ML20210K596

Forwards Insp Repts 50-327/86-27 & 50-328/86-27 on 860212-0314.Response to Concerns Identified During Insp, Including Lack of Available Calculations Supporting Original Design,Requested within 30 Days of Ltr Receipt

ML20210K596
Person / Time
Site:	Sequoyah
Issue date:	04/22/1986
From:	Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:	White S TENNESSEE VALLEY AUTHORITY
Shared Package
ML20210K600	List: IR 05000327/1986027 ML20210K596 ML20210K602
References
NUDOCS 8604280394
Download: ML20210K596 (6)

See also: IR 05000327/1986027

Text

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NUCLEAR REGULATORY COMMISSION

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Mr. S. A. White

Manager of Nuclear Power '

Tennessee Valley Authority

6N, 38A Lookout Place

1101 Market Street

Chattanooga, TN 37402-2801

Dear Mr. White:

SUBJECT: REPORT NOS. 50-327/86-27 AFD 50-328/86-27

On February 12 - March 14, 1986, the NRC staff conducted a specisi inspection

to examine design control practices for the Sequoyah Nuclear Power Plant.

The main focus of the inspection was to review the implementation and findings

of the Gilbert / Commonwealth technical review of Sequoyah Engineering Change

Notices (ECNs) for the main and auxiliary feedwater system and the TVA Office

of Engineering (OE) review of unimplemented or partially implemented ECNs at

Sequoyah. Reports for both these reviews were issued on March 4, 1986. The

NRC also conducted additional independent reviews.

The Gilbert / Commonwealth review was considered to be thorough and appropriate

in technical depth within the selected review scope. Specific Gilbert / Common-

wealth findings of significance included a failure to assess generic impli-

cations of concrete cracking near embedded plates due to inadequate edge

distance, and potential cable tray overloading caused by a failure to track

abandoned cables left in the trays. Gilbert / Commonwealth identified lack of

engineering evaluation, lack of documentation of evaluation, lack of detail in

design output, and lack of identification of design input and design bases as

root causes of the findings in their report. The technical and generic issues

identified by Gilbert / Commonwealth appear valid.

The OE "3 system review" was considered to be adequately implemented for the

purpose of determining the need to evaluate all incomplete ECNs. The TVA team

recommendation that all incomplete ECNs be evaluated appears appropriate. In

addition, the review recommended several corrective actions relating to the

control of plant configuration, with which the NRC team agrees.

The NRC team also independently examined the technical adequacy of several

design modifications to better assess the adequacy of the Gilbert and TVA

reviews. The NRC findings substantiate the need for comprehensive corrective

action and further evaluation as indicated by the two reviews. The NRC intends

to closely follow your activities relating to the assurance of adequacy of the

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8604280394 e60422

PDR ADOCK 05000327

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Mr. S. A. White -2- April- 22,1986

design control process. In the review of the additional design areas examined

by the NRC, the following concerns were identified by the NRC team during the

inspection.

In several cases standard industry codes and practices were not followed

in the samples of original design work examined by the NRC-staff in

conjunction with the review of the Gilbert / Commonwealth effort.

There is a lack of available-calculations' supporting the original design

in some disciplines. For example, calculations do not exist to support

the sizing of the station batteries, vital inverters, and battery chargers.

Temporary alteration procedures have been used for permanent design;

management controls did not provide timely engineering review and i

closure.  !

Seismic requirements were not being adequately handled as design input

in some instances nor were they translated into design output documents,

as evidenced by lack of specification of these requirements in purchase ,

documents and vendor data sheets. .I

Five cases were identified where design modifications violate the assump-

tions or the statements contained in unreviewed safety question

determinations.

The concerns and findings of the NRC inspection have been classified as defi-

ciencies, unresolved items, and observations. Deficiencies are errors, procedural

violations or inconsistencies with respect to NRC regulatory requirements or. i

licensing commitments. Unresolved items have been identified where more infor-

mation is needed to reach a conclusion. Other. observations have been described

where it was considered appropriate to call your attention to matters which are

nat deficiencies or unresolved items, but which are recommended for your

consideration.

You should respond in writing to the deficiencies and unresolved items within

30 days after receipt of this letter. In your assessment of individual defi . -i

ciencies identified in the inspection report, you are requested to address the

cause, the extent to which the condition may be reflected in the unreviewed

portion of the design, action to correct the existing condition, the action i

taken to prevent recurrence, and any other information you consider relevant.  !

For unresolved items, the response should provide information needed to reach-

conclusions concerning acceptability of the specific feature or practice involved.

Comments on observations may be included in your response in addition to'the

requested information but they are not required. Several of the items identified

by the team may be considered Potential Enforcement Findings. Formal enforcement

action, including any further action required, will be identified after receipt

and evaluation of your response.

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Mr. S. A. White .-3- April 22,1986

.In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosures

will be placed in the NRC Public Document Room.

i

Should you have any questions concerning this inspection, please contact me or

Mr. Ted Ankrum (301-492-4774) of this office.

Sincerely,

- >$Y

j@(Es

s M. Tay1 , Director

fice of Inspection and Enforcement

-

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Enclosure:

Inspection Report 50-327/86-27 and 50-328/86-27

cc w/ enclosures: See next page

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._ - __. _ _ _ . , - . .. - , _ . . .

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Mr. S. A. White Sequoyah Nuclear Power Plant

Tennessee Valley Authority

cc:

, Herbert S. Sanger, Jr., Esq. '

Tennessee Department of Public Health

General Counsel ATTN: Director, Bureau of Environmental

Tennessee Valley Authority Health Services

400 West Summit Hill Drive, E 118 33 Cordell Hull Building

Knoxville, TN 37902 Nashville, TN 37219

Mr. K. W. Whitt Mr. Michael H. Mobley, Director

Tennessee Valley Authority Division of Radiological Health

400 West Summit Hill Drive, E3A8 T.E.R.R.A. Building

Knoxville, TN 37902 150 9th Avenue North

Nashville, TN 37203 l

Mr. Bob Faas t

Westinghouse Electric Corp.

'

County Judge

P.O. Box 355 Hamilton County Courthouse

Pittsburgh, PA 15230 Chattanooga, TN 37402

Mr. Jerry Wills

Tennessee Valley Authority

SN 133 Lookout Place

Chattanooga, TN 37402-2801

>

Mr. Donald L. Williams, Jr.

Tennessee Valley Authority

400 West Summit Hill Drive, W10B85

,

Knoxville, TN 37902

Resident Inspector /Sequoyah NPS

c/o U.S. Nuclear Regulatory Commission

2600 Igou Ferry Road

Soddy Daisy, TN 37379

Regional Administrator, Region II

U.S. Nuclear Regulatory Commission

101 Marietta Street, N.W., Suite 2900

Atlanta, GA 30323

Mr. Everett Whitaker

Tennessee Valley Authority

SN 128B Lookout Place

Chattanooga, TN 37402-2801

.

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Mr. S. A. White

Distribution:

DCS

PDR

LPDR

DQAVT Reading

QAB Reading

NRC TVA Senior Mgmt Team

RArchitzel, IE

LSpessard, IE

EVImbro, IE

GTAnkrum, IE

HMiller, IE

BKGrimes, IE

JMTaylor, IE

RHVollmer, IE

ELJordan, IE

Resident Inspector

Inspection Team (7)

NSIC

Regional Administrator, II

TMNovak, NRR

NTIS

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JAAxelrad, IE

SWeise, RII

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CRStahle, NRR

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LIST OF ABBREVIATIONS

ACI American Concrete Institute

AISC American Institute of Steel Construction

ASME American Society of Mechanical Engineers

ANSI American National Standards Institute

ASTM American Society for Testing and Materials

CEB Civil Engineering Branch

CFR Code of Federal Regulations

CVCS Chemical and Volume Control System

ECN Engineering Change Notice

'

ERCW Essential Raw Cooling Water

ESF Engineered Safety Features

FSAR Final Safety Analysis Report

G/C Gilbert / Commonwealth

HVAC Heating, Ventilation and Air Conditioning

IEEE Institute of Electrical and Electronics EnginesFs

LOCA Loss of Coolant Accident

NRC U.S. Nuclear Regulatory Commission

NSSS Nuclear Steam Supply System

, OE Office of Engineering

P&ID Piping and Instrumentation Diagram

RCS Reactor Coolant System

TACF Temporary Alteration Control Form

TVA Tennessee Valley Authority _

USQ Unreviewed Safety Question

USQD Unreviewed Safety Question Determination

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