ML17334B101

Forwards Conformance to Generic Ltr 83-28,Items 2.1 (Part 1) Equipment Classification,Cook Units 1 & 2, Final Rept

ML17334B101
Person / Time
Site:	Cook
Issue date:	03/19/1987
From:	Roberts E EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:	Carrington M Office of Nuclear Reactor Regulation
Shared Package
ML17334B103	List: ML17334B101 ML17334B110
References
CON-FIN-D-6001 EWR-55-87, GL-83-28, NUDOCS 8706080032
Download: ML17334B101 (14)

Text

Idaho Nstlons/ Englneesfng Laboratory March 19, 1987 Mr. M. Carrington, Project Manager of Nuclear Reactor Regulation 'ffice U. S. Nuclear Regulatory Commission Washington, D.C. 20555 TRANSMITTAL OF FINAL REPORT, "CONFORMANCE TO GENERIC LETTER 83-28, ITEMS 2.1 (PART 1) EQUIPMENT CLASSIFICATION, COOK UNITS 1 AND 2" EGG-NTA-7609, MARCH 1987, (FIN D6001) EWR-55-87 Ref: NRC Form 189, "Evaluation-Conformance to Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events" (FIN'D6001), June 1986.

Dear Mr. Carrington:

Transmitted herewith is the above subje'ct report.

The report documents INEL's evaluation of the licensee actions in response to the NRC Generic Letter 83-28, Item 2. 1 (Part 1), Equipment Classification (RTS Components). Based on the licensee submittals, we conclude that the plant conforms to the requirements of the generic letter on this item.

Very truly yours, E. W., Roberts, Manager NRC Headquarters Support gmp

Enclosure:

As Stated cc; A. Toalston, NRR-PAEI (2)

G. L. Jones, DOE-ID J. O. Zane, EG&G Idaho, Inc. (w/o Encl.)

SP07R06080032 ADOCX 8703l9 050003 PDR 0

++lE&ECV~lckho, Inc. Rockville Pike 11428 $ 'uite 410 Rockvllle, MD 2085i2

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EGG-NTA-7609 CONFORMANCE TO GENERIC LETTER 83-28 ITEM 2.1 (PART 1) EQUIPMENT CLASSIFICATION (RTS COMPONENTS)

COOK UNITS 1 AND 2 Docket Nos. 50-315/316 R. Haroldsen Published March 1987 EGEG Idaho, Inc.

idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Under DOE Contract No. DE-AC07-76ID01570 FIN No. D6001

ABSTRACT This EGEG Idaho, Inc. report provides a review of the submittals from Cook Units 1 and 2 for conformance to Generic Letter 83-28, Item 2.1 (Part 1), equipment classification of reactor trip system components.

Docket Nos. 50-315/316 TAC Nos. 52989 and 52990

FOREWORO 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 Commission, Office of Nuclear Reactor Regulation, Oivision of PWR Licensing-A, by the EG&G Idaho, Inc.

The U.S. Nuclear Regulatory Commission funded this work under the authorization B8R No. 20-19-10-11-3, FIN No. 06001.

CONTENTS ABSTRACT FOREWORO

l. INTROOUCTION ANO

SUMMARY

2. PLANT RESPONSE EVALUATION

2. 1 Conclusion ..

3. GENERIC REFERENCES

l. INTRODUCTION AND

SUMMARY

On February 2S, 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 from the reactor protection system. This incident was terminated manually by the operator about 30 seconds after the initiation of the automatic trip signal. The failure of the circuit breakers was determined 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 Nuclear Power Plant based on steam generator low-low level during plant startup. In this case, the reactor was tripped manually by the operator almost conincidentally with the automatic trip.

Following these incidents, on February 28, 1983, the NRC Executive Director of Operations (EDO), directed the staff to investigate the 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 ATMS Events at the Salem Nuclear Power Plant." As a result of this investigation, the Commission (NRC) 2 requested (by Generic Letter 83-28, dated July 8, 1983) all licensees of operating reactors, applicants for an operating license, and holders of contstruction permits to respond to generic issues raided by the analyses of these two ATMS events.

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 whose fundtioning is required to trip the reactor are identified as safety-related on documents, procedures, and information handling systems used in the plant to control safety-related activities, including maintenance, work orders, and parts replacement.

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2. PLANT RESPONSE EYALUATION The licensee for Cook Units 1 and 2, Indiana and Michigan Electric Co., provided responses relating to Item 2. 1 (Part 1) in submittals dated November 4, 1983, March 30, 1984, April 10, 1985 and December 19, 1986.

The first of these submittals describes the criteria used by the licensee to identify the safety-related components of the reactor trip system.

The submittal states that the method used to control activities relating to safety-related components is different than that described in Item 2. 1 (Part 1) of the Generic Letter 83-28. It is stated that the N-list is one of the documents utilized to identify equipment as being safety-related. However, it also states that the list is not all inclusive and therefore not the sole source of reference. Other documents such as the FSAR, Technical Specifications, communications to the NRC, flow diagrams, isometrics, electrical one line and elementary diagrams are also consulted.

In the subsequent submittals, the licensee stated that a computerized component classification data-base was being implemented which will incorporate references to existing relevant drawings and procedures. The data-base has been designed to integrate existing documents and information systems to manage purchase, maintenance and replacement of safety-related components.

The December 19, 1986 submittal confirmed that computerized component classification system had been completed and is functional.

2. 1 Conclusion Based on our review of the licensee's submittals, we find that the licensee has identified the components necessary to perform reactor trip and that these components are classified safety-related in an equipment classification system which controls activities relating to the

~ ~ safety-related components. We therefore, find that the 1> ensee's responses meet the requirements of Item 2. 1 (Part 1) of Generic Letter 83-28 and are acceptable.

References

1. Letter, M. P. Alexich, Indiana and Michigan Electric Co., to D. G. Eisenhut, NRC, November 4, 1983.

2. Letter, M. P. Alexich, Indiana and Michigan Electric Co., to D. G. Eisenhut, NRC, March 30, 1984.

3. Letter, M. P. Alexich, Indiana and Michigan Electric Co., to

0. G. Eisenhut, NRC, April 10, 1985.

4. Letter, M. P. Alexich, Indiana and Michigan Electric Co., to H. R. Denton, NRC, December 19, 1986.

3. GENERIC REFERENCES

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

2. NRC 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.

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NRC FOAM 225 US NUCLEAR REGULATORY CQMMISSION I AEPOAT NUMSEA IAH~saop TIOC. nod Vol IYa, ilsnYI IC Ssl NACLI I 102.

220 I. 2202 BIBLIOGRAPHIC DATA SHEET EGG-NTA-7609 SEE INSTRUCTIONS ON THf. AfVERSE 2 LEAVE CLANK CONFORMANCE TO GENERIC LETTER 83-28, ITEM 2. 1 (PART 1), EQUIPMENT CLASSIFICATION COOK UNITS 1 AND 2 S GATE AEPOAT CQMPLETEO MONTH YEAR 5, AUTHQAISI March 1987 R. O. Haroldsen SOATS REPQR'I ISSUEO MONTH YEAR March 1987 2, PERFORMING ORGANIZATION NAME ANO MAILINGAOORESS IInsloaon O COOOI S. PAOIECTITASKAYOAKUFRT NUMSEA EGSG Idaho, Inc.

PIN OR GRANT NUMSCR P. 0. Hox 1625 S.

Idaho Falls, ID 83415 D6001 I0. SI'ONSORING OAOANICATIONNAMC ANO MAILINGAOOAFSS IlncloooZo Coool I la. TYPE OF REPORT Division of Systems Integration Technical Evaluation Report Office of Nuclear 'Reactor Regulation U. S. Nuclear Regulatory Commission S. PERIOO COVEREO IinslolnNOINII Washington, DC 20555 I'2 SUPPLEMENTARY NO'TES

'IS, ASSTA ACT I200 ~oral on loul This EG8G Idaho, Inc. report provides a reviewer of the submittals from Cook Units 1 and 2 for conformance to Generic Letter 83-28 Item 2.1 (Part 1) Equipment Classification (RTS Components).

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