ML19294B259

Technical Evaluation Rept of Tech Spec Change for Browns Ferry Unit 3.

ML19294B259
Person / Time
Site:	Browns Ferry
Issue date:	10/31/1979
From:	Cleveland C EG&G, INC.
To:	Shemanski P Office of Nuclear Reactor Regulation
References
CON-FIN-A-6256 EGG-EA-5045, EGG-EA-5054, NUDOCS 8002280102
Download: ML19294B259 (7)

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KNIUEG&G M8 INTERIM REPORT Accession No. .

Report No. EGG-EA-5045 Contract Program or Project

Title:

Electrical, Instrumentation and Control System Support Subject of this Document: Technical Evaluation Report of the Technical Specification Change for Browns Ferry Unit 3 Type of Document: Informal Report C, J. Cleveland Author (s):

Date of Document: October 1979 Responsible NRC Individual and NRC Office or Division: Paul Shemanski, Division of Operating Reactors This document was prepared primarily for preliminary or internal use. It has not received full review and approval. Since there may be substantive changes, this document should not be considered final.

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EGG-EA-5045 October 1979 TECHNICAL EVALUATION REPORT OF THE TECHNICAL SPECIFICATION CHANGE FOR BROWNS FERRY UNIT 3 t, . J. Cleveland D IP D lgr r:

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FOAuEG&b D8 INTERIM REPORT Accession No.

Report No. EGG-EA-5045 Contract Program or Project

Title:

Electrical, Instrumentation and Control System Support Subject of this Document:

Technical Evaluation Report of the Technical Specification Change for Browns Ferry Unit 3 (Docket 50-296)

Type of Document:

Informal Report Author (s):

C. J. Cleveland Date of Document:

October 1979 Responsible NRC Individual and NRC Office or Division:

Paul Shemanski, Division of Operating Reactors This document was prepared primarily for preliminary orinternal use. it has not received full review and approval. Since there may be substantive changes, this document should not be considered final.

EG&G Idaho, Inc.

Idaho Falls, Idaho 83401

, Prepared for the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy Idaho Operations Office NRC FIN No.

A6256 INTERIM REPORT K RC Researc'ri and TecMica p a. conm 1

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TECHNICAL EVALUATION REPORT TECHNICAL SPECIFICATION CHANGE FOR BROWNS FERRY UNIT 3 Docket No. 50-296 (TAC No. 11998)

C. J. Cleveland 9

CONTENTS

1.0 INTRODUCTION

. . . . . . . . . . . . . . . . . . . . . . . . . I 2.0 DISCUSSION . . . . . . . . . . . . . . . . . . . . . . . . . . I

3.0 CONCLUSION

, . . . . . . . . . . . . . . . . . . . . . . . . . I

4.0 REFERENCES

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TECHNICAL EVALUATION REPORT TECHNICAL SPECIFICATION CllANGE FOR BROWNS FERRY UNIT 3 1,0 INTRODUCTION On August 6, 1979, the Tennessee Valley Authority (TVA) submitted a proposed amendment to the Technical Specifications of Bcowns Ferry Unit 3. The changes that are proposed are the result of modifications to the Low Pressure Coolant Injection (LPCI) system. This report deals only with the changes to the Technical Specifications that involve the modifications on the AC and DC power supplies.

2.0 DISCUSSION To make the onsite power system meet the single failure criteria following the modifications to the LPCI system, the TVA has added a new quclified battery source to a 4 kV shutdown board. Another significant

. change to the power system has been the addition of two new 480 V MOV hoards using qualified motor-generator (M/G) sets to tie these MOV boards to the 480 V shutdown boards. These M/G sets will be installed at a later date because of delivery problems. The function of these M/G sets is to isolate the 480 V MOV boards and shutdown boards.

Two of these sets are used on each of the new 480 V MOV boards to meet single failure criteria, and they include an autotransfer feature.

The TVA has submitted changes to the Technical Specifications to include the new battery source in all their existing limiting condi-tions and surveillance requirements for Browns Ferry Unit 3. The limiting conditions or the surveillance requirements have not been compromised by the licensee's proposal.

3.0 CONCLUSION

Based on our review, we conclude that the proposed Technical Spec-ification changes are acceptable. The limiting conditions assure that 1

the batteries are in service for plant operation and the sureveillance requirements assure that the batteries will be capable of performing their functions when needed.

4.0 REFERENCES

1. L. M. Mills to H. R. Denton, letter dated August 6, 1979. '

2. IEEE Standard 308-1974, "IEEE Standard Criteria for Class IE Power Systens for Nuclear rower Centrating Stations."

3. IEEE Standard 450-1975, "IEEE Recommended Practice for Mainten-ance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations."

4. Branch Technical Position EICSB 6, " Capacity Test Requirements of Station Batteries--Technical Specifications."

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