ML20214R739

Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Clinton, Final Informal Rept

ML20214R739
Person / Time
Site:	Clinton
Issue date:	03/31/1987
From:	Udy A EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:	NRC
Shared Package
ML20214R737	List: ML20214R734 ML20214R739
References
CON-FIN-D-6002 EGG-NTA-7559, GL-83-28, NUDOCS 8706080283
Download: ML20214R739 (16)

Text

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.i EGG-NTA-7559 March 1987 INFORMAL REPORT a

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. CONFORMANCE TO GENERIC LETTER 83-28 ITEM 2.2.2--

Engineenng . VENDOR INTERFACE PROGRAMS FOR ALL OTHER SAFETY-Laboratory RELATED COMPONENTS: CLINTON ,

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o DISCLAIMER This book was prepared as an account of work sponsored by an agency of the United States Govemment. Neither the Uruted States Government not any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal hability or responsibehty for the accuracy, completeness Or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not intnnge pnvately owned nghts. References herein to any spooft commercal product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessanly constitute or imply its endorsement, recommendation, or favonng by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessanly state or reflect those of the Uruted States Govemment or any agency thereof.

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EGG-NTA-7559 i

TECHNICAL EVALUATION REPORT 4 .

CONFORMANCE TO GENERIC LETTER 83-28, ITEM 2.2.2--

VENDOR INTERFACE PROGRAMS FOR ALL OTHER SAFETY-RELATED COMPONENTS:

CLINTON i

l Docket No. 50-461 r

i Alan C. Udy l

Published March 1987 i

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l Idaho National Engineering Laboratory EG&G Idaho, Inc.

Idaho Falls, Idaho 83415 i

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! Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Under DOE Contract No. DE-AC07-76ID01570 FIN No. D6002

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ABSTRACT This EG&G Idaho, Inc., report provides a review of the submittals from the Illinois Power Company regarding conformance to Generic Letter 83-28, Item 2.2.2, for the for the Clinton Power Station.

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Docket No. 50-461 11 4

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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 Commission, Office of Nuclear Reactor Regulation, Division of PWR Licensing-A, by EG&G Idaho, Inc., NRR and I&E Support Branch.

The U.S. Nuclear Regulatory Commission funded this work under the authorization B&R No. 20-19-40-41-3, FIN No. 06002.

Docket No. 50-461 iii

CONTENTS t

ABSTRACT .............................................................. 11 1

FOREWORD .............................................................. iii

1. INTRODUCTION ..................................................... 1

2. REVIEW CONTENT AND FORMAT ........................................ 2 r

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3. ITEM 2.2.2 - PROGRAM DESCRIPTION ................................. 3-i .

3.1 Guideline .................................................. 3 t 3.2 Evaluation ................................................. 3 3.3 Conclusion ................................................. 4

4. PROGRAM WHERE VENDOR INTERFACE CANNOT PRACTICABLY BE j ESTABLISHED ...................................................... 5 4.1 Guideline .................................................. 5 1 4.2 Evaluation ................................................. 5 ,

4.3 Conclusion ................................................. 6

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! 5. RESPONSIBILITIES OF LICENSEE / APPLICANT AND VENDORS THAT PROVIDE j SERVICE ON SAFETY-RELATED EQUIPMENT .............................. 7 1 5.1 Guideline .................................................. 7

{ 5.2 Evaluation ................................................. 7 5.3 Conclusion ................................................. 7

6. CONCLUSION ....................................................... 8 j 7. REFERENCES ....................................................... 9 1

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i. CONFORMANCE TO GENERIC LETTER 83-28. ITEM 2.2.2--

4 VENDOR INTERFACE PROGRAMS FOR ALL OTHER SAFETY-RELATED COMPONENTS:

CLINTON

1. INTRODUCTION 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 l signal from the reactor protection system. This incident was terminated manually by the operator about 30 seconds after the initiation of the 2 automatic trip signal. The failure of the circuit breakers was determined to be related to the sticking of the undervoltage trip attachment. Prior  ;

j to this incident, on February 22, 1983, at' Unit 1 of the Salem Nuclear i Power Plant, an automatic trip signal was generated based on steam i

generator low-low level during plant startup. In this case, the reactor was tripped manually by the operator almost coincidentally with the l

' automatic trip. I Following these incidents, on February 28, 1983, the NRC Executive  !

Director for Operations (EDO), directed the NRC staff to investigate and

report on the generic implications of these occurrences at Unit 1 of the j Salem Nuclear Power Plant. The results of the staff's inquiry into the generic implications of the Salem unit incidents are reported in NUREG-1000, " Generic Implications of the ATWS Events at the Salem Nuclear l Power Plant." As a result of this investigation, the Commission (NRC) 1 requested (by Generic Letter 83-28 da'ted July 8,1983 ) all licensees of j operating reactors, applicants for an operating license, and holders of l construction permits to respond to the generic issues raised by the analyses of these two ATWS events.

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This report is an evaluation of the responses submitted by the l

Illinois Power Company, the licensee for the Clinton Power Station, for f*

Item 2.2.2 of Generic Letter 83-28. The documents reviewed as a part of this evaluation are listed in the references at the end of this report.

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2. REVIEW CONTENT AND FORMAT Item 2.2.2 of Generic Letter 83-28 requests the licensee or applicant to submit, for the staff review, a description of their programs for interfacing with the vendors of all safety-related components including supporting information, in considerable detail, as indicated in the guideline section for each case within this report.

These guidelines treat cases where direct vendor contact programs are ,

pursued, treat cases where such contact cannot practically be established, and establish responsibilities of licensees / applicants and vendors that provide service on safety-related components or equipment.

As previously indicated, the cases of Item t.2.2 are evaluated in a separate section in which the guideline is presented; an evaluation of the licensee's/ applicant's response is made; and conclusions about the programs of the licensee or applicant for their vendor interface program for safety-related components and equipment are drawn.

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3. ITEM 2.2.2 - PROGRAM DESCRIPTION 3.1 Guideline The licensee or applicant response should describe their program for

establishing and maintaining interfaces with vendors of safety-related components which ensures that vendors are contacted on a periodic basis and that receipt of vendor equipment technical information (ETI) is acknowledged or otherwise verified.

This program description should establish that such interfaces are established with their NSSS vendor, as well as with the vendors of key safety-related components such as diesel generators, electrical switchgear, auxiliary feedpumps, emergency core cooling system (ECCS) pumps, batteries, battery chargers, and valve operators, to facilitate the exchange of current technical information. The description should verify that controlled procedures exist for handling this vendor technical information which ensure that it is kept current and complete and that it is incorporated into plant operating, maintenance and test procedures as is appropriate.

3.2 Evaluation The licensee for the Clinton Power Station responded tc these requirements with submittals dated March 2, 19842 and October 1, 1984.3 These submittals include information that describe their past and current vendor interface programs. In the review of the licensee's response to this i item, it was assumed that the information and documentation supporting this program is available for audit upon request. We have reviewed this information and note the following.

The licensee states that they rely on General Electric (GE) customer services to obtain vendor information on the systems within the GE (the NSSS I

vendor) scope of supply. The disseminated information is in the form of 10 CFR 21 reporting, customer (urgent) communications (telephone with separate letter), Service Information Letters, Operation and Maintenance 3

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l Manuals, Service Advice Letters, Turbine Information Letters, Application l Information Documents, Field Disposition Instructions and Field Deviation

C!sposition Requests. This information is handled by the licensee in

cecordance with their existing departmental procedures and a Corporate 1

Nuclear Procedure that was, at the time of the submittal, being developed.

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r l The licensee has also inventoried the technical manuals for all j safety-related equipment and asked for verification by the vendor that their manual is current and is the most up to date edition. Additionally, they .

have encouraged these vendors to voluntarily provide updated information as it becomes available. This also provides a point of contact for vendor i information. Information provided by this program is processed in

! accordance with the same procedures used for NSSS supplied information.  !

I Additionally, the licensee states that they are a functional part of l

the INPO Nuclear Utility Task Action Committee (NUTAC) on the Vendor i

) Equipment Technical Information Program (VETIP). i i

l 3.3 Conclusion i

We conclude that the licensee's responsu regarding program description f is complete and, therefore, acceptable.  !

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4. PROGRAM WHERE VENDOR INTERFACE CANNOT l PRACTICABLY BE ESTABLISHED l 4.1 Guideline The licensee / applicant response should describe their program for compensating for the lack of a formal vendor interface where such an interface cannot be practicably established. This program may reference the NUTAC/VETIP program, as described in INPO 84-010, issued in l

March 1984. If the NUTAC/VETIP program is referenced, the response should l

describe how procedures were revised to properly control and implement this program and to incorporate the program enhancements described in Section 3.2 of the NUTAC/VETIP report. It should also be noted that the lack of either a formal interface with each vendor of safety-related equipment or a program to periodically contact each vendor of safety-related equipment will not relieve the licensee / applicant of his responsibility to obtain appropriate vendor instructions and information j where necessary to provide adequate confidence that a structure, system or component will perform satisfactorily in service and to ensure adequate quality assurance in accordance with Appendix B to 10 CFR Part 50.

4.2 Evaluation In Reference 3, the licensee provided a description of the vendor l

l interface program. Their description references the NUTAC/VETIP program.

l The licensee states that plant instructions and procedures are both I

currently in place and being oeveloped to assure that the VETIP program is properly controlled and implemented.

1 VETIP is comprised of two basic elements related to vendor equipment problems; the Nuclear Plant Reliability Data System (NPRDS) and the Significant Event Evaluation and Information Network (SEE-IN) programs.

VETIP is designed to ensure that vendor equipment problems are recognized, evaluated and corrective action taken.

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Through participation in the NRPDS program, the licensee submits engineering information, failure reports and operating histories for review under the SEE-IN program. Through the SEE-IN program, the Institute of Nuclear Power Operations (INPO) reviews nuclear plant events that have been reported through the NPRDS programs and Nuclear Network and NRC reports.

Based on the significance of the event, as determined by the screening review, INP0 issues a report to all utilities outlining the cause of the event, related problems and recommends practical corrective actions. These reports are issued in Significant Event Reports, and Significant Operating ,

Experience Reports and as Operations and Maintenance Reminders. Upon receipt of these documents, the licensee evaluates the information to determine applicability to the facility. This evaluation is documented and corrective actions are taken as determined necessary.

Additionally, the licensee will handle information provided by regulatory agencies in a similar manner.

The licensee's response states that procedures now exist and that an overall corporate procedure was being developed to review and evaluata incoming equipment technical information and to incorporate it into existing procedures.

4.3 Conclusion We find that the licensee's response to this concern is adequate and, therefore, acceptable.

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5. RESPONSIBILITIES OF LICENSEE / APPLICANT AND VENDOR THAT PROVIDE SERVICE ON SAFETY-RELATED EQUIPMENT 5.1 Guideline The licensee / applicant response should verify that the responsibilities of the licensee or applicant and vendors that provide service on safety-related equipment are defined such that control of applicable instructions for maintenance work on safety-related equipment are provided.

5.2 Evaluation The licensee, in Reference 3, cort..i+.ted to implement the NUTAC/VETIP program. They further state that their p esent and planned future practices and activities adequately implement this program. The VETIP program includes implementation procedures for the internal handling of vendor services.

5.3 Conclusion We find the licensee's commitment to implement and use the VETIP program acceptable.

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6. ' CONCLUSION Based on our review of the licensee's response to the specific I

) requirements of Item 2.2.2, we-find that the information provided by the licensee to resolve the concerns of this program meet the requirements of-Generic Letter 83-28 and is acceptable. .

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7. REFERENCES

1. Letter, NRC (D. G. Eisenhut), to all Licensees of Operating Reactors, Applicants for Operating License, and Holders of Construction Permits, 4

" Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8,1983.

2. Letter, Illinois Power Company (D. I. Herborn) to NRC (D. G. Eisenhut), " Schedule for Submittals in Response to NRC Generic Letter 83-28," March 2, 1984, U-0699.

. 3. Letter, Illinois Power Company (F. A. Spangenburg) to NRC (A. Schwencer), "NRC Generic Letter 83-28, Salem ATWS Events,"

October 1, 1984, U-0743.

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