ML20215L882

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

ML20215L882
Person / Time
Site:	Brunswick
Issue date:	05/31/1987
From:	Udy A EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:	NRC
Shared Package
ML20215L847	List: ML20215L844 ML20215L882
References
CON-FIN-D-6001 EGG-NTA-7552, GL-83-28, NUDOCS 8706260203
Download: ML20215L882 (16)

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a DISCLAIMER This book was prepared as an account of work sponsored by an agency of the United States Govemment; NJither 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 disclosed, or represents that its use would not infringe pnvately owned nghts. References herein to any specific commercial

- 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 United States -

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, , . TECHNICAL EVALUATION REPORT CONFORMANCE:TO GENERIC LETTER 83-28, ITEM 2.2'.2- .

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-;c VENDOR ~ INTERFACE PROGRAMS FOR ALL-0THER SAFETY-RELATED. COMPONENTS:

BRUNSWICK-1 AND.-2

. Docket Nos. 50-325/50-324'

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~ Alan C, Udy- o Published May 1987 q

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. ABSTRACT "

~ This EG&G. Idaho, Inc.,.reportLprovides'a' review of the.submittals from'.

H .te' h l Carolina Power &' Light. Company.'for;the Brunswick Steam Electric' Pla'nt

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Docket Nos. 50-326/50-324

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FOREWORD 1ThisL: report:is csupplied' as; part of' the program ~ for; evaluating:

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' ' ' licensee / applicant conformance:to Generic ~ Letter 83-28,."R"equired Actions 3

BasedonGenericImplicationsofLSalemATWSEvents."[Thiswohkiis'bsing <

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conducted for the U.S. Nuclear Regulatory Commission, Officefor Nuclear 1 fp  : Reactor; Regulation,-Division-of-PWR Licensing-A,'by:EG&GgIdaho,_Inc.,.NRR:

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'The U.S! Nucisar Regulatory Commission funded this work under the-I

-authorization.B&R..No.-_20-19-10-11-3, FIN No. 06001.

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@s Docket Nos. 50-325/50-324 TAC Nos. 53657/53658 1ii 4 .

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..ABSTRACTi............'.....-.,.......................'.....................

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FO R EWO R D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . ' i i i

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, e i1. . INTRODUCTION ...................................................... I t ~

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'2.- REVIEW. CONTENT AND'F0RMATi.....-.................................... '2'

<3 . -ITEM 2.2.20 . PROGRAM DESCRIPTION'.................................

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. . 3.1 Guideline .................................................... 3 U- '

3.2' Evaluation ....... ........ a..............................:.-

. "3 3.3. .. Conclusion ....y..... . .................-....................... 5 f

c. 4. - -PROGRAM WHERE VENDOR INTERFACE CANNOT PRACTICABLY BE.

E S TAB LI S H ED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . '. . . . . . . . . . . . . . . . . . . . 6

/! f 4 .' 1 - . Guide 11new a.............;.................................. 6 4 2.

c4,3-EvaluatioEA...i............................................

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5.  : RESPONSIBILITIES OF LICENSEE / APPLICANT' AND VENDORS THAT PROVIDE -

SERVICE ON SAFETY-RELATED'EQUIPMENTL................................ 8~

m' 5.1 G u i d e l i n e . . . . . . . . . . . . . . . . . . ' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . 8 5.2" Eva1uationi................................................. .8 5.3- Conclusion'................................................. L8.

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' 6 .' - CONCLUSION:........ .............................................. 9

7. . REFERENCES ........................................................ .

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

• x E VENDOR' INTERFACE PROGRAMS FOR- ALL OTHER SAFETY-RELATED COMPONENTS:

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BRUNSWICK-1 AND:-2^

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.I X INTRODUCTION' J

L O'n February 25, 1983, bothofthe.scramcircuitireakersat. Unit 1of.-

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the Salem Nuclear? Power Plant.. failed to'.openfupon an' automatic reactor trip; r

i7 Esignal.from the' reactor'proiection' system. This incident was" terminated; %

g, ' manually by the~ operator.about 30' seconds-afterLthe initiation of.the ,

automatic-tripisignal. The failure of the circuit breakers'was determined!

-to be reisted to the sticking of the undervoltage trip.: attachment. Prior, L y to .this sident', on February 22,' 1983, at. Unit.1;of the Salem

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Nuclear-

, Power Plant, an automatic trip. signal' was generated based on steam generator low-low;1evel during. plant startup. InLthis case,Jthe reactor.'

iwas tripped manually by:the operator'almost coincidentally with.the; j automatic trip, nm )

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, Following th'ese' incident.s, on February 28, 1983, the NRC Executive- -

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, Director- for. 0perations (EDO), directed the NRC staff:to' investigat'e and - ]

g" . report on theLgeneric. implications of these occurrences at Unit' 1-of the The results of'theistaff's inquiry into:the

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Salem Nuclear Powe'r Plant 1.- ,

d generic Limplications'of.the Salem unit incidents are reported in rNUREG-1000, " Generic Implications'of the.ATWS Events at the: Salem Nuclear Power Plant."' ^s a:re'sult of thisiinvestigation the' Commission;(NRC) h:N ,

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[h requested '(by Generic Letter 83'-28 ' dated July' 8,1983 .) all ._ licensees. of -

y*L, :operatingTreactors, applicants.forfan operating license,:an'd' holders of.

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construction permits;to respond to the generic-issues raised by'the-N analyses of these two ATWS events.

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

' Carolina . Power & Light Company, 'the licensee for the. Brunswick Steam j

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Electric Plant, for Item 2.2.2 of Generic Letter 83-28. The document j

'; . reviewed as a.part of this evaluation is listed in the references at the 'W h.y end'offthis report. s q f

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'2. . REVIEW CONTENT AND FORMAT a item 2'2.2'of Generic Letter 83-28. requests the licensee.or applicant:

E to; submit, for the staff review, a description of their programs for.

. interfacing with the vendors of all safety-related components including 4

support'ingcinformation, .in considerable detail,J as indicated in' the .

guideline.sectionlfor each; case within this report.. _,

These guidelines treat cases where direct vendor contact' programs tre .

pursued, treat cases where such-contact cannot practically be established, and establish' responsibilities of licensees / applicants and vendors that; y ' provide service onLsafety-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

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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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1 3. LITEM 2.2.2 - PROGRAM DESCRIPTION J

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~3 .' 1 ' Guideline'

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licensee or applicant. response should describe their program for establishing;and maintaining interfaces with vendors of safety-related 1.o . .

. components which ensures that. vendors are. contacted on:a periodic basis and g .that -receipt of vendor equipment technical-information (ETI);is acknowledged Lor otherwise verified.-

L 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,

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auxiliary)feedpumps, emergency core cooling system (ECCS) pumps, batteries,

.. y - battery chargers, and. valve. operators, to facilitate the exchange.of current technical.information. .The description .should ' verify that' controlled

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procedures exist for handling.this vendor technical information which ensure, y thatnit.islkept current and complete and that it is. incorporated into plant.

' operating, maintenance and test procedures as is appropriate.

3.2 Evaluation b LThe licensee for the Brunswick Steam Electric-Plant'respohded to these.

~ requirements with'a submittal dated November 7, 1983.2 This submittal

' includes 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 L

note the following.

The following. procedures are referenced in the licensee's submittal:

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7 (ONSI-01 Operating Experience Feedback -

J -Capture and Indexing of Correspondence and Plant: Records RMI-01 4

.AI-02 Feedback of Operating Experience

,PPP-02; Vendor Recommendation Processing ,

e RMI-03 Reproduction, Distribution and Accountability of Plant f.

Documents' f.

.-NP-16 Writing Cberective Maintenance Instructions ENP-22 Equipme'nt Failure Trending and' Analysis These proce'dures incorporate vendor equipment technical information as controlled documents in-the' licensee's document' control process. They also incorporate this information in their maintenance instructions for safety-related equipment. j I

Th'e licensee has stated that a formal. program for. periodic contact with [

-the'NSSS vendor and acknowledgement of feedback exists. Also, that a vendor interface is opened whenever spare parts are ordered. Information gained by these ~ programs is. maintained in a vendor. library that is updated as new information is' gathered. Additionally, the licensee states that they.are.a functional part'of the INPO Nuclear' Utility Task Action Committee (NUTAC) on the Vendor Equipment Technical Information Program (VETIP).

'One of the VETIP implementation responsibilities is 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. However, Section 2.2.2 of the. generic letter states that formal vendor interfaces ,

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. should be' established with vendors besides ' he t NSSS vendor. The licensee s 'has not indicated that any= forma 1Linterface program has been established

, with vendors other..than'the NSSS vendor.

.-3.3 ' Conclusion

We concludeLthat, with the exception of' interaction with the vendors -of other; safety-related equipment, the licensee's response regarding program.

-description.is complete and', therefore, acceptable. The licensee should. .

establish a program to periodically contact vendors of key components (such~

as auxil.iary'feedwater pumps, safety-related batteries, ECCS pumps and j

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.

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f4. ITEM 2 212I PROGRAM-WHEREVENDORINTERFACECANNOTL

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4.1; Guideline j

, 'l The licensee / applicant. response should' describe their program for' c.

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compensating for .the? lack of a formal: vendor interface where such an -

.. interface cann'ot befpra'cticably established. . This program may' reference.  !

E the NUTAC/VETIP program, as described in INP0 84-010, issued in=

March 1984.- JIf the NUTAC/VETIP program'is referenced,.the response should-describe how procedures.were revised to properly. control-land 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

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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 H  : where; necessary to' provide adequate confidence that a structure, system or-

, component'will perform satisfactorily in service and to ensure adequate .

f quality assurance in accordance with . Appendix B 'to 10 CFR Part 50.

4.2 Evaluation For those. vendors where an interface cannot practicably be established, the licensee is a participant in the NUTAC/VETIP program.

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

. 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.

Through participation in the NPRDS program, the licensee submits engineering information, failure reports and operat-ing 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 4

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7 reported'throughthe.NPRDS:programsand' Nuclear, Network'andNRC-reports.

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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-

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-event and.related prob.lems. It also recommends practical. corrective-W

actions. These reports /are' issued as Significant Event Reports, as.  !

'Significant. Operating Experience' Reports and'as Operations and Maintenance Remi nde rs .- Upon receipt of these documents, the 1icensee' evaluates'the.

information to determine applicability to.the facility. ;This evaluation'is  !

.. documented and. corrective' actions are taken as determined necessary.

.The licensee describes existing procedures and instructions (see the list ofiprocedures in Section;3.2)'.for the review and evaluation of.

., information: derived from this source as well as vendor sources'(such as when replacement. parts are p'urchased). Maintenance instructions include vendor recommendations as.a result-of_this process.~ The licensee states-that existing procedures: adequately implement this program.

I 4.3 Conclusion We find that the licensee' . response' addresses this concern

adequately and'.is acceptable.

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-5,l' Guideline s ,

'4 The licensee / applicant. response should verify that:the .

responsibilities of the111censee 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 i

Th'el licensee states that'the activities of safety-related equipment, vendors are controlled'and monitored as required by Section 4 (Procurement and Control) and Section:5 (Material and Equipment Contr'ol) of the' i

Corporate Quality Assurance Manual. The licensee states that these sections! cover' vendor' activities, fabrication, inspection and testing (in accordance'to' specifications) and proper documentation, f

5.3 Conciusion Wes 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 g information1provided by the licensee for this item is acceptable.

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6. CONCLUSION

' Based on our review of' the111censee's response to the specific.

requirements _offitem.2.2.2 for Brunswick-1 and -2, we find that the licensee's-interface program with its NSSS supplier (but not for vendors of' other safety-related equipment), its internal handling of' vendor-supplied L services, along'with~the licensee's commitment.to implement:the NUTAC/VETIP

, program, is acceptable.

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The-licenseo should' establish a program to' periodically contact vendors of key components-(such as auxiliary feedwater pumps, safety-related batteries, ECCS ' pumps and safety-related valve operators) to 1

' facilitate'the exchangt of. current technical information. In the case of the diesel generator a'dn safety-related switchgear vendo'rs, a formal interface, such as that established with the NSSS vendor, should be  !

established, if practicable.

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7. REFERENCES i

L :1. Letter. NRC (D. G.; Eisenhut), to al.1 Licensees 'of Operating Reactors, Appl.icants for Operating. License',-and Holders of Construction Permits,

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

2. Letter, Carolina Power and Light Company (P. W. Howe), to NRC L

(D. G. Eisenhut), " Generic Implications of Salem ATWS-Events,"

. November 7, 1983,: LAP-83-513.

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

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U.S. 8euCLEAR R80ukATOR Y C0asMem0N I ktPOR f NUMSG A f.tssgner er floc. #se Vo, NL <r sayd MacPOSM 338 hhe','- BIBUOGRAPHIC DATA SHEET EGG-NTA-7552 ]

sig INSTRUCflONS ON TMs RaytRst 2 leTLL AND RUGfirLE - - .

. J L8Avt 9 LANE

-CONFORMANCE T0-GENERIC. LETTER 83-28. ITEM 2.2.2--

VENDOR INTERFACE PROGRAMS-FOR ALL OTHER SAFETY-

• oAri apoar CoMaurio RELATED COMPONENTS: BRUNSWICK-1 AND -2 Mo rN nAR 3 May l 1987 l

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7. etRPORMING ORGANi2 AtlON NAME AND MAILING ADORtSS flarnemte CamJ 8 PROJECT /TA$n/ WORE whti NUMetR

'EG&G Idaho, Inc.

P. 0. Box-1625 ,

Idaho. Falls, ID 83415 .D6001 l;

10 SPONSORING ORGAN 12ATION NAME AND MAILING ADORESS (Jar,seau Je Cams lie, TYPt OF REPORT

' Division of PWR Licensing - A  ;

Office of Nuclear Reactor Regulation s. ,, R,oo Cov .R, o ,,,,,,,.. . , i U.5. Nuclear Regulatory Commission 1 u ' Washington, DC 20555 1 s

17 SUP8LSM4NT ARY Norts l

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.This EG&G Idaho, Inc., report provides a review of the.submittals from the Carolina Power and Light Company regarding conformance to Generic Letter

'83-28, Item 2.2 2, for-Brunswick-1 and -2.

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