ML20205N943
| ML20205N943 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 10/31/1988 |
| From: | Udy A IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY |
| To: | NRC |
| Shared Package | |
| ML20205N941 | List: |
| References | |
| CON-FIN-D-6001 EGG-NTA-7269, GL-83-28, TAC-53689, NUDOCS 8811070119 | |
| Download: ML20205N943 (20) | |
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. EGG HTA 7269 2.i , . January 1988 f..
INFORMAL REPORT l
. .: . 4 Idaho Nat/onal i - s.
Engineering : '*,1 Laboratory .tyg CONFORMANCE TO GENERIC LETTER 83 28, d '. ITEM 2.2.1 EQUIPMENT CLASSIFICATION FOR ALL
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OTHER SAFETY RELATED COMPONENTS: MILLSTONE 1 WW by the U.S.
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DISCLAIMER N ocee .es reeceo se em aceova i e wers womeets e, na egrev of ew Wwe
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, EGG-NTA-7269 TECHNICAL EVALUATION REPORT 1
CONFORM.ANCE TO GENERIC LETTER 83-28. ITEM 2.2.1--
EQUIPMENT CLASSIFICATICN FOR ALL OTHER SAFETY-RELATF,0 COMPCNENTS:
MILLSTCNE-1 Cocket No. 50-245 Alan C. Udy P.011shec January 1983 Idaho National Eng',ies in; Laboratory EC'" iJaho, Inc.
Icaho Falls, Icaho 8.415
- e:a e: 'e the U.S. Nuclear Regulatory Commission Washington. 0.C. 20555 Unoer DOE Contract Nc. DE-AC07-761001570 FIN No. C6001
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'e A8STRACT This EG&G Idaho, Inc., report provides a review of the submittal from Unit No. 1 of the Millstone Nuclear Power Sta;ien for conformance to
! Generic Letter 83-28. Item 2.2.1, i
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Oceket No. 50-245 l
- TAC No. 53689 11 1
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FORE'atRD 1 1
Ir.is re::rt is su;cliac as : art of tne pr:grar : . eva war.n; licensee /a:clicant confer-ance to Generic Letter 83-28 "Recuired Actions l Easec en Generic 1.- lications of Salem AT=5 Events." This work is being c:rcu: tee fer tne U.S. N.: lear Regulat ry C: uission, Office of Nu: lear Reacter Regulation, Divislen of Engineering anc System Technology, by E m Icano, Inc., Electrical, Instru entation anc Centrol Systems Evaluation Unit.
The U.S. Nucinar Regulatory Co-nission funced this work under the aatneri:stien B&R 20-19-10-11-3, FIN No. 06001.
Cocket No. 50-245 TA: No. 53669 111
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CONTENTS A E S T RA C T . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 Fv. st=.0R0 .............................................................. 111
- 1. INTRCDUCTION ..................................................... 1
- 2. R E V I EW C ON T EN T AND FO RMAT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
- 3. I T EM 2 . 2 .1 - P R OG RAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 3.1 Guideline ............................................. ... 3 3.2 Evaluation ................................................. 3 3.3 Cenclusion ................................................. 4 4 ITEM 2.2.1.1 - ICENTIFICAi!CN CRITERIA ........................... 5
- 4.1 Guiceline .................................................. 5 4.2 Evaluation ................................................. 5 4.3 Ccnclusion ................................................. 6
- 5. ITEM 2.2.1.2 - INFORMATION RANDLING SYSTEM ....................... 7
%1 Guideline .................................................. 7 s.2 Evaluation ..... ........................................... 7 5.3 Conclusion ......................................... ....... 7
- 6. ITEM 2.2.1.3 - USE OF EQUIPMENT CLA551FICATION t!$ TING ........... 8 i
6.1 Guiceline .................................................. 8 6.2 Evaluation ................................................. &
6.3 Conclusten ................................................. 8
- 7. ITEM 2.2.1.4 - MANAGEMENT CONTROL 5 ............................... 9 7.1 Guiceline .................................................. 9 7.2 Evaluation ........... ............................... ..... 9 7.3 Conclusion ................................................. 9
- 4. ! TEM 2.2.1.5 - DE51GN VERIFICATION AND PROCUREMENT . . . . . . . . . . . . . . . 10 8.1 Guideline .................................................. 10 2.0 E.a'ast ce i
...... ... .... .. . .. . .... .. .. ... .. 'O 8.3 Conclusion ................................................, 10 9.. ! TEM 2.2.1.6 "!KPORTANT TO 5AFETY" COM/CNENT5 ..................
11 9.1 Guideline ................. ................................ 11
- 10. CONCLU510N ...................................................... 12
- 11. REFEREN:!5 .......................................... ........... 13 iv
- e. O CONFORMANCE TO GENERIC LETTER 83-28. ! TEM 2.2.1--
EOUTP"ENT CLA$$1FICATICN FOR Alt. OTHER SAFETY-RELATED COMP 0NENT$(
Mit.t.$ TONE-1
- 1. INTRODUCTICN On February 25, 1983. both of the scram circuit breake*s at Unit 1 ef the 5alem Nuclear Power Plant failed to'open bpon an autoratic reactor tric signal from the reactor pret.ection systee. This incident was terminated manually cy the operator acout 30 sacer.cs af t6r the tr.itiation of sne automatic trip signal. The failure of the circuit breakers was determined to be related to the sticking of the uncervoltage trip atsschment. Prior tc tnis incicent, on Fe:rvary 22, 1983, at Unit 1 of the ?,alem Nuclear Pc er Plant, an autematic trip signal was generated based on steam generator low-low level curing plant startup. In this .ase, the reacter was tricce: manually ty the acerator aleest coincicentally with sne automltic trip.
Fc11 ewing there incidents, on February 28, 1983, the NRC Executive Director for i= rations (EDO), directed tne NRC staff to investigate and roccet ce the geretic ten 11 cations of these occurrences at Unit 1 of the
$ates Nuclear Dower Plant. The results of the staff's inquiry into the l generic imolicat,iens of the Salem incidents are reported in NUREG-1000, l
"Generte Implications of the ATW$ Events at the Sales Nuclear Power Plant." As a result of this investigation, the Commission (NR;) recueste:'
(by Generic Letter 83-28 dated July 8, 1983 I ) all licensees of ope sting reactors, applicants for an operating license, and holcert of construction I
permits to respond to the generic issues raised by the analyses of these two ATV$ events.
This report is an evaluatien cf the res:enses submi te: ty the Northeast Utilities Company, the 11cen,see for the Millstone Nuclear Power Station, for Itca 2 0.1 of Generic Letter 83-28. The accueents reviewed as a part of this evaluation are listed in the references at the end of this reDort.
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- 2. REVIN CONTENT. AND FORMAT ,
Item 2.2.1 of Generic Letter 83-28 recuests ..4 licensee /acpitcant submit, for staff review, a description of their programs for safety-related equipment classification inclucing supporting information, in consicerable detail, as indicated in the guideline section for each item within this report.
As previously stated, each of the sin items of Item 2.2.1 is cvaluatec in a separate section in which the guiseline it presentect an evaluation of
- Pt li:tr.see's/ app 1*: cant's response is mace; anc c:n:' oion: at:. tr.a ticensee's or acclicart's program for safety- elated equipment classification are crawn.
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- 3. Item 2.2.1 - PROGRAM 3.1 Guideltne Licensees and acclicants should tonfina that an ecuipment classification program esists that provides assurance that all safety-related components are designated as safety-related on clant cocementation and in the information handling system that controls safety-related activities. The purpose of this program is to ensure that personnel performing activities that affect safety-related components are aware that they are working on safety-related components and are guiced by safety-related procecures anc constraints. Features of this program are evaluatec in the remaincer of this report.
3.2 Evaluation The licenset for Unit 1 of the Millstone Nuclear Power $tation resconcec to these r6cuirements with submittals dated Novemcer 8, 1983 2 sed March 13, 1987. These submittals include information that describes the Millstone-1 safety-related sculpment classification program. In the review of tse licensee's response to this item, it was assueec that the information and cocumentation succorting this irogram is available for audit upon recuest.
The licensee's computer-based Production Maintenance Management $ystem
(#"MS) anc the Material. Ecuipment and Parts List (MEPL) make us the sculpeent classification program. Both the PMM$ and tne MEPL use Nuclear Engineering and Operations procedures (6.10 and 6.01) for control. Thus, the Nuclear Engineering and Operations Departmens has the responsibility for beth the DWW$ end the WEDL.
' wark orcers are generated by the PMM$ and incluce a cesignation for safety-related work activities. The plant procedures for surveillance testing, acministrative control procedures, drawings, and purchase docueents also cesignate safety-related souisment.
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e 3.3 Cenelusten We have reviewed the 11Cen$tt's submittall and find that the lictnSet's Pts:Cn!* 15 adequate, 1
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, 4. ITEM 2.2.1.1 - IDENTIFICATION CRITERIA 4.1 Guideline The arolicant or Itcensee should confire that the program used for ecuipment classification includes criteria for identifying components as safety-related.
4.2 Evaluation Tne licensee's response provided the criteria for the original and ongoing identification of systems, structures, and components as safety-related. The criteria consist of a listing of safety-related systems, structures, and components, and include. .'oundations and su corts.
Tre listing consists of 19 items, cost of whten contain sub-items. Tne l
licensee states that these criteria are currently used to identify safety-related components in accordance with quality assurance procedures.
Geeeric Letter 83-28 identifies as safety-related those structures, systems, and components that assure (following a design basis event) (1) the integrity of the reactor ceolant boundary (2) the capability to snut down the reactor ar.d to maintain 1 in a safe snuscown condition, and (3) the cacability to prevent or to mitigate consecuential offsite exposures.
The licensee defines (but the definition is not limited to) as safety-related those systems, st.ructures, and components, including associated foundations, supports, and auxiliary systems, that: (1) are a portion of the reactor coolant pressure boundary; (2) are used for emergency core cooling, reactor shutdown, residual heat removal and cooling water systems which support the previous systems; and (3) reactivity contrel systems, primary to secondary containment, Dortions of radioactive waste
.ontrol systems, and systems snat might contain racteactive materials and wnose postulated failure could result'in offsite exposures.
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4.3 Conclusion he find that the criteria used to identify safety-related components encompasses the definition for safety-related that is part of the generic letter. Therefore the identification criteria meets the requirements of Ium 2.2.1.1.
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- 5. ITEM 2.2.1.2 - INFORMTION HANDLING SYSTEM 5.1 Guideline The licensee or applicant should confirm that tne program for equipment classification includes an information handling system that is l used to identify safety-related components. The response snould confirm !
that this information handling system in'cludes a list of safety-related ,
equipment and that procedures exist which govern its development and
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5.2 ! valuation Tne Itcensee's submittals icentify the harc-copy MEPL as the information handling system that lists safety-related structures, systets, com:enents, anc parts. The PW.5 is a computerized data base that will eventually replace the MEPL. Currently the two systems co-exist, and the MEPL is the governing document. The licensee's cescription of the systems included the rethods used for the development of these systems, the process by wnten new safety-related items are entered; how changes in tne classification of listed itees are made, how listed items are verified, hcw unauthorized changes to sne listing are preventec, and now the listing is enintained and distributed to online computer terminal users. Revisions to l
b:th sne MEpL and the Pm $ are controlled by the MEPL engineer 5.3 Comelusion l
l he find that the information contained in the i censee's submittals is sufficient for us to conclude that the licensee's information hancling system for equipment classification meets the guiceline requiretents.
l inerefore, tne information orovicec ey sne licensee for smis tsam is 1 acceptabit.
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- 6. ITEM 2.2.1.3 - USE OF EQUIPMENT CLAS$1 FICA 71CN L1$71N3 ,
6.1 guideline The licensee's or applicant's description should confirm that the program for equipment Classification includes criteria and procedures that govern how station personnes use the equipment c1 4354ficat4CP inf 0**atica handling system to determine that an activity is safety-relatec. The coscription should also include the procecures for maihtenance, r;-.c'11a cs, psets rec!acces-t, a-: ct*:- tctiv did ?: d cd '- t's introcuction to 10 CFR 50. Appendia B, that apply to safety-related comoenents.
6.2 Evaluatien The licensee states that either the MEPL or the PMMS is consultec to cetermine the safety-related status of the above work activities. The .
Itcensee has proviced a listing of Acministrative Control Procecures that .
adcress these activities. The licensee has also shown how proceCures to be usec in the above activities are icentified as safety-relatec.
6.3 Cemelusten We find that the licensee's description of plant seministrative ,
controls and procedures meets the requirements of this item anc is, snerefore, acceptable.
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- 7. ITEM 2.2.1.4 - KANAGEMENT CONTROLS 7.1 Guicoline The applicant or licensee should briefly describe the management controls that are used to verify that the precedures for preparation, valication, and routine utt11:stion of the information handlieg system have teen anc are being followec.
7.2 Eva1watton The licensee's restc9se states that their Quality Assurance Program fccical Re:crt lea"t: ss the Petecc of manage *1a1 control. CAP 18.0 (aucits), as 1eplemente: by NOA 1.14, is used to verify the preparation, valicatien, anc rewtine use of the inforesticn hancling system. Qwality assuraece reviews anc aucits cecur en a schedulec basis anc assure that the programs anc their implementation are correct.
7.3 Conclusion
'ne fine that the management controls usec ey the licensee assure that tre inforeation handling sys',em is maintained, 15 current, and is ulec as inteece:. Tnerefore, the licensee's response for this item is acceptable.
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- 8. ITEM 2.2.1.5 - DESIGN VERIFICATION AND PROCUREMENT 8.1 Guice11me The applicant's or licensee's submittal show1c cocument that past usage cetenstrates that appropriate design verification and qualification testing are scocified for the crocurement of safety-relateo ecmcoments arc ca'ts. The scocifications showlc include ewalification testing for en:ectec safety service concisions anc provice support for the acclicant's/ licensee's receipt of testing cor.mentatten te s.;swrt ste limits of life retemmences by the sweelier. If such cocumentation is ect available, confirmation that tne present pregram meets these recuirements sncalc te :rovicec.
. 8.2 Evaluatten Nuclear Engineer.ing anc 0:erations (NEC) Procedure 5.04 ts the c:ntrollies seccecure for procurement. NE0 Procecure 6.02 outlines tre a::retriate cocumentation reswirements. The originator of the purchase retwisition is respons1 Die for scocifying tne technical, testing, anc c:catentation recuirements of the v"urchase. Restensittlity for ensw*ing snat qualification testing anc testing documeetation are.scocified is also celimented in Prececure 6.02.
8.3 Cemclusiem Tne licensee's response for this item is consicerec to ce cceplete.
Tne information provised accresses the concerns of this ites anc is acce: table.
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- 9. ! TEM 2.2.1.6 "1MPORTANT TO SAFETY" COMPCNENTS 9.1 Guiceline Generic Letter 83-28 states that the licensee's or apolicant's equipment classification program should include (in addition to the safety-related components) a broader class of ce*porents designatet as "Im ortant to $afety." However, since t'he generic letter does not reawire the licensee or applicant to furnish this information as part of their ressonse, this item will not be reviewec.
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- 10. CONOLU$1CN Based on our review of the licensee's response to the soecific reavirements of Item 2.2.1, we find that the inforsation provided my the Itcensee to resolve the concerns of Items 2.2.1.1, 2.2.1.2, 2.2.1.3, 2.2.1.4. and 2.2.1.5 meets the requirements of Generic Letter 83 28 anc is ac:ectatie. Item 2.2.1.6 was not reviewpe, as noted in Section 9.1.
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- 11. REFEREN;ES
- 1. Letter, NR (0, G. Eisenhut) to all Licensees of Operating Reactors, Acclicants for Operating License, anc Holcers of Construction Permits, "Re: wired Actions lased on Generic Implications of $alem ATW5 Events (Generic Letter 83-28)," July 8, 1983.
- 2. Letter, No*theast Utilities Com any (V. G. Cownstl) to NRO (0, G. Eisenhus), "Rescense to Generic Letter 83 28. Gemeric Imolications of Salem ATV$ Events," Novemeer 8, 1983. A03381, Atta:hments 2 inc 5. -
- 3. Letter, hertheast utilities company (E. J. Mroc4ka) to NRC, "Generic
'. ette 83-28. Item 2.2, 'E:w':=ent C1stsif *:stice' " war:h 13, 1981 A06176, A06384, AC6345, 812375.
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CONFOR$ NCE TO GENERIC LETTER 83 28. ITEM 2.2.1..
EQUIPMENT CLAS$!FICATION FOR ALL OTHER SAFETY.RELATED COM70NENT5: N!LLSTONE.1 *a'" ~
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. . + . January 19A8 Alan C. Udy * * * ** ' m ie January l 1568
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En83 !caho. Inc. '"""" -
P. O. Box 1625 Idaho Falls. 10 83415 06001
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Division of Engineering and System Technology Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission .a==~-
Washington DC 20555
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This EG83 Idaho. Inc.. report provides a review of the submittals from Unit No.1 of the Millstone Nuclear P0ver Station regarding conformance to Generic Letter 83 28 Ite'n 2.2.1.
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