ML20235M465
| ML20235M465 | |
| Person / Time | |
|---|---|
| Site: | Satsop, Washington Public Power Supply System |
| Issue date: | 06/30/1987 |
| From: | Udy A EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY |
| To: | NRC |
| Shared Package | |
| ML20235M443 | List: |
| References | |
| CON-FIN-D-6002 EGG-NTA-7673, GL-83-28, NUDOCS 8707170206 | |
| Download: ML20235M465 (16) | |
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- EGG-NTA-7673 June 1987 INFORMAL REPORT
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1 l CONFORMANCE TO GENERIC LETTER 83-28, ITEM 2.2.2--
o- ,N$ilona/J VEND 0R INTERFACE PROGRAMS FOR ALL OTHER SAFETY-Engineering . 'w RELATED COMPONENTS: WNP-1/-3 Laboratory,;. + 1 Managed'. '
. by the U. S. ' Alan C. Udy Department.-
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U nm EGr5,a.n. Prepared v.or the wo,, ,,fo,m a - o, U.S. NUCLEAR REGULATORY COMMISSION DOE Contract :
_ No. DE-AC07-MID01570 B70717020b B7 b2D PDR ADOCK 05000460 A ppg e
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'l l I DISCLAIMER l
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 assumes any legal hability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product or process d:sclosed, of represents that its use would i not infringe pnvately owned r'ghts. heferences herein to any specific commercial ,
J 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 expres. Sed herein do not necessanly state or reflect those nf the United States l
l Government or any agency thereof.
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i EGG-NTA-7673 k 4 1
TECHNICAL EVALUATION REPORT l CONFORMANCE TO GENERIC LETTER'83-28, ITEM 2.2.2--
VENDOR INTERFACE PROGRAMS FOR ALL OTHER SAFETY-RELATED COMPONENTS:
WNP-1/-3 ,
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Docket Nos. 50-460/50-508 I
Alan C. Udy Published June 1987 l
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Idaho National Engineering Laboratory EG&G Idaho, Inc.
- Idaho Falls, Idaho 83415 l 1 Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Under DOE Contract No. DE-AC07-76ID01570 FIN No. D6002 L-__----------------_----_--------------_-----_---------__
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l ABSTRACT This EG&G Idaho, Inc., report provides a review of the submittals from the Washington Public Power Supply System regarding conformance to Generic Letter 83-28, Item 2.2.2, for Nuclear Projects 1 and 3.
l Docket Nos. 50-460/50-508 ii
i 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. 20-19-40-41-3, FIN No. D6002.
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. Docket Nos. 50-460/50-508 iii l
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CONTENTS
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1 ABSTRACT .................. .......................................... 11 FOREWORD .............................................................. iii
- 1. INTRODUCTION ..................................................... 1
- 2. REVIEW CONTENT AND FORMAT ........................................ 2 3
- 3. ITEM 2.2.2 - PROGRAM DESCRIPTION ................................. 3 3.1 Guideline .................................................. 3 3.2 Evaluation ................................................. 3 ,
3.3 Conclusion ... ........................................ .... 4' l
- 4. PROGRAM WHERE VENDOR INTERFACE CANNOT PRACTICABLY BE l ESTABLISHED ...................................................... 5 !
4.1 Guideline .................................................. 5 i 4.2 Evaluation ................................................. 5 4.3 Conclusion ........................... ..................... 6
- 5. RESPONSIBILITIES OF LICENSEE /APPLICANY AND VENDORS THAT PROVIDE SERVICE ON SAFETY-RELATED EQUIPMENT .............................. '7 j
- 5.1 Guideline .................................................. 7 3 5.2 Evaluation ................................................. 7 l 5.3 Conclusion ......... ....................................... 7 l
l 6. CONCLUSION .... .................................................. 8
- 7. REFERENCES .............. .. .............. ............ ......... 9 1
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I CONFORMANCE TO GENERIC LETTER 83-28, ITEM 2.2.2-- i l VENDOR INTERFACE PROGRAMS FOR ALL OTHER SAFETY-RELATED COMPONENTS:
l WNP-1/-3 l \
- 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 j manually by the operator about 30 seconds after the initiation of the l
automatic trip signal. The failure of the circuit breakers was determined I 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 l 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 I 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) I 1
requested (by Generic Letter 83-28 dated July 8, 1983 ) all licensees of j 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 Washington Public Power Supply System, the applicant for Nuclear Projects 1 and 3 (WNP-1 and -3), 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. 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 l
guideline section for each case within this report. ,
I 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 ecuipment.
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. ITEM 2.2.2 - PROGRAM DESCRIPTION 3.1 Guideline ,
J 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 l that receipt of vendor equipment technical information (ETI) is acknowledged or otherwise verified. j 1
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, I 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
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operating, maintenance and test procedures as is appropriate. )
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3.2 Evaluation 1
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The applicant for WNP-1 provided a limited response to these j requirements with a submittal dated March 30, 1984.2 Due to the suspension of construction for WNP-3, no response was made.
The applicant's response for WNP-1 states that they have participated in the Nuclear Utility Task Action Committee (NUTAC) program. The Vendor ,
Equipment Technical Information Program (VETIP) was developed by NUTAC. . l VETIP includes interaction with the NSSS vendor and with other electric
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. They also state that they have a contractor / vendor information file I system to assure that equipment technical information is available throughout the life of the unit. For both units 1 and 3, the applicant ha", suspended 3
construction'. They state that they will review the NUTAC report (Unit 1) 3 years prior to fuel. load. For Unit 3 they state that they will respond l
with a schedule for answering 2.2.2 prior to the restart of construction. i i
3.3 Conclusion )
i It is evident-tnat the concerns of Item 2.2.2 of Generic Letter 83-28 -
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will be resolved on an industry wide basis prior to the completion and j licensing of either WNP-1.or WNP-3. The concerns of Item 2.2.2 for these -
units will be resolved during the review and approval process of their Safety 0 I
Analysis Report and technical specifications. Therefore, we consider this '
item to be closed for WNP-1 and WNP-3. l l
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- 4. PROGRAM WHERE VENDOR INTERFACE CANNOT PRACTICABLY BE ESTABLISHED 4.1 Guidelig 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
+he NUTAC/VETIP program, as described in INP0 84-010, issued in March 1984. If the NUTAC/VETIP program is referenced, the response should describe how procedures were revised to properly control and implement this l program and to incorporate the program enhancements described in l
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 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 Eva' uati on VETIP is comprised of two basic el'ements related to vendor equipment problems; the Nuclear Plant Reliability Data System (NPRDS) and the Significant Event Evaluation and Information Network (SEE-IN) programs. 1 i
VETIP is designed to ensure that vendor equipment problems are recognized, j evaluated and corrective action taken. j l
1 Through participation in the NPRDS program, a licensee submits l engineering information, failure reports ansi 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 NPRDS programs, Nuclear Network and NRC reports. Based on q
the significance of the event, as determined by the screening review, INPO 5
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issues a report to all utilities outlining the cause of the event, related problems and provides recommendations for practical corrective actions.
These reports are issued as Significant Event Reports, Significant Operating Experience Reports and Operations and Maintenance Reminders.
Upon receipt of these documents, a licensee evaluates the information to determine applicability to the facility. This evaluation is documented and corrective actions are taken as determined necessary. The means by which this documentation and tracking will be done shall be described in the FSAR upon resumption of the licensing effort.
4.3 Conclusion As the applicant's response to this concern is yet to be made, we point out that a commitment to incorporate the VETIP recommendations, including the enhancements descrioed in Section 3.2 of the NUTAC/VETIP program to the extent that the applicant can control or influence the implementation of these recommendations, would acceptably satisfy this j concern of Item 2.2.2.
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- 5. RESPONSIBILITIES OF LICENSEE / APPLICANT AND VENDOR THAT PROVIDE SERVICE ON SAFETY-RELATED EQUIPMENT 5.1 Guideline l . 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 We could find no information from the applicant that add,resses the control of vendor-supplied services for maintenance work on safety-related equipment. The applicant has not stated that they have specific procedures to provide the proper quality assurance control over vendor-supplied service on safety-related equipment.
5.3 Conclusion As the applicant's response to this concern is yet to be made, we point out that a commitment to incorporate the VETIP recommendations, including the objective for the " Internal Handling of Vendor Services" described on page 23 of the March 1984 NUTAC report, would acceptably satisfy this concern of Item 2.2.2.
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- 6. CONCLUSION It is evident that the concerns of Item 2.E.2 of Generic Letter 83-28 will be resolved on an industry wide basis prior to the completion and licensing of either WNP-1 or WNP-3. The concerns of Item 2.2.2 for these units will be resolved during the review and approval process of their ,
Final Safety Analysis Report and technical specifications. Therefore, we consider this item to be closed for WNP-1 and WNF-3. .
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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 3 (Generic Letter 83-28)," July 8, 1983.
- 2. Letter, Washington Public Power Supply System (G. C. Sorensen) to NRC !
- (E. G. Adensam), " Nuclear Project No. I Response to Generic j Letter 83-28 Salem ATWS Events," March 30, 1984, G01-84-0094. l
- 3. Vendor Eauipment Technical Information Procram, Nuclear Utility Task Action Committee on Generic Letter 83-28, Section 2.2.2, March 1984, INP0 84-010. l j
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- i AvT-O isi June 1987 l Alan C. Udy e o ATs ae*0af issvio MO T. YiAa j
June 1987 7 e(RFORMiNG ORGANIZ ATION NAME AND MAlg;NQ AQQht$$ (#ngilemJe Coms 3 PROJECTIT ASE/womK UNIT hvMgER EG&G Idaho, Inc.
. *iN Oa Ga A..T NuM. a P. O. Box 1625 Idho Falls, ID 83415 D6002 o $PON50HiNG OHGANi2ATiON NAME AND MAsLING ADORES $ timumJe Cases 1is TYPE OP ptPORT l Division of Engineering and System Technology ;
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission n eeaiOo Coviano u-m-e Wathington, DC 20555 12 SUPP(EMENT ARV NOT65 tJ ASSTR ACT (JW avese or seas This EG&G Idaho, Inc., report provides a review of the submittals from the Washington Public Power Supply System regarding conformance to Generic Letter 83-28, Item 2.2.2, for WNP-1 and -3.
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