ML20244E190

Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components), Fort Calhoun,Millstone Unit 2,Nine Mile Point Unit 2 & Fort St Vrain

ML20244E190
Person / Time
Site:	Millstone, Nine Mile Point, Fort Calhoun, 05000000, Fort Saint Vrain
Issue date:	07/31/1986
From:	Haroldsen R EG&G IDAHO, INC.
To:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
Shared Package
ML20236K073	List: ML20236K070 ML20236K081 ML20236K116 ML20244E190
References
CON-FIN-D-6001, CON-FIN-D-6002 EGG-NTA-7305, GL-83-28, NUDOCS 8608190421
Download: ML20244E190 (12)

Text

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1 CONFORMANCETOGENERICLETTEN'83-28 ITEM 2.1 (PART 1) EQUIPMENT CLASSIFICATION (RTS COMPONENTS)

FORT CALHOUN MILLSTONE UNIT 2 NINE MILE POINT UNIT 2 FORT ST. VRAIN R. Haroldsen i

Published July 1986 EG&G Idaho, Inc.

Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Comission Washington, D.C. 20555 Under DOE Contract No. DE-AC07-76ID01570

, FIN Nos. D6001 and D6002 O h k,3 h N b XA

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4 ABSTRACT This EG8G Idaho, Inc. report provides a review of the submittals from selected operating and applicant plants for conformance to Generic Letter

. 83-28, Item 2.1 (Part 1). The following plants are included in this review.

Plant Name Docket Number TAC Number Fort Calhoun 50-285 52339 Millstone Unit 2 50-336 52855 Nine Mile Point Unit 2 50-410 OL Fort St. Vrain 50-267 52840 e

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FOREWORD This report is supplied as part of the program for evaluating licensee / applicant conformance 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 Comission, Office of Nuclear Reactor Regulation, Division of PWR Licensing-A, by the EG8G Idaho, Inc.

The U.S. Nuclear Regulatory Commission funded this work under the authorization B&R 20-19-10-11-3 and 20-19-40-41-3, FIN Nos. D6001 and D6002.

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CONTENTS ABSTRACT .............................................................. ii FOREWORD .............................................................. iii

1. I NTRODUCTI ON AND SU MMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

2. PLANT RESPONSE EVALUATIONS ....................................... 3

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2.1 For Calhoun .......................~........................ 3 22 Conclusion ................................................. 3 2.3 Millstone 2 ......................................... ,.... 4 2.4 Conclusion ........ 4....................................... 4 2.5 N i ne M i l e P oi n t 2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5

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2.6 Conclusion ................................................. 5-2.7 Fort St. Vrain ............................................. 6 2.8 Conclusions ................................................ 7

3. GENERIC REFERENCES ............................................... 8 iv i - - - - - - _ - - . - _ .

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1. INTRODUCTION AND

SUMMARY

On February 25,1983, both of the scram circuit breakers at Unit 1 of the Salem Nuclear Power Plant failed to open upon an automatic reactor trip signal- f rom the reactor protection system. This incident was teminated

. manually by the operator about 30 seconds after the initiation of the automatic trip signal. The f ailure. of the circuit breakers was detennined

. to be related to the sticking of the undervoltage trip attachment. . Prior to the incident, on February 22, 1983, an automatic trip signal was generated at Unit 1 of the Salem Wuclear Power Plant based on steam gencr; tor low-low level during plant startup. In this case, the reactor was tripped manually by the operator almost coincidentally with the automatic trip.

Following these incidents, on February 28, 1983, the NRC Executive Director of Operations (EDO), directed the staff to investigate and report on the generic implications of these occurrences at Unit 1 of the Salem Nuclear Power Plant. The results of the staff's inquiry into the generic implications of the Salem Unit 1 incidents are reported in NUREG-1000,

" Generic Implications of the ATWS Events at the Salem Nuclear Power Plant."I As a result of this investigation, the Commission (NRC) requested (by Generic Letter 83-28, dated July 8, 1983)2 all licensees of operating reactors, applicants ..for an operating license, and hoIders of construction permits to respond to generic issues raised by the analyses of these two ATWS events. ,

This report is an evaluation of the responses submitted from a group of reactor plants for Item 2.1 (Part 1) of Generic Letter 83-28. The results of the reviews of several' plant responses are reported on in this document to enhance review efficiency. The specific plants reviewed in

. this ramrt were selected based on convenience of review. The actual documents which were reviewed for each evaluation are listed at the end of each plant evaluation. The generic documents referenced in this report are listed at the end of the report.

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Part 1 of Item 2.1 of Generic Letter 83-28 requires the licensee or applicant to confirm that all reactor trip system components are identified, classified, and treated as safety-related as indicated in the following statement:

. Licensees and applicants shall confirm that all components Nhose functioning is required to trip the reactor are identified as safety-related on documents, procedures, and inf ormation handling systems used in the plant to control safety-related activities, including maintenance, work ordersi and parts replacement.

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- 2. PLANT RESPONSE EVALUATIONS 2.1 Fort Calhoun, 50-285 TAC No. 52839 The licensee for the Fort Calhoun Nuclear Plant (Omaha Public Power

. District) provided responses to Items 2.1 (Part 1) of Generic Le'tter 83-28 in submittals dated November 4,1983 and May 24, 1985. The first submittal described an interim program for identifying and classifying components of the reactor protective system. This system was based on the " Interim Electrical CQE List." A plan was described for upgrading the systen, to provide confirmation that the list of safety-related components was complete and to review applicable procedures to insure that plant documents adequately control activities that relate to reactor protective system components.

The second submittal stated that review of the reactor protective

. system equipment list had been completed and the COE List was found to be accurate and complete. This list has been integrated into the plant information data base. The submittal also states that the review of reactor protective system procedure had been completed to verify the adequacy of controls. TI,e controls are said to meet the requirements of the Generic Letter.

2.2 Conclusions Based on the review of the licensee's submittal, we find that the components necessary to perform reactor trip are classified as safety-related and that activities relating to safety-related components are controlled by procedures which reflect the necessary requirements for handling safety-related components. We, therefore, find that the licensee's responses meet the requirements of Item 2.1 (Part 1) of Generic Letter 83-28 and are acceptable.

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References I

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1. Letter, W. C. Jones, Omaha Public Power District, to D. G. Eisenhut, NRC, November 4,1983.

. 2. Letter, R. L. Andrews, Omahu public Power District, to J. R. Miller, NRC, May 24, 1985.

2.3 Millstone Unit 2, 50-336, TAC No. 52855 The licensee for Millstone Unit 2 (Northeast Nuclear Energy Co.)

responded to the requirements of Item 2.1 (Part 1) in submittals dated November 8,1983 and May 9,1985. The submittals state that all components

- whose function is required to trip the reactor are identified as Category 1 (safety related) on their Material, Equipment and Parts List (MEPL) and that safety-related activities on tnese components including maintenance, work orders and parts replacement will be completed using Category 1 controls.

2.4 Conclusion Based on the review of the licensee's submittals we find that the licensee's responses confirm that the components necessary to perform reactor trip are classified safety related and that all activities relating ,

to these components are oesignated as safety related. These responses, therefore, meet the requirements of Item 2.1 (Part 1) of Generic Letter 83-28, and are acceptable.

References

1. Letter, W. G. Counsil, Northeast Nuclear Energy Co., to D. G. Eisenhut, NRC, November 8,1983.

2. Letter, J. F. Opeka, Northeast Nuclear Energy Co., to J. A. Zwolinski, NRC, May 9,1985.

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2.5 Nine Mile Point Unit 2, 50-410, (OL) l The applicant for Nine Mile Point Unit 2 (Niagra Mohawk Power Corporation) provided responses to Item 2.1 (Part 1) of Generic Letter 83-28 in submittals dated April 10, 1984, December 20,1985 and April 15,1986. The last of these submittals states that an equ'ipment classification list (0-list) is used at Nine Mile Point Unit 2 to identify safety-related components including those components which contribute to the reactor trip function.

Administrative controls consisting of documents, procedures and information handling systems are used to control safety-related activities including maintenance, work requests, parts replacements and modifications. These activities require classification information derived from the 0-list. A Computerized Infonnation handling system is being developed which will include information on all equipment installed at the plant.

2.6 Conclusion Based on the review of the licensee's submittal, we find that the components necessary to perform reactor trip are classified as safety-related and that activities relating to safety-related components are controlled by procedures which reflect the necessary requirements for ,

handling safety-related components. We, therefore, find that the licensee's response meets the requirements of Items 2.1 (Part 1) of Generic Letter 83-28 and is acceptable.

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,' ." 1 References I . 1' . Letter, G. K. Rhode, N4agra Mohawk Power Co., to A. Schwencer, NRC, April _10,1984 l, 2. Letter, T. E. Lempges, Niagra Mohawk Power Co., to A. Schwencer, NRC, L December 20, 1985.

3. Letter, T. E. Lempges, Niagra Mohawk Power Co., to E. G. Adensam, NRC, April 15,1986.

2.7 Fort St. Vrain, 50-267, TAC No. 52840 The licensee for the Fort St. Vrain Nuclear Plant (Public Service Company of Colorado) responded to the requirements of Item 2.1 (Part 1) of Generic Letter 83-28 in submittals dated November 4,1983 and June 12, 1985. The.first submittal states that the licensee was engaged in a project to highlight Class I electrical equipment required for safe shutdown including reactor trip system components on schematic drawings.

An audit has been completed by the licensee to verify that safety-related components are indicated as such on a computerized safety-related component list and on the process and instrumentation diagrams. Components are not necessarily labeled as safety-related within safety-related procedures but previde appropriate guidance for activities related to safety-related components. _

The June 12, 1985 submittal states that the plant maintenance procedures were being rewritten and that all reactor trip system components would be identified as safety-related in the revised procedures. The revised procedures were expected to be completed by January 3,1986.

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, 2.8 Conclusions Based on the review of the licensee's submittal, we find that the components necessary to perform reactor trip are classified as safety-related and that activities relating to safety-related components

, are controlled by procedures which reflect the necessary require'ments for handling safety-related components. We, therefore, find that the licensee's responses meet the requirements of Item 2.1 (Part 1) of Generic Letter 83-28 and are acceptable.

References

1. Letter, O. R. Lee, Public Service Company of Colorado, to D. G. Eisenhut, NRC, November 4,1983.

2. Letter, J. W. Gahm, Public Service Company of Colcrado, to Regional Administrator, Region IV, NRC, June 12, 1985.

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. 3. GENERIC REFERENCES

1. Generic Implications of ATWS Events at the Salem Nuclear Power Plant, NUREG-1000, Volume 1 April 1983; Volume '2, July 1983.

o 2. NRC Letter, D. G. Eisenhut to all Licensees of Operating Re' actors, 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.

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