ML20244D769

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Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3,River Bend Unit 1
ML20244D769
Person / Time
Site: River Bend Entergy icon.png
Issue date: 11/30/1985
From: Haroldsen R
EG&G IDAHO, INC.
To:
NRC
Shared Package
ML20234E002 List:
References
CON-FIN-D-6002 EGG-NTA-7097, GL-83-28, NUDOCS 8604070510
Download: ML20244D769 (8)


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CONFORMANCE TO GENERIC LETTER 83-28 ITEMS 3.1.3 AND 3.2.3 RIVER BEND UNIT 1 R. Haroidsen Published November 1985 EG&G Idaho, Inc.

Idaho Falls, Idaho 83415 Preparert for the U.S. Nuclear Regulatory Commission Washington, D.C. 20555

. Under 00E Contract No. DE-AC07-761001570 FIN No. 06002

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'I ABSTRACT q Tnis EG&G Idaho, Inc., report provides a review of the submittals from River Bend Unit 1, for conformance to Generic Letter-83-28, items 3.1.3 and 3.2.3.

FOREWORD This report is supplied as part of the program for evaluating licensee / applicant ccnformance to Generic Letter 83-28 " Required Actions Based on Generic Implications of Salem ATWS Events." This work is being conducted for the U.S. Nuclear Regulatory Commission, Office of Nuclear, Reactor Regulation, Division of System Integration by EG&G Idaho, Inc., NRR and I&E Support Branch.

The U.S. Nuclear Regulatory Commission funded the work under the authorization, B&R 10-19-19-11-3, FIN No. D6002.

Docket No. 50-458 ii

CONTENTS ABSTRACT .............................................................. ii.

FOREWORD ................. ............................................

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1. INTF,00UCTI0f4 ...................................................... 1 REVIEW REQUIREMENTS ...............................................
2. 2
3. REVIEW RESULTS .................................................... 3 3.1 Evaluation ................................................... 3 3.2 Conclusion .................................................. 3
4. REFERENCES ........................................................ 4 i

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.eL 9 C0tiFORMANCE.T0 GENERIC LETTER 83-28 ITEMS 3.1.3 AND 3.2.3 RIVER' BEND UNIT 1

1. ' INTRODUCTION On July'8, 1983,. Generic Letter No. 83-28 was issued by D. G. Eisenhut, Director.of the Division of Licensing, Nuclear Reactor Regulation, to all licensees of operating reactors, applicants for

'merating licenses, and holders of construction permits. This letter included! required actions based on the generic implications of the Salem ATWS events..'These requirements have been published in Volume 2 of J

NUREG-1000, " Generic Implications of ATWS Events at the Salem Nuclear Power.-

Plant".2 Tnis report documents the EG&G Idano, Inc. review of the submittals.

from River Bend Unit i for conformance to items 3.1.3 and 3.2.3 of Generic Letter 83-28. The submittals and other documents utilized in this evaluation are referenced in Section 4 of this report.

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2. REVIEW REQUIREMENTS Item 3.1.3 (Post-Maintenance Testing of Reactor Trip System Components) requires licensees and' applicants to identify, if applicable, any post-maintenance test requirements for the reactor trip system (RTS) in

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existing. technical specifications which can be demonstrated to degrade rather than enhance safety. Item 3.2.3 applies this same. requirement to 611 other' safety-related components. .Any proposed technical specification changes resulting from this action shall receive a pre-implementation review by NRC.

The relevant submittals for River Bend Unit I were reviewed to oetermine compliance with items 3.l.3 and 3.2.3 of the generic letter.

First, the submittals from this plant were reviewed to determine that tnese two items were specifically addressed. Second, the submittals were checked i to determine if any post-maintenance test items specified in the technical specifications were identified that were suspected to degrade rather than enhance safety. Last, the submittal was reviewed for evidence of special conditions or other significant'information relating to the two items of concern.

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3. REVIEW-RESULTS FOR RIVER BEND UNIT 1 3.1 Evaluation Gulf States Utilities Company, the applicant for River Bend Unit 1,

- stated in their submittal dated August 3, 19843 that a response to items 3.1 and 3.2 would be provided prior to fuel' loading. A subsequent submittal dated March 20, 1985 provided a specific response to both items 3.1.3 and 3.2.3. In the response the applicant stated that a review of the draft technical specifications revealed no post-maintenance test requirements which degrade rather than enhance safety.

3.2 Conclusions l The applicant's responses to items 3.1.3 and 3.2.3 meet the requirements of Generic Letter 83-28 and are acceptable.

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4.- REFERENCES

1. f4RC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits,

" Required Actions Based on Generic Implications of Salem ATWS Events .

(Generic Letter 83-28)", July 8, 1983.

2. Generic Implications of ATWS Events at the Salem Nuclear Power Plant, -

hUKEG- 1000, . Vo lume 1, Apri l 1963; Volume 2, July 1963.

3. Letter, J. E. Booker, Gulf States Utilities Co., to D. G. Eisenhut, NRC, August 3, 1984.
4. Letter, J. E. Booker, Gulf States Utilities Co., to H. R. Denton, NRC, March 20, 1985.

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