ML20195C761

Forwards Insp Repts 50-327/88-29 & 50-328/88-29 on 880620- 0708 & Notice of Violation

ML20195C761
Person / Time
Site:	Sequoyah
Issue date:	10/20/1988
From:	Richardson S NRC OFFICE OF SPECIAL PROJECTS
To:	White S TENNESSEE VALLEY AUTHORITY
Shared Package
ML20195C765	List: ML20195C761 ML20195C769 ML20195C775
References
NUDOCS 8811030366
Download: ML20195C761 (4)

See also: IR 05000327/1988029

Text

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OCT 2 01933

Docket Nos.: 50-327 and 50-328

License Nos. DPR-77 and DPR-79

/ Tennessee Valley Authority

/ ATTN: Mr. S. A. White

Senior Vice President,

Nuclear Power

6N 38A Lookout Place

1101 Market Square

j Chattanooga, TN 37402-2801

Gentlemen:

SUBJECT: NOTICE OF VIOLATION

(NRC INSPECTION REPORT NOS. 50-327/88-29 AND 50-328/88-29)

This refers to Nuclear Regulatory Commission (NRC) special announced team

inspection conducted by K. Jenison on June 20, 1988 through July 8, 1988. The

inspectior. included a review of the activities associated with the startup of

Sequoyah Unit 1 and the Sequoyah restart program matrix. At the conclusion of

the inspection, the findings were discussed with those members of your staff

identified in the enclosed inspection report.

The purpose of this inspection was to determine if adequate implementation of

corrective actions had occurred to support Unit I startup. These corrective

actions included TVA Nuclear Perfora nce Plan implementation and evaluation of

equivalent Unit 2 startup items on Unit 1. This determination was based on a

sample of the programma*.ic corr'ective actions that pertained to the containment

spray system. The results cf this inspection were used to evaluate the need

for additional NRC activity in specifically identified areas.

This inspection was composed of design and as-constructed aspects. Contact was

maintained between inspectors in each area such that their respective efforts

and inspection findings were coordinated. The design portions consisted of a

review of portions of the containment spray system design, design bases and

design requirements. The as-constructed portion consisted of an in plant

review in the mechanical, electrical, civil, structural, and instrumentation

and control disciplines in order to verify that the containment spray system as

currently constructed and installed is in accordance with the licensed design

basis, system design specifications, applicable drawings, system modifications

and temporary alterations. In addition, the operational capability of the

containment spray system was evaluated by reviewing the system operating

instructions and procedures, surveillance and testing requirements, corrective

and preventive maintenance activities, emergency operating instructions and

operator training. The inspection team evaluated, on a sampling basis,

8811030366 001020

PDR ADOCK 05000327

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Tennessee Valley Authority 2

portions of the TVA Nuclear Performance Plan functional corrective action

areas that were not addressed for Unit 1 in other inspections. The areas not

addressed for Unit 1 in other inspections were established by a review of

those NRC inspections conducted since the shutdown of Sequoyah Units 1 and 2

(August 1985).

The inspection findings indicate Uias certain activities appeared to violate

NRC requirements. The identified violations involved aissing system design

basis calculations, procedural noncompliances associated with electrical work,

structural walkdown discrepancies, and procedure inadequacies in the areas of

ASME Section XI testing and weld evaluations. The violatuns, references to

pertinent requirements, and elements to be included in you, response are

described in the enclosed Notice of Violation.

As discussed during the exit, several of the above violations have additional

corrective actions associated with them in order to ensure adequate resolution

of the issue. These additional corrective actions are as follows:

Violation 327, 328/88-29-01, Design Basis Calculation Discrepancies, has

associated with it additional corrective actions identified as Unresolved

Item 327,328/88-29-06a through s. Adequate corrective action for .his

violation should include resolution of these issues and a 100% Engineering

Assurance review of the results.

Violation 327,328/88-29-02, Structural Walkdown Discrepancies, Ms

associated with it additional issues which require unique, generic a,d

programmatic review. This review should also include a TVA Quality

Assurance review of the TVA pre-SSQE walkdown discrepancies and the

applicability of those discrepancies to other components.

Violation 327,328/88-29-03, Maintenance of Safety-Related Electrical

Equipment, has associated with it additional issues which require unique,

generic and programmatic review. This review should also include a TVA

Quality Assurance review of the TVA pre-SSQE walkdown discrepancies and

the applicability of those discrepancies to other components.

In addition to the above violations, several commitments were made during the

exit meeting on July 8, 1988, conducted for this inspection. These commitments

were:

To test the containment spray pump flow characteristics using a multiple

point test prior to the startup cf Unit 3.

To test the ESF pump valve logic performance as demonstrated in surveil-

1. lance instruction 68 prior to the startup of Unit 1.

To complete licensee actions associated with establishing the 143 psid

pressure required to ensure 4750 gpm f rom the containment spray pumps

prior to the startup of Unit 1.

To determine actual containment spray anu RHR heat exchanger differential

pressure in order to resolve restart test functions72-003 and 72-018

prior to the startup of Unit 1.

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To include in the next scheduled update of the containment spray training

lesson p'ans, information on the manual suction source swapover of the ,

containment spray system and the interlocks associated with the system.

Based on a review of the containment spray system, there appears to be adequate

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program implementation in the following areas to support Unit 1 startup without

i further NRC inspection: i

Design Basis Verification Program ,

TVA as-constructed walkdowns  ;

Drawing Control Program

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Inplant Configuration Control and System Alignment

Surveillance Instructions

ASME Section XI

Restart Test and Functional Performance Program

Cricical Calculation Regeneration Program

De*,ign Change and Modifications Program

Caole Routing and Cable Leading

Equipment Qualification and Seismic Programs

Preoperational Test Program

Employee Concerns

Condition Adverse to Quality Reports including the Quality Assurance

audit process

Potential Reportable Occurrences and Licensee Event Reports

4 Nuclear Experience Review

Instrument Line Slope

System Operating and Emergency Operating Instructions

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Alternate and Rigorous Support Analysis

1 Maintenance (including trending, material control, preventive maintenance ,

and housekeeping)  ;

Operability Lookback  :

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Fi:tform Thermal Growth

Cable Tray Supports

Welding (including pipe, structural, and civil) i

1 Operator Training  !

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Nuclear Performance Plan implementation requiring additional NRC review I

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is as follows:

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Critical Calculations Regeneration Program (as part  :

i of violation 327, 328/88-29-01 review) (

Appendix R  !

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Electrical System SER related issues

Functional test observation of pump flow and component

, logic

' 10 CFR 50 Appendix J testing  !

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Tennessee Valley Authority 4

In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2,

Title 10. Code of Federal Regulations, a copy of this letter, its enclosures,

and any reply will be placed in the NRC's Public Document Room.

The responses directed by this letter and its enclosures are nct subjected to

the clearance procedures of the Office of Management and Budget a> required by

the Paperwork Reduction Act of 1980, PL 96-511.

Should you have any questions concerning this letter, please contact us.

Sincerely,

{) Ah w0 S& *

Steven D. Richardson, Director

TVA Projects Division

Office of Special Projects

Enclosures:

1. Notice of Violation

2. NRC Inspection Report

cc w/encis:

/J. L. Kirkebo, Vice President

Nuclear Engineering

vJ. L. LaPoint, Acting Site Director

Sequoyah Nuclear Plant

4 . L. Gridley, Director

f Nuclear Safety and Licensing

'M. R. Harding, Site Licensing

Manager

/TVA Representative, Rockville

Office

sState of Tennessee

General Counsel, TVA

bec w/encis:

-J. G. Partlow, OSP

S. C. Black, OSP

B. D. Liaw, OSP

F. R. McCoy, OSP

,K. P. Barr, OSP

.L. J. Watson, OSP

',J. B. Brady, OSP

i R. E. Shewmaker, OSP

i '/J. Rutberg, OGC

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NRC Resident Inspector -

NRC Occument Control Desk 7'

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