and

bypass breakers in accordance with TS SR 3.3.1.4. Additionally.

Procedures 14752-1/2 were inadequate. in that, they failed to test the

P-4 signal generated to the EHC system from the reactor trip bypass

breakers in accordance with TS SR 3.3.2.9.

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

Enclosure 1

9801200077 900112

PDR ADOCK 0500o424

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Notice of Violation 2-

Pursuant to the provisions of 10 CFR 2.201, Southern Nuclear Operating

Company, Inc. is hereby required to submit a written statement or explanation

to the U.S. Nuclear Regulatory Commission ATTN: Document Control Desk,  ;

Washington. 0.C. 20555, with a copy to the Regional Administrator, Region II,

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and a copy to the NRC Resident Inspector, Vogtle, 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 ham been taken and the results achieved. (3) the corrective steps that

w1il be t0 ken 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.

Because your res)onse will be placed in the NPZ r blic Document Room (PDR), to

the extent possi)le, it should not include any g monal privacy, 3roprietary,

or safeguards information so that it can be placed in the POR witicut

redaction. However, if you find it necessary to include such information, you

should clearly indicate the specific information that you desire not to be

placed in the PDR, and provide the legal basis to support your request for

withholding the information from the public.

Dated at Atlanta, Georgia

this 12th day of January 1998

Enclosure 1

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