ML20235M630

Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Three Mile Island-1, Informal Rept

ML20235M630
Person / Time
Site:	Three Mile Island
Issue date:	06/30/1987
From:	Udy A EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:	NRC
Shared Package
ML20235M604	List: ML20235M602 ML20235M630
References
CON-FIN-D-6001 EGG-NTA-7662, GL-83-28, TAC-53724, NUDOCS 8707170261
Download: ML20235M630 (16)

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EGG-NTA-7662 l June 1987

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

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VENDOR INTERFACE PROGRAMS FOR ALL OTHER SAFETY-Engineering 7 :p RELATED COMPONENTS: THREE MILE ISLAND-1 Laboratory; ' , _.

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CISCLAIMER This book was prepared as an account of work sponsored by an egency of tne United States Govemment. NeithE the United States Government nor any agency thereof, not any of their employee 3, makes any warranty, express or implied, or assumes any legal liebility or responsibility for the accuracy, completeness, er usefulness of any I information, apparatas, product or process disclosed, or represents that its use would not ininnge piv3tely owiied nghts. References herein to any 2,pecific commercial product, process, or service by trade r ame, trademark, manufacturer, or ctherwise, does not riecessanly constitute or imply its endorsement. recommendation, or favonng by the United States Government or any agency thereof. The views aid opinions of echors exprescad hereir) do not necessanly state or reflect those of the United States GovGrnment or any agency thefsof.

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EGG-NTA-7662 TECHNICAL EVALUATION REPORT CONFORMANCE TO GENERIC LETTER 83-28, ITEM 2.2.2--  :

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

THREE MILE ISLAND-1 l Docket No. 50-289 i Alan C. Udy v

Published June 1987 Idaho National Engineering Laboratory EG&G Idaho, Inc.  !

Idaho Falls, Idaho 83415  !

M Frepared for the U.S. Nuclear Regu'latory Commission

l. Washington, D.C. 20555 l Under DOE Contract No. DE-AC07-761D01570 FIN No. 06001 l

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n ABSTRACT This EG&G Idaho, Inc., report provides a review of the submittals from the GPU Nuclear Corporation regarding conformance to Generic Letter 83-28, Item 2.2.2, for Unit 1 of the Three Mile Island Nuclear Station.

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Docket No. 50-289 TAC No. 53724 ii

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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 Engineering and System Technology, 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. 20-19-10-11-3, FIN No. D6001.

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Docket No. 50-289 'I TAC No. 53724 I iii i

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J CONTENTS' 1

- ABSTRACT .............................................................. 11 i

. FOREWORD ...........................................................'... iii

1. - I NT R O DU C T I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 1 j

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2. REVIEW CONTENT AND' FORMAT ........................................: 2' '

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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 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 'j 1

5.1 Guideline .................................................. ~7 5.2 E v a l u a t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 5.3 Conclusion ............................................'..... -7 1

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

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

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CONFORMANCE'TO GENERIC LETTER 83-28, ITEM .2~2.2--  ;

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

THREE MILE ISLAND-1 1

1. INTRODUCTION On February 25, 1983, both of the scram circuit breakers at Unit 1 of the Salem Nuclear Pcwer Plant failed to open upon an automatic recctor 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 f ailure of the circuit breakers was determined to be related to the sticking of the undervoltage trip attachment. Frior.

to this incident, on February 22, 1983, at Unit 1 of the Salem Nuclear .l Power Plant, an automatic trip signal was generated based on steam generator low-low level during plant startup.. In this. case, the reactor i was tripoed manually by the operator almost coincidentally with the automatic trip.

i Following these incidents, on February 28 $1983, the NRC Executive Director for Operations (EDO),. directed the'NRC' staff to investigate and j 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 I NUREG-1000, " Generic Implications of the ATWS Events at the Salem Nuclear Power Plant." - As a result of this investigation, the Commission (NRC) requested (by Generic Letter 83-28 dated July 8, 1983 I ) all licensees of operating reactWs, 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 GPU Nuclear Corporation, the licensee for the Three Mile Island Nuclear Station, 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, i

'2. REVIEW CONTENT AND FUtMAT-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 i

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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 j licensee's/ applicant's response is made; and conclusions about the programs I of the licensee or applicant for their vendor interf ace program for.

1 safety-related components and equipment are drawn. l 1

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3. ITEM 2.2.2 --PROGRAM 0ESCRIPTION 3.1 Guideline The licensee or applicant response should describe.their program for o 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. )

k 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, j auxiliary feedpumps, emergency core cooling system (ECCS). pumps, batteries, j battery chargers, and valve operators, to f acilitate 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 Unit No. 1 of the Three Mile Island Nuclear Station responded to these requirements with submittals dated November 8,.1983,2

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August 5, 19853 and October 4, 1985.4 These submittals include information that describes their past and current vendor interf ace 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 the information submitted and note the following.  !

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The licensee's response states that they actively participate in the Nuclear Utility Task Action Committee (NUTAC) program. The Vendor Equipment  :

Technical Information Program (VETIP) was developed by NUTAC. VETIP includes interaction with the NSSS vendor and with other electric utilities. The ,

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' licensee states that new or revised procedures to implement the NUTAC/VETIP

' program include the following: EP-021, " Technical Manuals,".EP-003, " Vendor Document Review," EP-017, " Review of Operating Experience," and. j 5000-ADM-7316.02, 5000-ADM-7370.92 and 5000-ADM-7316.03. These I administrative controls and procedures require the review of safety-related equipment technical information to verify that it is referenced by and -

incorporated into plant procedures and instructions.

l The licensee states that they have established-interfaces with the NSSS supplier (B&W) and with vendors of oth'er major safety-related equipment.

Vendors in this information gathering process include those vendors that are still in business and provide manual updates. The licensee indicates that this is a one time process, with the exception of the NSSS supplier, and with those vendors that- have active service feedback and product' development ]

programs. In these cases, a continuing contact is made.

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3.3 Conclusion We conclude that the licensee's response regarding program description is complete and, therefore, acceptable.

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4. PROGRAM WHERE VENDOR INTERFACE CANNOT l PRACTICABLY BE ESTABLISHED l ,

l 4.1 Guideline

. The licensee / applicant response should describe their program for compensating for the lack of a formal vendor interf ace where such an interf ace cannot be practicably established. This program may reference the NUTAC/VETIP program, as described in INP0 84-010, issued in March 1984. If the NUTAC/VETIP program is referenced, the response should j describe how procedures were revised to properly control and implement this program and to incorporate the program enhancements described in j Section 3.2 of the NUTAC/VETIP report. The use of the NUTAC/VETIP program, instead of either a formal interface with each vendor of safety-related I

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 interf ace program. Their description references the NUTAC/VETIP program. The licensee states that plant instructions and procedures are in place to j 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 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 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 (INP0) reviews r,celear plant events that have been l reported through the NPRDS programs, 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, in Significant Operating Experience Reports and as Operations and Maintenance Reminders. Upon i receipt of these documents, the licensee, as part of his implementation of j the NUTAC/VETIP program, evaluates the information to determine 4 applicability to the f acility. This evaluation is then documented and '

corrective actions taken as determined necessary.

The licensee's response states that procedures have been reviewed, and revised as necessary, for the review and evaluation of incoming equipment l technical information and for incorporating 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 H commitment to implement the VETIP program includes the implementation of the enhancements described in Secticn 3.2 of the NUTAC/VETIP program to the extent that the licensee can control or influence the implementation of d 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 adequately implement this program. The VETIP guidelines include implementation procedures for the internal handling of vendor services.

5.3 Conclusion We. find the licensee's commitment to implement the VETIP i recommendations acceptable, with the understanding that the licensee's commitment includes the objective for " Internal Handling of Vendor- 1 Services" described on page 23 of the March 1984 NUTAC report.

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6. CONCLUSION

l. Based on our~ review of the licensee's response to the specific requirements of item 2.2.2 for Threel Mile, Island-1, we find that the q licensee's interface program with its NSSS' supplier, along with the  !

licensee's commitment.to implement the NUTAC/VETIP program, is acceptable'. ..

This.js based on the understanding that the. licensee's commitment to implement the NUTAC/VETIP program' includes the objective for'" Internal =

l Handling of Vendor Services" described .on page 23 of the March.1984 report and includes the enhancements described in Section 3.2 of th~e report to the extent that the licensee can control or influence such enhancements.  ;

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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,

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

2. Letter, GPU Nuclear Corporation (H. D. Hukill) to NRC (O. G. Eisenhut), " Required Actions Based on Generic Implications of Salem /ATWS Events," November 8, 1983, 5211-83-330.

3. Letter, GPU Nuclear (R. F. Wilson) to NRC (J. F. Stolz), "Respense to Request for Additional Information-Generic Letter 83-28,"

August 5, 1985, 5211-85-2132, RFW-0570.

4. Letter, GPU Nuclear (R. G. Wilson) to NRC (J. F. Stolz), " Generic Letter 83-28, Vendor Interface," October 4, 1985, 5211-85-2160, RFW-0633.

5. 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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P. 0.. Box 1625 e < =oaoa.=v=vmeen Idaho Falls, ID 83415 D6001

... i,0 so...o oao... r.o= ... .~o omi.o .oona u ,, 7. ,, c , ii. rv,. o, aeroar Division of Engineering and System Technology Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission . ,eaico coveneo ,,,,,.s. ..,

Washington, DC 20555 17 SUPPLEMENT Aav NOf t5 1J ASSTa ACT ,100 e.r.s r aess, This EG8G Idaho, Inc., report provides a review of the submittals from the-GPU Nuclear Corporation regarding conformance to Generic Letter 83-28, Item 2.2.2, for Three Mile Island-1.

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