ML18150A188

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Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components, North Anna Units 1 & 2 & Surry Units 1 & 2, Informal Rept
ML18150A188
Person / Time
Site: Surry, North Anna, 05000000
Issue date: 04/30/1987
From: Udy A
EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:
NRC
Shared Package
ML18150A187 List:
References
CON-FIN-D-6001 EGG-NTA-7612, GL-83-28, TAC-53693, TAC-53694, TAC-53721, TAC-53722, NUDOCS 8706260296
Download: ML18150A188 (16)
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.. *.. *~ e EGG-NTA-7612 April 1987 INFORMAL REPORT 1dah,Q NatiQnal CONFORMANCE TO GENERIC LETTER 83-28, ITEM 2.2.2--

, Eilgirieering: VENDOR INTERFACE PROGRAMS FOR ALL OTHER SAFETY-Laboratory>'

  • R~LATED COMPONENTS: NORTH ANNA-1 AND -2 AND SURRY-1 AND -2

.. Managed by the u.*s..

Department* .

Alan C. Udy of Energv

  • Prepared for the Work per{ormed*under.

No. DE-AC07-76/D01570 ..

U.S. NUCLEAR REGULATORY COMMISSION 8706260296 870501 PDR ADOCK 05000280

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e 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, make8 any warranty, express or implied, or assumes 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 infringe privately owned rights. 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 the;eof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

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  • EGG-NTA-7612 TECHNICAL EVALUATION REPORT CONFORMANCE TO GENERIC LETTER 83-28, ITEM 2.2.2--

VENDOR INTERFACE PROGRAMS FOR ALL OTHER SAFETY-RELATED COMPONENTS:

NORTH ANNA-1 and -2 SURRY-1 and -2 Docket Nos. 50-338/50-339/50-280/50-281 Alan C. Udy Published April 1987 Idaho National Engineering Laboratory EG&G 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. 06001

ABSTRACT This EG&G Idaho, Inc., report provides a review of the submittals from the Virginia Electric and Power Company regarding conformance to Generic letter 83-28, Item 2.2.2, for North Anna Units 1 and 2 and Surry Units 1 and 2.

Docket Nos. 50-338/50-339/50-280/50-281 TAC Nos. 53693/53694/53721/53722 ii

e FOREWORD This report is supplied as part of the program for evaluating licensee/applicant conformance to Generic Letter 83-28, 11 Required Actions Based on Generic Implications of Salem ATWS Events. 11 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. 20-19-10-11-3, FIN No. D6001.

Docket Nos. 50-338/50-339/50-280/50-281 TAC Nos. 53693/53694/53721/53722 i; i

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

1. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
2. REVIEW CONTENT AND FORMAT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
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 Gui de 1i ne ................................. : . . . . . . . . . . . . . . . . 5 4.2 Evaluation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
5. RESPONSIBILITIES OF LICENSEE/APPLICANT AND VENDORS THAT PROVIDE SERVICE ON SAFETY-RELATED EQUIPMENT.............................. 7 5.1 Guideline . . . . . . . . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 7 5.2 Evaluation . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . 7 5.3 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
6. CONCLUSION 8
7. REFERENCES 9 iv

CONFORMA~ TO GENERIC LETTER 83-28, ITEM.2.2--

VENDOR INTERFACE PROGRAMS FOR ALL OTHER SAFETY-RELATED COMPONENTS:

NORTH ANNA-1 AND -2 SURRY-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 Directo~ for Operations (EDD), 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, 11 Generic Implications of the ATWS Events at the Sa.lem Nuclear Power Plant. 11 As a result of this investigation, the Commission (NRC) requested (by Generic Letter 83-28 dated July 8, 1983 1) 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 Virginia Electric and Power Company, the licensee for North Anna and Surry, 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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e 2. REVIEW CONTENT AND FORMAT e

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 responsibil*ities 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 1 s/applicant 1 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 DESCRIPTI~

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 ch_argers, 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 North Anna and Surry responded to these requirements with submittals dated November 4, 1983, 2 February 8, 1985, 3 May 20, 1985, 4 August 30, 1985, 5 and November 18, 1985. 6 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 Technical Information Program (VETIP) was developed by NUTAC. VETIP includes interaction with the NSSS vendor and with other electric utilities. Typical 3

e e NSSS vendor contact with the licensee includes Westinghouse technical bulletins. This information, along with information provided by the vendors of other safety-related equipment is handled by the licensee in accordance with corporate and station procedures.

The licensee describes an inventory program of technical manuals for all safety-related equipment that seeks verification by the vendor that the licensee's manual copies are current and the most up-to-date editions. The licensee also describes how technical information obtained is integrated into plant operating and maintenance instructions and procedures.

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

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4. ~GRAM WHERE VENDOR INTERFACE CA~T 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 properly co.ntrol 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 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 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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e e 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 (INPO) reviews nuclear plant events that have been reported through the NPRDS programs, through Nuclear Network and by NRC reports. Based on the significance of the event, as determined by the screening review, INPO issues a summary report to all utilities outlining the cause of the event and related problems. This INPO report also recommends practical corrective actions. These reports are issued as Significant 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 response states that procedures 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 Section 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. RESPONS"'ILITIES OF LICENSEE/APPLICANT~ 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.

The licensee states that administration controls and procedures assure the proper documentation and qualification of vendor-supplied services.

Engineering and Quality Assurance reviews assure the control of applicable instructions for maintenance work on safety-related equipment.

5.3 Conclusion

. We find that the information contained in the licensee's submittals is sufficient for us to conclude that the licensee's and vendor's responsibilities are defined and controlled appropriately. Therefore, the information provided by the licensee for this item is acceptable.

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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 North Anna-1/-2 and Surry-1/-2, we find that the licensee's interface program with its NSSS supplier, along with the licensee's commitment to implement the NUTAC/VETIP program, is acceptable.

This is based on the understanding that the licensee's commitment to implement the NUTAC/VETIP program includes the objective for 11 Internal Handling of Vendor Services 11 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.

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e 7. REFERENCES e

1. Letter, NRC (D. G. Eisenhut), to all Lic~nsees of Operating Reactors~

Applicants for Operating License, and Holders of Construction Permits, 11 Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28), 11 July 8, 1983.

2. Letter, Virginia Electric and Power Company (W. L. Stewart) to NRC (H. R. Denton and D. G. Eisenhut), 11 Response to Generic Letter 83-28, 11 November 4, 1983, Serial No. 617.
3. Letter, Virginia Electric and Priwer Company (W. L. Stewart) to NRC (H. R. Denton and D-. G. Eisenhut), 11 Revision to Generic Letter 83-28, 11 February 8, 1985, Serial No.85-063.
4. Letter, Virginia Power (W. L. Stewart) to NRC (H. R. Denton and H. L. Thompson, Jr.), "Response to Generic Letter 83-28, Request for Additional Information, Items 2.1.3, 2.2.2, 4.5.2, 11 May 20, 1985, Serial 85-211 (Surry).
5. Letter, Virginia Electric and Power Com~any (W. L. Stewart) to NRC (H. R. Denton and H. L. Thompson, Jr.), "Submittal for Additional Information to Generic Letter 83-28, Item 2.2,U August 30, 1985, Serial No. 85-0638.
6. Letter, Virginia Electric and Power (W. L. Stewart) to NRC (H. R. Denton and E. J. Butcher), 11 Response to Generic Letter 83-28, Items 2.1, 2.2, 3.1.3, 3.2.3, 4.4 and 4.5, Request for Additional Information," November 18, 1985, Serial No.85-695 (North Anna).
7. Vendor Equipment Technical Information Program, Nuclear Utility Task Action Committee on Generic Letter 83-28, Section 2.2.2, March 1984, INPO 84-010.

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NRC fORM 335 U.S. NUCL!AII IIEOULATOIIY COMMIIIIION 1. REPORT NUMBER (Auign~by*T/DC, *dd Vol. No., il*nrl (2-841 ,

NRCM 1102, 3201, 3202 BIBLIOGRAPHIC DATA SHEET EGG-NTA-7612 SEE INSTRUCTIONS ON THE REVERSE

2. TITLE AND ~UBTITLE J. LEAVE IILANI(

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

VENDOR INTERFACE PROGRAMS FOR ALL OTHER SAFETY-RELATED COMPONENTS: NORTH ANNA-1 AND -2 AND SURRY-1 4, DATE REPORT COMPLETED AND -2 MONTH YEAR

5. AUTHOR(SI April 1987 Alan C. Udy 6. DATE REPORT ISSUED MONTH April I YEAR 1987
7. PERFORMING ORGANIZATION NAME AND MAIL.ING ADDRESS (lnclutNZ,p c_, 8. PROJECT/TASK/WORK UNIT NUMBER EG&G Idaho, Inc.

P. 0. Box 1625 9. FIN OR GRANT NUMBER IdahoFalls, ID 83415 D6001

10. SPONSORING ORGANIZATION NAME AND MAIL.ING ADDRESS (lnclutNZip CotUI 1 h. TYPE OF REPORT Division of PWR Licensing - A Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission b. PERIOD COVERED /lnclu1i** tarn/

Washington, DC 20555

12. SUPPLEMENTARY NOTES 1J. ABSTRACT (200 word, or !1111 This EG&G Idaho, Inc., report provides a review of the submittals from the Virginia Electric and Power Company regarding conformance to Generic Letter 83-28, Item 2.2.2, for North Anna-1 and -2 and Surry-1 and -2.

14 DOCUMENT ANALYSIS

  • KEYWORDS/DESCRIPTORS 15. AVAILABILITY STATEMENT Unlimited Distribution
16. SECURITY CLASSIFICATION (Thi*-*I
b. IDENTIFIERS/OPEN-ENDED TERMS Unclassified (Thi* reporrl Unclassified
17. NUMBER OF PAGES
18. PRICE
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