ML20216C230

Final Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Nine Mile Point,Units 1 & 2, Informal Rept

ML20216C230
Person / Time
Site:	Nine Mile Point
Issue date:	04/30/1987
From:	Udy A EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:	NRC
Shared Package
ML20216B869	List: ML20216B865 ML20216C230
References
CON-FIN-D-6001, CON-FIN-D-6002 EGG-NTA-7611, GL-83-28, NUDOCS 8706300240
Download: ML20216C230 (15)

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l DISCLAIMER This book was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assune any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infnnge pnvately owned nghts. References herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof, I

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EGG-NTA-7611 r...

TECHNICAL EVALUATION REPORT

.a; CONFORMANCE TO GENERIC LETTER 83-28' ITEM 2.2.2- :

VENDOR INTERFACE PROGRAMS FOR ALL OTHER SAFETY-RELATED COMPONENTS:

NINE MILE' POINT-1.AND ' Docket Nos. 50-220/50-410 Alan C. Udy Published April 1987 Idaho National Engineering Laboratory

,~ EG&G Idaho, Inc.

Idaho Falls, Idaho 83415 4

i Prepared for the U.S. Nuclear Regulatory Commission-Washington, D.C. 20555' Under DOE Contract No. DE-AC07-76ID01570 FIN Nos. 06001 & D6002 L

ABSTRACT This EG&G Idaho, Inc., report provides a review of the submittals from the Niagara Mohawk Power Corporation regarding conformance to Generic ,

Letter 83-28, Item 2.2.2, for Nine Mile Point, Unit Nos. I and 2.

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Docket Nos. 50-220/50-410

. TAC No. 53692 ii

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-- FOREWORD This report is supplied as par't o'f the program for evaluating licensee / applicant conformance' to Generic Letter 83-28, " Required Actions l 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 Nos. 20-19-10-11-3 and 20-19-40-41-3, FIN Nos. 06001 and 06002.

Docket Nos. 50-220/50-410

. TAC No. 53692 iii

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CONTENTS l-i IABSTRACT ,............................................................. ii FOREWORD ~............................................................... iii

, 1.. ' INTRODUCTION ..................................................... 1 l

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~2. REVIEW CONTENT AND~ FORMAT ........................................ 2 1

3. ITEM 2.2.2 - PROGRAM DESCRIPTION ................................. 3 3.1 Guideline .................................................. 3 3.2 ~ Evaluation ............. ................................... 3 3.3 Conclusion .................................................. .4

4. PROGRAM.WHERE VENDOR INTERFACE CANNOT. PRACTICABLY BE ESTABLISHED ...................................................... 5

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4.1 Guideline ,................................................. 5 4.2- Evaluation ................................................. 5

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

5. RESPONSIBILITIES OF LICENSEE / APPLICANT AND VENDORS THAT PROVIDE  !

SERVICE ON SAFETY-RELATED EQUIPMENT .............................. 7 I

5.1 Guideline .................................................. 7 5.2 Evaluation ... . . ......................................... 7 5.3: . Conclusion ................................................. 7

6. CONCLUSION ....................................................... 8

7. REFERENCES ....................................................... 9 1

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

VENDOR INTERFACE PROGRAMS FOR ALL OTHER SAFETY-RELATED COMPONENTS:

NINE MILE POINT-1 AND -2

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.

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 this incident, on February 22, 1983, at Unit 1 of the Salem Nuclear-Power Plant, an automatic. trip signal was generated based on steam generator 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 for Operations (EDO), directed the NRC 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 incidents are reported in NUREG-1000, " Generic' Implications of the ATWS Events at the Salem Nuclear Power Plant." As a result of this investigation, the Commission (NRC) 1 requested (by Generic Letter 83-28' dated July 8,1983 ) all licensees of operating reactors, applicants for an operating license, and holders of construction permits to respond to the generic-issues raised by the analyses of these two ATWS. events.

This report is an evaluation of the responses submitted by the Niagara Mohawk Power Corporation, the licensee for Nine Mile Point, for 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. REVIEU COMTENT AND FORMAT l

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. -

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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 2.2.2 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.  ! TEM 2.2.2 - PROGRAM DESCRIPT10N--

o 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-

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'that receipt of-vendor equipment technical information (ETI) is acknowledged'- '

.- or otherwise verified.

This program description sh'ould 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 incorpor'ated into plant operating, maintenance and test procedures as is appropriate.

3.2~ Evaluation

-The licensee for Nine Mile Point responded to these requirements with submittals dated November 8, 1983,2 February 29, 1984,3 April 10, 1984,4 April l30,1984,5 September 4, 1984,6 December 20,_.1985,7 April' 15', 19868 and January 22, 1987.9 These submittals include

-information that describes their past and current vendor interface programs. In the review of the licensee's response to this 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's response states that they actively participate in the Nuclear Utility Task Action Committee (NUTAC) program. The Vendor Equipment I Technical Information Program (VETIP) was developed by NUTAC. VETIP- j includes interaction with the NSSS vendor and with other electric 1

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1 utilities. ' Typical NSSS vendor (General Electric) contact with the licensee includes the Service Information Letter program, service advice letters and technical information letters. Assistance from the equipment vendors is sought when needed. The licensee also states that procedures to implement the NUTAC/VETIP program are in-place.

One of the VETIP. implementation responsibilities 1s to seek assistance -

and equipment technical information from the vendors of safety-related equipment'(other than the NSSS vendor) when the licensee's evaluation of an equipment problem or an equipment technical information problem concludes that such interaction is necessary or would be beneficial. The licensee states that they comply with this NUTAC implementation requirement.

However, Section 2.2.2 of the generic letter states that formal vendor )

interfaces should be established with vendors besides the NSSS vendor. The licensee has not indicated that any formal interface program has been established with vendors other than the NSSS vendor.

3.3 Conclusion We conclude that, with the exception of interactio'n with the vendors of other safety-related equipment, the licensee's response regarding program description is coinplete and, therefore, acceptable. The licensee should establish a program to periodically contact vendors of key components (such i as auxiliary feedwater pumps, safety-related batteries, ECCS pumps and I safety-related valve operators) to facilitate the exchange of current  !

technical information. In the case of the diesel generator and safety-related electrical switchgear vendors, the licensee should establish  ;

a formal interface similar to that with the NSSS vendor, if practicable. l l

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4. PROGRAM WHERE VENDOR INTERFACE CANNOT PRACTICABLY BE ESTABLISHED 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 March 1984. If the NUTAC/VETIP program is referenced, the response should describe how procedures were revised to proper'ly control and implement this program and to incorporate the program enhancements described in f 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 -

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 The licensee provided a brief description of the vendor interface program. Their description references the NUTAC/VETIP program. The licensee states that plant instructions and procedures are currently in place to assure that the VETIP program is properly controlled and implemented.

VETIP is comprised of two basic elements related to vendor equipment problems; the Nuclear Plant Reliability Data System (NPRDS) and the 3

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 NPRDS program, the licensee submits t engineering information, failure reports and operating histories for review l under the SEE-IN program. Through the SEE-IN program, the Institute of Nuclear Power'0perations (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, INPO issues a report to all utilities outlining the cause of the .

I event, describing related problems and providing recommendations for practical corrective actions. These reports are issued as Significant - - i Event Reports, as 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.

The licensee's respo'n'se states that procedures now exist to review and evaluate 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 acceptable. This' finding is based on the understanding that the licensee's commitment to implement the VETIP program includes the implementation of the enhancements described in Secti,n 3.2 of the NUTAC/VETIP program to the extent that the licensee can control or influence the implementation of these recommendations.

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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's response commits to implement the NUTAC/VETIP program.

They further' state that their present and revised programs and procedures -

I adequately implement this program. The VETIP guidelines include

' implementation procedures for the internal handling of vendor services.

4 5.3 Conclusion We find the licensee's' commitment to implement the VETIP recommendations acceptable, with the understanding that the licensee's commitment includes the objective for " Internal Handling of Vendor Services" described on page 23 of the March 1984'NUTAC report.

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6. ' CONCLUSION Based on'our review of the licensee's response to the specific requirements of item 2.2.2 for Nine Mile Point-1 and -2, we find that the licensee's. interface program with its NSSS supplier, its internal handling of. vendor-supplied services, along with the licensee's commitment to l

implement the NUTAC/VETIP program, is acceptable. This is based on the

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understanding that the licensee's commitment to implement the NUTAC/VETIP ,

program includes the objective for " Internal Handling of Vendor Services" described on Page 23 of the March 1984 report and includes the enhancements described in Section 3.2 of the report-to the extent that the licensee can  ;

control or influence such enhancements. ]

In addition, the licensee should establish a program to periodically ,

4 contact vendors of key components (such as auxiliary feedwater pumps, l l

safety-related batteries, ECCS pumps and safety-related valve operators) to facilitate the exchange of current technical information. In the case of the diesel generator and safety-related switchgear vendors, a formal  !

interface, such as that established with the NSSS vendor, should be established, if practicable.

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7. REFERENCES

1. ' Letter, NRC (D. G. Eisenhut), to all Licensees of.0perating. 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. Letter, Niagara Mohawk Power Corporation (T. E. Lempges) to NRC (D. B. Vassallo), November 8, 1983 (Unit 1).

3. Letter, Niagara Mohawk Power Corporation (C. V. Mangan) to NRC (D. B. Vassallo), February 29, 1984 (Unit 1).

4. Letter,. Niagara Mohawk Power Corporation (G. K. Rhode) to NRC (A. Schwencer),: April 10, 1984, NMP2L 0029.

5. Letter, Niagara Mohawk Power Corporation (C. V. Mangan) to NRC (D. B. Vassallo), April 30, 1984 (Unit 1).

6. Letter, Niagara Mohawk

Power Corporation (C. V. Mangan) to NRC (D. B Vassallo), September 4, 1984 (Unit 1).

7. Letter, Niagara Mohawk Power Corporation (T. E. Lempges) to NRC (E. G. Adensam), ' December 20,1985, NMP2L - 0566.

8. Letter, Niagara Mohawk Power Corporation (T. E. Lempges) to NRC (E. G. Adensam), April 15, 1986, NMP2L 0687.

9. Letter, Niagara Mohawk Power Corporation (C. V. Mangan) to NRC, January 22, 1987, MMPIL 0128.

10. Vendor Equipment Technical Information Program, Nuclear Utility Task Action Committee on Generic Letter 83-28, Section 2.2.2, March 1984, INP0 84-010.

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

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.RELATED COMPONENTS: NINE MILE POINT-1 AND -2 "*'* aoa ' co**'a t s o

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1J A8S Ta ACT 1200 w.r e .* 'eoob This EG&G Idaho, Inc., report provides a review of the submittals from the j Niagara Mohawk Power Corporation regarding conformance to Generic Letter 83-28, )

Item 2.2.2, for Nine Mile Point-1 and -2. I I

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