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#REDIRECT [[IA-92-212, Final Response to FOIA Request for Documents Re Insp of Susquehanna Steam Electric Station.Forwards Apps F & G Documents.App G Record Partially Withheld & App H Documents Completely Withheld (Ref FOIA Exemptions 5 & 7)]]
| number = ML20128H287
| issue date = 10/29/1992
| title = Final Response to FOIA Request for Documents Re Insp of Susquehanna Steam Electric Station.Forwards Apps F & G Documents.App G Record Partially Withheld & App H Documents Completely Withheld (Ref FOIA Exemptions 5 & 7)
| author name = Grimsley D
| author affiliation = NRC OFFICE OF ADMINISTRATION (ADM)
| addressee name = Hymanson M
| addressee affiliation = MUNGER, TOLLES & OLSON
| docket = 05000387, 05000388
| license number =
| contact person =
| case reference number = FOIA-92-212
| document report number = NUDOCS 9302160330
| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE
| page count = 5
| project =
| stage = Other
}}
 
=Text=
{{#Wiki_filter:-
w a vetas mc e wn w m muN                            scrain ,m r,*,iam
                              .g                                                                                    FOlA - 907 - 3 / z. -
  ,f. e.%                                                                                                                              airO~si t m g'
* 4 $p-                                RESPONSE TO FREEDOM OF                                                ki riNat                1:PAatiat INFORMATION ACT (FOIA) REQUEST                                              o^fi                      :
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PART l.-AGENCY RfCORDS RELE ASLD OH NOT LOCATED ($recherArdboars/
No agency itsords subject to the request have been located.
No additional agency rnords tubject to the request have been located.
Requested enords are available through annther public distribution proyam. See Comments section.-
Agency records subint to the requnt that are identified in Appendiates)          N              are already asellable for pubhc inspection and copying at the NRC Pubhc Document Room,2120 L Street, N.W., Washington, DC, Agency records subject to the request that are identitled in Appendiates)                        are be:ng made available for public inspection and copying .
at the NRC Public Dxument Room,2120 L Street, N.W., Washington, DC,in a folder under this FOIA number, The nonproprietary verCon of the prop (dalM that you agreed to accept in a telephone conversation with a member of rny staf f is now being made sveilable for public inspection and cN ving at the NRC Public Document Room 2120 t. Street, N.W., Washing *on, DC,in a folder under th4 F OIA number.-
Agency records subject to the request that are identified ir. Avi+ndiales)                rnay be inspected and copied at the N RC 1 ocal Public Document -
Roo.n identified in the Comments section.
Enclosed is information on how you may obtam access to and the chargr s for copying records located at the NRC Public Document Room,2120 L 4treet, N .W.,. Washington. DC.
g      Agency records subject to the request are enclosed. -[          .jg [ e,Lg Records subint to the request have been referred to another Federal agencyhes) for review and direct response to you.
[    Fees You wit! be billed by the NRC for fees totabog $_    !                      -
You will receive a refund from the N RC in the amount oi $                              .
        -In view of NRC's response to this request, no further action It being taktn on appee? 'etter dated                              ; No _ -                    ,
PART 11. A-INf ORMATION WigHELD l FtbM PUBLIC DISCLOSURE Certain inf ormation in the requested recorda ls being withheld from public disclosure purcuant.to the e semptions described In and lof tha reasons stated..
V    in Port fl, B, C, and D. Any released porOons of the documents for which only part of the rerord is being withhelrf are being made available for public (T    inspection and copying in the NRC Public Document Room,2t20 L Street, N W., Washington, DC in a folder under this fos A number, COMME NTS p ~4                              /.w t.ro
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                  -PDR :FOIA:
                . ;HYNANSO92-212 .PDR                        _
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                                                                                                                                                                                    ,w s,s,rr                                                            nt, RESPONSE TO FREEDOM OF INFORMATION ACT (FOlA) REQUEST                                                                                    FOlA -                                      -  h-                          OCT 2 9 $32
      ,(                  ,
(CON 11NUAT 40N)
PAftf li B- APPNCABLE ExtMPilONS                                                                                                                                                                                            ,
Records setiect to the request that are degribed in the enclowd Appendmfes)k                                                                                - are t,eing withheld in their entirety tw in part urider the Laemption Nods) and for the reason (s) given tielow pursuant to 6 U $ C. %2(W and 10 CF R 9.17(a) of NHC repatkins.                                                                                                                                                                                                              t
    'W 4 . The wethhekt intotmet.on es poperly c!ctsefeed pu.suant ta f secvties Order, d aernet on 11                                                                                                                                                                                                                              ;
                                                                                                                                                                                                    .      ~ . - . - -                                , _ . ,                                                                        .-
2 The withbeV eitorvostion seletet so6ely to the entertial personnel tules a**d p'otedures of hsgC (f nempt60n 26 3 The w*beid ordoernation es specit,cali, e empted t oni pubi4 d1sciosu.e ce itsiute ir+cetw. ((semption at
                              $6t.ons 1J1146 Of the Atomic (hergt Act, whith papNtuts the declosu'e of Aentretied Date or Fo+mesty Aestocied Date (42 U,$ C,21612166).
                                                                                                                                                                      - - - -                                        _,,                                                                          w mn    -                              -
Sect +n 147 of the itomic [ne#gy Act. wh4.h proh'brts the d4r tosse of Unetess f ed Sa'eNaedt information 147 U $.C. 216M.
: 4. The *tthe eid mfomatton as a trede 6ettet of Conwne'ost or imential enf otmautm that is bemg withheld fee the seasonis) 6ttdicsied. (I atmptiori 4)                                                    - - - - , . .
                                                                                                                                                        .r      -_ , -
      &.l                      The miofmeteon is consideted to be rorAdental tuisiness lptopficta*y) eformahnn
            , +.
The entomstmn is considried to t,e propheta y mfortnetruti puesuant tr,.10 Cf A 2 79Chdn1 m              -
The ir4tmation was submitted and eccewed m cr rAdrnte ps taant to 10 (f k 219D d 2-            e 9
6 The wthbrid Anfotr nr.on consists et vrae+pg*ncy ot mHeegerst, retow Itat ait eersi nadstic * > / a+y.e*,es**phigabon ((sernpben bl Applicable Privaege-
                                                                                                                                      ~
i'                      Dehberate,e Pwess 0.stlosure oIpUcitMaUrMrnsten would tNd l'oM,7the~tI~ ea and                                                                  t    ha% ensharge of stJess enent a' to the debbetebre process                                                                                          l y    Where setoeds are withheld in theu entsett. the totis aw weie4 at?. intern amed with the t"edet ao''af terwaSon Thef t also see eso reasonably seJiegatae tactua                                                                                                                                                  i
                        /\ po'tior's bec st.se the refense of its Mis wouso permit go ed4et1 nnun, mio lhe prede; wa' gadi est to the egent y 1                                                                                                                                                                                                                                            , .~._ - -,.- ..
ATINbe, woo peorixt pov>iepe Omuments owpved t.y an at to"+ , m c. cetempf a'nso 4 4 m ut ++                                                                                  .
Attorney.chent povaepe, (Contdenbal commurucatmos t tiween en atiomey end im het chent t                                                                                :....                    .--n.,~..                    _ n                        .              en                      . ,    ..e
: 6. The mt**sid efptnanon +s e nempted f >om tubht dwowe ties avse its o sriewe wwd 'es# + a t a r v -wa"ar'ted evenwr' cit osofS                                                  ,  r                                    l            pu atv y (f aempteo'n 61
                                                            - - , . _ _ _ . _ _ . _ _ _ __ . . . ~ _ _ -
7 The withheld mtormebon crmsists of ret oeds corneed f ot fan eMonement putnses and a t'e eg withheid lov the #cason'st indica'ed (E m emption 7)
D6sclosvte could ttatoe.eb!v be empveted 10 mterlere mth an enfo'tement pioctert'ng tierause it tou'd rental the itt+e, direchon. and focus of l enforcement of fonts. and thut couhilosobly 4404 retc ents to take ettem to sh> eld puter-1 a' mo^pvr$ oe a oestion of NRC requaements from investigniort l( aere=pbon 7 ( Ah Disclosure would constitute an u rwananted m asion of pe' sons' pmscy (E nempt$n 71C7)
                                                                                                                                                                              +M                        m w e, im e me,ted to w < cal wicnnpes ut The d'fo*mabon consats of names of ar                                  1.e av v N
* en .3 a w a 1 W wm.
i c onf 4enba' soutsel li nemption 7 (D H                                                                                                                                                                                                                      .
OT H! 84 PART 11 C- DENYING OFFICI ALS
          ' Pwsuant to 10 Cf A 9 2bibi amt m 9 26M cf tM U.S %cita RegWtm v Commm on '* gest ohn a M t er dets<m nn that the mformabon withheld s enempt from pro duct.on or darlowe, and that a production o daciosce is convair to fne putAc enterest The pencas respans toe te the rien# s'e those afloa's ident4ed below as tieMmg eiff eels and the Dae(tor. D..+on of F rewom of Informanon entf Pot.hcai ons Semces Ott r, of Adm n menoa, for any denas that enay be appealed to the imecut6ve Di< ecto <
          ' for Operat ons if DO)
TiflOOf f tCE                                                                        RICORDS OlNi[D                                                APPfll Af f OFFICIAL DINYING Of fiCIAi
                                                                                                                                                .                                                                                                              ~ ftd "                SEcrqtany                                to
                                                                                          -    (/ . d.. e. .'_                      _ - , __ 9                                                              _ - . - - - _&. .                          . _ _
                                      ~ - -
_ , .%scW._ ~. %.-      ~
Alw46-
                                                                                                                                                                                      .s
                                                                                                                                                                                          . GHf                -
                                                                                                                                                                                                                                                                                    --                                  - . ~ .
                                                                                                                                                                                                                                                                                      . . ~ .                                            _
                                                                                                                                                                                                                                          .-                ~-
_.___.. _. .-            '.*_{
                                                                                                                  .                                                            -..4-.
nn                                ~-
4e.4.W 4W.e.i.e.g C e  .
PART 11. D- APPEAL RtGHTS                                                                                                                                                                              -_
3 The dental by each denymg ofhcial identAed in Pa t ll.C may be appealnd to the Appellate Off t.af ident i ed the*e. Ariv seh arrest must be made in writing withM                                                                                                                                                            #
of this responsa. Appeals rnust t>e addressed, as appropriate, to the (secut#ve Ostector for Operations, to the secrets'y of the commisson, or to the laspec ReN! story Commission, Washington, DC 20555, and should cleary stee on the envelope and in the lettot that it is an ''Appest f rom an Initial FOI A Decisio                                                                                                                                                                  l.
U S. NUCLEAR REGULATORY COMMISSION NRC FORM 464 (Part 210-91)
 
        . e- ,
                                                                                      ' Ro t -                    'FOIA-92-212                                  -
APPEllDIX - F -
BE9EDR_MAINTILUMD EiONG_ PDR FUd?J HUMER            DATE                                              DEEEDVION
: 1.              11/22/88        liRC Bulletin lio. 88-10                                              lionconforming                  .
Molded-Case Circuit Breakers (13 pagos) '
A110 8811180315                                                                                                ,
: 2.                8/13/90        Memo-to T. T. Martin from W. T. Russell!                                                                        [
re: Allegation :- (RI-89-A-0072)-. Adjustmont of Molded Caso Circuit Dreakers (MCCB).
at Susquehanna-(5 pagos) A110 9008150133.-
l h
5 i
. .                                                                                                                                                            t 1 '
i 7
I b
4
                                                                                                                              ,f _-
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e .
Rox    .FOIA-92-212 APPENDIX G 11ECORDLEN3TIALLY WITilHELD llVMlHiB DEU?              DliSClulTLQL{_& EXEMEEIpli
: 1.      8/13/90      Annotations on memo to T. T. 14artin from W. T. Russell ret. Allegation (RI-89-A-0072)' Adjustment of Molded Case circuit Breakers (MCCB) at Susquehanna (1 page)
EX. 5
 
p Re:    FOIA-92-212
                                    - APPENDIX .li RECDEDr.>_IO.TAIJN WITitt1 ELD HWiDEB -DATE                DEECRU"rIDH_LEKEliP11QH
: 1.      5/21/90      Note to P. Rosa from-H. Drach (1 page)
EX. 5
: 2.      5/29/90      NRR Allegation Review Board Meeting Notice (1 pago) EX. S 3.. 6/14/90      Memo.to E. W. Drach from F. Rosa'With enclosed draft letter (3 pages) EX. 5 and-7A
: 4.      12/24/90    Lotter to an individual from J. L oe  L =(1 page) EX. 7A
: 5.      12/18/91    Lotter to an. individual from'J. Lee.(1 page) EX. 7A 6.. Undated      2egulatory Information Distribution
                                -System-(1 page) EX. 7A  .
: 7.      Undated      Regulatory Information Distribution System with enclosed Routing and-Transmittal Slip and handwritton' note'(3':
pages)-EX. 7A-l l'
l 1-l
 
. _. s                                                        MUNOC R, TOL L CS E. OLSON
          .$  -                                              .s................,....c,..........
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Director Division of Freedom of Information and Publication Services United States Nuclear Regulatory Commission
                . Washington, D.C. 20555 Re:        in Re Circuit Breaker Litigation USDC, Centril"DIst W 6 G 61H ornla Case No. CV88-3012 RG                                                                                                                      s
 
==Dear 51r:==
 
our firm represents Westinghouse Electric Corporation in the abovc-referenced litigation.                                                                In order to develop informationi that will assist Westinghouse in this care, we wish to make a request under the authority of the Freedom of Information Set,
                .5 United States Code S 552,'and 10 Code of Federal Regulations S 9.23 for certain documents in the possession of the Nuclear Regulatory Commission.
This request is for all documents concerning the NRC Inspection of 14CCB Adjustment Procedures .at Susquehanna' Steam Electric Station--NRC Docket No.. 50-387/388, and includi'19,- but not limited to, File No. RI-89-A-0072.                                                                  -In addition to;all~
documents relating to the Report issued by Region I:of the Nuclear Regulatory Commission on March 6, 1990 follow.ing its Inspection of Susquehanna Units 1 and 2 on January 22 through 26, 1990 (hereinafter the ' Report"), we wish to obtain copies of any and all subsequent reports, notes, investigations, or dissenting opinions issued by anyone at the Nuclear Regulatory Commission
                  ~ I. 5            y            )                                                                                                                                      '
 
c- .      . +,;-
        ..y        ,.
OMUNGER.iTOt.tCS & OLSON                                                                                                                                                                                                                          -
Nuclear Regulatory commission                                                                                                                                                                                                '
April 21, 1992                                                                                                                                                                                                                        ,
Page'2                                                                                                                                                                                                                                ;
i regarding-any"of the-issues raised 1n the-March 6, 1990 Report.                                                                                                                                                                      l These documents would include correspondence to or from parties                                                                                                                                                                  1 outside the Nuclear Regulatory Commission regarding,the Report,                                                                                                                                                                      ,
as well as any reports or notes made by Commission personnel                                                                                                                                                                          ;
regarding any visits to or discussions with any conpanies that'-                                                                                                                                                                      ,
manufacture molded caso circuit breakers ("MccB's"),. including                                                                                                                                                              y!
Westinghouse, regarding the procedures followed at the                                                                                                                                                                                  .
Susquehanna-Steam Electric Station.                                                                                                                                                                                            -.
We will, of cource, reimburse you for,the~ search-and                                                                                                                        .
copy costo associated with this request,-as specified in410 code-                                                                                                                                                                      '
of Federal Regulations-$$ 9'.3J et. seq.                                                                                                                Please let me know as-soon as_possible if you require any additionni information in..'                                                                                                                                                                      i order to comply with this request.-                                                                                                                                                                                                .l Sincerely ~,                                                                                  $
7hg3;,ib;w y        %                                                                -
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                                                                                                                                                                                                                                                            .f 1
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OMB No. 3150 0011                  -
NRCB Be 10 i
UNITED STATES                                                        \
NUCLEAR REGULATORY COMM15510N                                            -
{
OFFICE Of NUCLEAR REACTOR REGULATION                                      t          j WASHINGTON. D.C. 20555 November 27, 1988 NRC Bulletin No. 88-10:
NONCONFORMINC HOLDED-CASE circuli BREAKERS Addressees:
All  holders of operating licenses or construction permits reactors.                                                                          wer for nuclear po
 
==Purpose:==
f          1 provide reasonable assurance that molded-case circuit                                              y ciuding CBs applications          used w{thout    with mc*or verifiable              controllers, purjhased for traceability                                  use in safety-related factnrer (CBM) perform their safety functions,to the circuit breaker manu-                                  -
thyscription of Circumstances:
Circuit Breakers." dated July 8,1988, and                                          Supplerent I theret e
dated July 21,'
that its Diablo Canyon Nuclear Power etPlant was supp Systecis. Inc. through a '.ocal electrical distributor.                          -
e These CBs (Square D cations at the Diablo Canyon Nuclear PowerePlant.                          -
appli- molded case, that      an inspection refurbished  Square D Companyand testing equip.ient.of these breakers detennined that thSquare D Com    -
e CBs were Furthennore. Square D reported that
!      writers perfonted.      Laboratories. Inc. (UL) specifications                          cal tests for all of the e panies that were involved in supplyingossibly                                  surplus refurbished an
      /$efective refurbished electrical equipment to the nuclear industry.
During recent NRC inspections, additional examples                                      were identified th t indicate to              a poter,tial nuclear power    plants. safety concern regarding electrical                a eouipment supplied as new and assumed to maet all applicable plant de$ign requirem                        or original requirements    manufacturer's and specifications. specifications may, he fact, not confom to these 1.
Refer to Attachment 2 for Definition of Terms i W 1/ lo36 M                                            g aum PDR T$E S W h 9 'B - O l o
* NRCB 88-10 November 22, 1988 Page 2 of 1 The actions requested in this bulletin are limited to molded case CBs. Molded-case CBs are tested and calibrated at the manufacturer's plant in accordance with recognized industry standards, such as UL 489, " Molded Case Circuit Breakers and Circuit Breaker Enclosures " and National Electrical Manufacturers Associ-atter (NEMA)-AB1,
* Molded-Case Circuit Breakers." Since molded-case CBs have factory-calibrated and sealed elements, any unauthorized modification or re-furbishing of these CBs (.ould jeopardize their design capability and reliability.
The NRC is concerned that the reliability and capabilities of refurbished CBs purchased as commercial grade (non-Class IE) for later upgrading to safety-related (Class 1E) applications may not meet the minimum commercial grade standards.      In addittun, the NRC is concerned abou'. the reliability and capa-bilities of comercial grade CBs upgraded to safety-related because of some observed inadequacies in the dedication process and numerous failures found during the testing of some of these CBs. In order to properly dedicate electrical items procured as commercial grade for subsequent use in safety-related applications, the dedication process should build from the comercial grade quality, include a proper evaluation of seismic and environn' ental quali-fication, confirm critical parameters, and include testing as appropriate.
Molded-case CBs purchased from the CBM or that can be traced to the CBM are of lesser concern than other molded-case CBS because CBs from the CBM, whether safety-related or comercial grade, are manufactured under controlled conditions to conform to a proven design. Safety-related CBs the CBM are controlled under quality assurance (QA)        purchased programs          as Class that conform  to 1E from Appendix B of 10 CFR Part 50. While upgrading programs may vary 'n Quality, the controls exercised by the CBM over the manufacturing activities provide reasonable assurance that improperly refurbished components have not been in-              ,
troduced and passed through the upgrading process. Furthermore, the redundancy
                                                                                                            ~
of safety systems and the in-service use of CBs provide a rei.sonoLk hasis for accepting installed replacement CBs that have been procured from the CBm er that can be traced to the CBM.
The NRC currently believes that the concerns addressed in this bulletin do not apply to electrical cauipment (safety-related and comercial grade) originally-installed in plants. This equipment appears to have been procured during plant construction from CBMs with full certification. The large quantities of electrical assemblies or components procured under bid packages during plant construction reduce th^ possibility of any original plant equipment being sup-plied by vendors doing refurbishing, Although the actions. requested in this bulletin only apply to safety-related molded-case CBs, the NRC intends to monitor industry programs to ensure that other molded-case CBs, which may have been installed as replacements, installed
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during modifications, or are being maintained as stored spares, are suitable for their intended service. Addressees are encouraged to participate in a joint program, if industry programs are either not timely or not suf ficient, additional regulatory actions will be taken, as appropriate.
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NRCB 88 10 November 22, 1988 Page 3 of 7 The NRC regoested and received coments from the Nuclear Management and Resources Council (NUMRC), the National Electrical Manufacturers Association (NEMA), and the Underwriters Laboratories, Inc. (UL), during the preparation of this bulletin.            :
These conments were considered and some were appropriately incorporated into this bulletin.
NEMA has cornented to the NRC that determination of the critical performance characteristics of durability and short circuit capabilities of CBs requires destructive testing of selected breakers that are representative of CBs to be placed in service. Because a refurbished breaker may not have been refurbished under controlled conditions to conform to a proven design, destructively testing selected breakers will not infer anything about a refurbished CB.- UL            provided In addition, specific coments on ne tests in Attachment 1 of this bulletin.                                '
they stated that, 'it is UL's opinion that the test prograsa is not adequate to provide assurance that the tested, non traceable, circuit breakers would be suitable for their intended purpose." Although the test program described in Attachment 1 of this bulletin does not provide complete verification of_all the performance requirements and characteristics of molded-case CBs (such as seismicity or fault clearing capability), the hRC considers the test program to provide a reasonable assurance of performance requirements and characteristics most important to ensuring recctor safety. This, considered in conjunction with (1) the limited number of nonconforming CBs that may remain installed in safety-related systems following implementation of the actions requested by this bulletin, (2) the existence of redundant saft:ty-related systems in nuclear power reactors that are required by NRC regulations, (3) the license. required in-service testing of installed CBs perforried to demonstrate the CB's functional
_ performance, and (4) the low frequency of occurrence of seismic events and severe electrical faults, provides a reasonable assurance that nuclear power reactors can be operated without undue risk to the health and safety of the public.
The NRC investigation of this issue is not complete. A svpplement to this bulletin er.ay be issued to include other electrical equipment or a' longer pro-curement review period if warranted by the results of the ongoing evaluations or the results of testing requested in this bulletin.
Actions Rewested:
: 1. All addressees are requested to perform the following review by March 1.1989:
: a.      Identify all molded-case CBs purchased prior to August 1, 1988, that are being maintained as stored spares for safety-related (Class lE) applications or conraercial grade CBs that are being maintained as stored spares for future _use in safety-related applications; this includes CBs purchased from a CBK or from any other source. I( the
: f. umber of these stored spare CBS is'less than 50 at a nuclear plant site. then randomly select CBS purchased between August 1. 19P3 end August _l,1988 that have been installed in safety-related applica-tions as replacements or modifications to form a minimum saniple of 50 CBs per nuclear plant st_te.
q
 
NRCB 88-10 i                                                                                                                                                November 22, 1988 Page 4 of 7 I
: b.      Verify the tra4eability of these CBs.
+- !                            c.      Identify the number, manufacturer, model number, and to the extent 4
possible the procurement chain for all those CBs ide itified in (la) that cannot be traced to the CBM, For installed CBs also identify each system in which they are/were installed.
l                  2.      All holders of operating licenses who identify installed CBs per item 1 l                          above or item 4 below that cannot be traced to a CEM are requested to
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prepare, within 30 days of the completion of each item, an analysis justifying continued operatioh until items 1 through 5 of the actions j                          requested in this bulletin have been completed.
: 3.      All addressees who identify 80 percent or more CBs traceable to the CBM per item 1 above are requested to test the CBS that are not traceable to the CBM in accordance with the test program described in Attachment 1.
Any installed CBs that fail any of these tests should be replaced with I                            CBs that meet the criteria of item 7 of the actions requested or CBs
      !                          that pass all tests in accordance with the testing program described i                          in Attachment 1. If more than 10 percent of the CBs tested fall any of the tests described in Attachment 1, continue with item 41 otherwise, I                          proceed to item 6 of the actions requested.
Holders of operating licenses are requested to complete this testing program before startup from the first refueling outage beginning after March 1, 1989.
Holders of construction permits are requested to complete this testing program before fuel load.
4        All addressees who identify less than 80 percent of the CBs traceable to the CBM per item 1 above or who identify-a failure rate of more than 10 t                          percent for the CBs tested per item 3 above are requested to perform the j                          following actions:
l l                          4.      Identify all molded-case CBs that have been purchased between August 1.
        ,                                  1983 and August 1. 1988, and installed in safety-related applications j                                  as replacements or installed during modifications.
: b.      Verify the traceability of these CBs.
: c.      Identify the number, manufacturer, model number, system in which they are/were installed, and to the extent possible, the procurement chain-for all those CBs identified in (4a) that cannot be traced to the CBM.
i
: 5.      All addressees who identify installed CBs that cannot be traced to the CBM
          ;                        per item 4.above are requested to replace these CBs with components that reet the criteria'of item 7 of the actions requested or to test them in accordance with the program described in Attachment 1;'CBs that fail any-of .these tests should be replaced with CBs that: meet the criteria of item 7 of the acticas req'uested or CBS that pass all tests in accordance with the test program described in Attachnent 1.
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NRCB 88-10 November 22, 1988 Page 5 of 7 Holders of operating licenses are requested to replace or to test at least one-half, or all if the total number is less than 75, of these installed CBs before startup from the first refueling outage beginning after March 1, 1989. The remaining CBs should be replaced or tested before startup from the second refueling outage beginning after March 1, 1989.
Holders of construction permits are requested to replace or to test these installed CBs before fuel load.
: 6. Information generated while performing the actions requested in items 1, 2, 3, 4 and 5 above should be documented and maintained for a period of 5 years af ter the completion of all requested as.tions.
: 7. With the exception of actions taken in response to items 3 and 5 of the actions requested above, molded-case CBs installed in safety related ap-plications af ter August 1,1988 should be:
: a. Manufactured by and procured from a CBM under a 10 CFR 50, Appendix 3, program; or
: b. Procured from a CBM or others with verifiable traceability to the CBM, in compliance with applicable industry standards, and upgraded to safety-related by the licensee or others using an acceptable dedi-cation program. The NRC encourages addressees to significantly upgrade their dedication programs through a joint industry ef fort to ensure their adequacy and consistency. The NRC will monitor these industry initiatives and if they are not sufficient or not timely, or if prob-lems with the dedication of corrnercial grade equipnent for safety-related use continue, the NRC will take appropriate regulatory actions.
: 8. Addressees that cannot meet the schedule for the actions requested ibove and/or the corresponding reporting requirements below, should justi' / to the NRC their proposed alternative schedule.
Reporting Requirements:
: 1. All holders of operating licenses are required to provide a written report by April 1, 1989, that;
: a. Confirms that only molded-case CBs that meet the criteria of item 7 of the actions requested are being maintained as stored spares for future use in safety-related applications,
: b. Surparizes the total number, manufacturer, model number, and to the extent possible the procurement chain of those CBs that could not be traced to the CBM in items 1 and 4 of the actions requested. For installed CBs, also identify each system in which they are/were in-stalled,  if item 4 of the actions requested has not been completed i
 
4 NRCB 88 10 November 22, 1988 Page 6 of 7 by April 1,1989, due to the schedule for tests in item 3 of the actions requested, this infomation should be updated within 30 days of the completion of item 4 to address those-additional CBs that could not be traced to the CBM.
: c. Confims that items 1, 2, 3, 4, 5, 6 and 7 of the actions requested have been completed or will be implemented as requested.
: 2.      All holders of operating licenses are required to cubmit a report that sumarizes available results of tests conducted in accordance w!th items
;                  3 and 5 of the actions requested within 30 days after startup from the first and second refueling outages beginning after March 1 1989. For CDs that pass these tests, the only infomation reoutred is the number,
;                  manufacturer, model number, and to the extent possible the procurement-chain of (,Bs tested (sumary report fomat-is acceptable). For CBs.that fail these test (s), these reports should indicate the test (s) and'the values of test parameter (s) at which the failure (s) occurred, as well
=
as the corresponding manufacturer, model number, and to the extent'possible.:
the procurement chain.
: 3.      All holders of construction pemits are required to provide a written.
report by April 1, 1989, that:
: a. Confirms that only molded-case CBs that. meet the criteria of item 7 of the actions requested are being maintained as stored spares for future use in safety-related applications.                                      ,
: b. Sumarizes the total number, manufacturer, model number, and to the extent possible the procurement chain of those CBs that could not be-traced to the CBM in items 1 and's of the actions-requested.- For installed cps, also identify each system in which they are/were installed. .If item 4 of the actions requested has not been com--
pleted by April 1, 1989, due to the schedule >for tests in item 3              ,
of the actions _ requested, this infomation should be updated within-30 days of the completion of. item 4 to address those additional CBs
* that could not be traced to the CBM.-
: c. Confims that items-1, 3, 4, 5, 6 and 7 have been completed or will be implemented before fuel load.
: 4.      All holders of construction perutti are required to submit'a report that sumarizes the results of tests conducted in accordance with items 3 and 5-of the actions requested within 30 days after fuel load. For CBs that pass these tests, the only information required is the number.. manufacturer, model number, and to the extent possible, the procurement chain (sumary report format is acceptable). For CBs that fall these test (s)', the report-should indicate the test (s) and the values of test parameter (s) at'which.
the failure (s)- occurred, as well as the corresponding manufacturer, model number, and to the extent possible, the procurement chain-  ,
 
NRCB 88-10 November 22,1988 Page 7 of 7
:      The written reports required above shall be addressed to the U. S. Nuclear Regulatory Comission ATTH: Docurent Control Desk Washington, D.C. 20555, i      under oath or. affirmation under the provisions of Section 182a Atcnic Energy.
Act of 1954, as amended.      In addition, a copy shall be sutaitted to the ap-
  ,      propriate itegional Administrator.
  !      This request is covered by Office of Management and Budget Clearance Number j        3150-0011 which expires December 31, 1989. The estimated burden hour is 1000 '
to 10,000 man hours per plant response, including assessment of these require-
,      ments, searching data sources, testing, and analyzing the data, and preparing the required reports. Coments on the accuracy of this estimate and suggestions to reduce the burden may.be directed to the Of fice of Management and Budget, Room 3208, New Executive Of fice Building, Washington,- D.C., 20503. and to the U.S. Nuclear Regulatory Conmission, Records and Reports Management. Branch, Office of Administration and Resource Managccent. Washington, D.C., 20555. -
!        If you have any questions regarding this matter, please contact one of the
{        technical contacts. listed belcw or the Regional Administrator of the appropriate NRC regional office, l
t (YMh b Charles E, Rossi, Director Division of Operational Events Assessment Office of Huclear Reactor Regulation Technical Contacts: Paul Gill. NRR (301) 492-0811 Jaime Guillen NRR (301) 492-1170 Attachments:
: 1. Test Program for Molded Case Circuit Breakers
: 2. Definition of Tenns
: 3. 1.ist of Recently issued NRC Bulletins
 
t 4 -
t Attachment-1 NRCB 88-10 November 22,1988 Page 1 of 4 TEST PROGRAM FOR MOLDED-CASE circuli BREAKERS 1.0  Test Program Objectives The objective of this proposed. test program is to verify the-reli-abilityandcapabilitiesofmolded-casecircuitbreakers(CBs).
For the safety of personnel and others involved with the activities
* related to these proposed tests, appropriate safety practices, such as ANS!/NFPA 70E, " Electrical Safety Requirements for Employee Workplaces," Part !!, should be followed.
These proposed tests-have been based on tests described in industry standards, such as NEMA AB 1, " Molded-Case Circuit Breakers," NEMA-AB-2, "Proceduros for Field Inspection and Perfomance Verification of Molded-Case Circuit Breakers Used in Connercial and Industrial Applications," UL 489 " Molded Case Circuit Breakers and Circuit-Breaker Enclosures," and NETA STD ATS-1987, " National Electrical Testing Association, Acceptance Testing Specifications."
2.0  Test Procedu- as for CBS The following tests should be perfomed in the sequence listed. CBs failing any of these tests should be considered unacceptable-for safety-related applications.                                                                    ,
2.1  Mechanical Test t
The CB should be operated, reset, and closed a mintinum'of five times, to-ensure that the latching surfaces are free of any binding.
2.2  Individual Pole Resistance or Millivolt Drop Test (Ref. NETA STD- AT5-198TT NEMA AB-2)
The contact resistance of each pole of the CB should be measured ats ambient temperature. Three readings of_each-pole should'be taken                            3" with the __CB operated without load between each reading. The. average.
          .of-three readings for each pole should be. calculated-and compared with the manufacturer's contact resistance data"or_ with those values of similar CBs from'the-same manufacturer. ._ Also, the: average?value
          'for each pole ~should.be. compared with the average of'the other poles and the difference between the pole values should not exceed 50. '
percent of the lowest value;-or A millivolt _ drop test maylbe perfortned by applying a direct current; across the closed CB contacts and measuring the voltage;dropidue to                          a the' contact resistance. The millivolt drop test should be performed at room temperature. Direct current should be applied across each-
 
'                                                                                                                  l I
Attachment 1
                                                                                      - NRCB 88-10 November 22, 1988 Page 2 of 4 pole and the millivolt drop and test current recorded for each pole. .                              .
Three readings of each pole should be taken with the CB operated with-                              ,
out load between each reading. The average of the three re: dings for each pole should be calculated and compared with the manufacturer's
* value for acceptance of the breaker.
2.3  _ Rated Current Hold-In Test (Ref. NEMA AB A UL 489) i            This test should be conducted at 100% rated current and at an                                      '
  ,            ambient air temperature of 25'C i 3'C, and followed by a test at~
135% rated current and at an ambient temperature of 25'C 13'C.
Equal 100% rated currents should be applied to all poles of the CB.-
The CB must not trip within 1 hour for CBs rated 50 amperes or below '
or within 2 hours for CBs rated over 50 amperes during this test. At the end of the 100% rated current test. the current should be increased _
  !            to 135% and the CB should trip within 1 hour for CBs rated-50 amperes or below or within 2 hours for CBs rated over 50 amperes.
2.4  Overload Test (Ref. NEMA AB-1 & UL 489)
This test consists of one operating cycle (i.e., closing action followed by an opening action) of the CB at 600% rated current.
This test may be conducted at low voltage. There should be no electrical or mechanical breakdown of the CB during this test.
2.5  Instantaneous Trip Test (Ref. NERA AB-1 & UL 489) 2.5.1 Fixed Instartaneous Setting CBs Each pole of the CB should be tested for pickup of the. instantaneous unit. Each pole must be between 75% and 125% of the instantaneous trip rating. The trip time should.not exceed 0.1 seconds (6 cycles).
2.5.2 Adjustable instantaneous Setting CBs This test is the same as that in Section'2.5.1 except that each pole must be tested at the lowest and highest settings.-
The trip value for the lowest setting should be between 75% and 125%
of the lowest setting, and the highest' setting should be between 80%;
and 120% of the highest setting.
2.5.3 Short-Time Trip Setting Test This test is applicable only if the CB is equipped _with the short-time delay trip. This test should be conducted at an ambient-air temperature of 25'C t 3'C. The operation of the short-time delay unit should be within 90% and 125% of the overcurrent setting of-the CB as shown on the manufacturer's tine-current curves.-
                                                                                                                  +
 
(
Attachment 1-
                                                                              .NRCB 88                                                                                -November 22,,1988 Page 3 of 4                                            ,
2.6      Time Delay Overcurrent Trip (Ref. NEMA AB-2)
This test should be conducted at-an ambient air temperature off 25'C e 3'C.
A current of 300% (at low voltage) off the marked rating should be applied to each pole of the CB. The trip time for each pole-                                              '
should be compared with the time shown in the CB manufacturer's:
time-current curves. If the test trip times obtained for each pole                                          .g are not within the time band shown on the.CB manufacturer's time-                          ,                  .s current curves, then the test trip must not exceed the t,ime specified '                                    A e
in Table 1 and the acceptance-of the CBs must be evaluated with; thel                            -
criteria listed below TABLE 1 VALUES FOR OYMC'IRRENT 1 RIP TEST .      .
(AT 300% OF RATED CONTINUQU5 CURRENT OF CIRUu!T BREAKER)            '
                                                                                                                    '*-I (LIEF. NERA AB-2)
Breaker                            Range of Rated.                      . .
                                                                                                  .. l.                      :
Voltage                        Continuous. Current                  Maximum.TrippingL Amperes                        Time In- Seconds"                            p Volts _                                                                                                                p
                                                                                                                                '  H 240                                    15                                  501      N          '
240                                  50-100                                  !70s          .
600                                  .-15-45                                  -70L                  s a' 50-100-                                  125                  i 600 t
                -240                                  110-225                              3200                                    ;l 240                                  250 400-                                L300?
                '600                                  110-225                              $250                      4                q 600                                  250-400                                  300-600                                  450-600                                '350.
600-                                700-1200                                '500;                                  -
600                              1400-2500:                                  600i 600.                              3000 5000                                  L650 Minimum Tripping Time:        if the minimum trippingJtimesLare lower ~
than indicated by the manufacturer's': time-current curves for the!                            1:,
CD under. test, the' CB- should be- retested af ter~it has .been cooled' lto 2f'C                                                                      -the lf-the coordination      values and:
with upstream    obtained    areistill downstream      lower after CB should.be    evaluatretest.Ed.
If no problem with coordination is indicated. then the CB isiac -
ceptable.                                                        -
          ~
k
 
p Attachment 1 NRCB 08-10 November 22, 1988 Page 4 of 4 If the tripping time exceeds the maximum Maximum _ Tripping Timel                                                      ,
tripping time shown on the manufacturer's time-current curves but is below the time shown in Table 1, check the CB tine against the protection requirecents of the circuit'(such as cable, penetration, etc.) to ensure that the CB provides the protection, as well as the        l coordination with upstream and downstream CBs.. If the CB provides the necessary protection and coordination, then.the CB is acceptable..    .
Maximum Allowable Tine:  If the tripping time of the CB exceeds the TrTp~tTnTshTwn WTaETe 1, the breaker is unacceptable for Class 1E dpplications.                                                            j r
2.7  DielectricTests_{Ref.NEMAAB-1&UL-4891                                      j The dielectric test should be conducted at an ac test voltage of 1760    i volts (80% x [2 x rated voltage + 1000 volts)), or at 2500 volts de for 1 minute withstand. The dielectric test should be conducted for (1) line to load terminals with CB open, (2) line to line terminals        4 with CD closed, and (3) pole to ground with CB open, and (4) pole to ground with CB closed.
I
  .{.
 
L                                                                          -
Attachment 2 NRCB 88-10 November 22, 1982 DEFINIT 10NOFTERJH
_C_!_RCUIT BREAKER MANUFACTURER (CBM)
The ranufacturing facility that actually produced the circuit breaker being.                        >
pun ha sed.
                                                                                                                  ~
VERIFIABLE TRACEABILITY Documented evidence such as a certificate of compliance that establishes traceability of purchased equipment to the CBM. If the certificate of' compliance is provided by any party other than the CBM, the valid'.ty of such cortificate must be verified by the licensee or permit holder through an audit or other appropriate means.
DEDICATION PROCESS The process by which consnercial grade (non-Class IE) equipment is' upgraded-to safety-related (Class IE) and is thereby considered qualified for use in safety-related applications. The dedicution process must include:
: a. A technical evaluation to determine the characteristics critical to fulfilling the safety function (s).                                                        ;
: b. An acceptance process to ensure that those critical characteristics:
are met.
(:
                                                                                                                )
N
        \
                                                                            ..____.___._.______mm--_____ . - _
 
W                                                \ f id N Q f O l;;.1.f j [i W    l -l. %      > $$-l$
:.                            &j f[q        't, .                              ?
i
-        n                                                                                    Attachment 3'                >
h
)'                                                                                            NRCS 89-10 .                        ],
November 22. 1988              . !)
                                                                                                                                  }
LIST OF RECEN11.Y ISSUED                                            i NRC BULLETINS-                                            .b  1 f
                                                    ~
Bulletin                                                          Date_of                                    g, No.                            Subjact                            Issuance      Issued-to 88-05,                        Nonconfoming Faterials            8/3/88-      All holders of-Ols Supplemi.nt 2                  Supplied by Piping Supplici,                    or cps for~ nuclear Inc. at Folsom, Ncw Jersey                      power reactors.
and West Jersey Manufacturing Company at Williamstown, New Jersey-                                                                      ,
3-
{
88-08,                        Thermal Stresses'in Piping        '8/4/88        All holders of Cis                    '
Supplement 2                  Connected to Reactor Coolant                    or cps for lights Systems                                          water-cooled nuclear-power reactors.
88-09                          Thimble-Tube Thinning in            7/26/08      All holderssof Ols*      '
Westinghouse Reactors;                          or' cps ' Tor W-designed nuclear power reactors that utilize bottom mounted instrumentation.
88-08,                        Thermal Stresses in Piping          6/24/88    -All holders of Ols-Supplement l'                Connected to Reactor Coolant                      or cps for light-Systems                                          water-cooled nuclear power reactors, t
88                        Thermal Stresses in Piping'        6/22/88'      All holders of Ols                  ,
or cps for light-Connected to Reactor Coolant                                                    T Systems                                          water-cooled nuclear power reactors.-
88-05                          Nonconforming Materials            6/15/88
                                                                                              .All holders of Ols-
  ,            Supplement 1                  Supplied by Piping Supplies,                    or cps for nuclear
.                                            Inc. at Folsom, New Jersey                        power reactors.-
and West Jersey Manufacturing Company at Williamstown, New Jersey 88 07                          Power Oscillations in              6/15/88        All holders of Ols Boiling Water Reactors (BWRs)                    or cps for_BWRs..
OL'= Operating License CP = Construction Permit
 
s        .
MEMORANDUM FOR:        Thomas.T. Martin, Regional Administrator Region I FROM:                  Wil?iam T. Russell, Associate Director for Inspection and Technical Assessment                                                        '
Office of Nuclear Reactor Regulation
 
==SUBJECT:==
 
7 LLEGATION(RI-89-A-007 CIRCUITBREAKERS(MCCB)J2,ADJUSTMENTOFMOLDEDCASE Af SUSQUEHANNA We have reviewed your memorandum of July 3,1990, regardin9 the adjustments of molded. case circuit breakers (NCCB) at Susquehanna. . We agree that this activity is not prohibited by any NRC requirement. However, we also conclude that the reuse of a circuit breaker which nas been unsealed and adjusted without the manufacturer's approval and outside NEHA guidelines, and which has lost its UL approval-in the process, constitutes a modification to the facility subject to the provisions of 10 CFR 50.59. The unsealing and adjustment of a-molded case circuit breaker cannot be treated as a normal maintenance activity by licensees.. Additional discussion on the basis for concluding that such activities constitute modifications is included in Enclosure 1.
Since the unreviewed safety question tests included in 10 CFR S0.59 appear to be adequate and appropriate for control of this type of activity, we do not' intend to issue any additional guidance suggesting that such adjustments are either endorsed or prohibited. We would, of course,.be available to assist the Region in dealing with any specific technical issues where you chose to inspect a licensee's 10 CFR 50.59 evaluation.
Based on my staf f's discussions with you and your staff on August 9,1990, I                                                ,
understand that you are in agreenent with this approach. In addition I.
understand that your staff will review the circumstances surrounding the molded- sse circuit breaker adjustments at Susquehanna to assure that they were,        will be, handled as facility modifications subject to 10 CFR 50.59.
I believe that this approach and the factual information included in your memorandum wil,1 form the basis for- our resolution of the relatedOa legation.
(RI.89-A007j2)
ORENE SIGNED BT'                                            -
W. T. RUSSELL Nilliam T. Russell, Associate Director for Inspection and Technical Assessment
 
==Enclosure:==
As Stated cc:    See next page "SEE PREVIOUS CONCL'RRENCE n /
FC :SELB/ DST            MC75ELB/OST :BC/SELB/ DST :00/ DST                        :0/ DST
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  -ATE :8/ 1/90~            :8/ 1/90          :8/ 1/90          :8/10/90            :8//$/90          :8/q/90          -:
0FFICIAL RECORD COPY Document Name: MEMO MARTIN spo+iw 2 s h
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p=                                                                                          .,
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  ,y y
    "!      Thomas T. Hartin.          . -  August 13, 1990-cc:  B. Grimes, NRR-U. Pota>ovs, NRR
                                                                                = "                '
W. Brac1, NRR S. Varga,.HRR J. Lee,.NRR D. Letts, NRR                                                        "
R. Brady, NRR S. B. Ebneter, RII A. B. Davis, RI!!
R. D. Hartin, RIV J. B. Martin, RV                                                                ,
Distribution:'                                                                        l Central Files                                          4                        1 SELB Rdg.
NRC PDR P. Gill (PF)(2)
* J. E. Knight ~                                                              i F. Rosa.                                                              s      ;
_            G.-Holahan                          .
A, Thadani                                                              -
W. T. Russell J.:Sniezek-                                      .                                    -
F. Miraglia                                                          ,                .
F.;Gillespie-                                                      '
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4    a MEMORANDUM- FOR:- Thomas T.- Martin, Regional Administrator-Region I-FR0 -              William T. Russell, Associate Director for Inspection and Technical Assessment Office of Nuclear Reactor Regulation
 
==SUBJECT:==
 
k' ALLEGATION            (RI-89-A-0072)lADJUSTMENTOFMOLD RCUITBREAKERS(MCCB)'ATSUSQUEHANNA We have reviewe your nemorandum of July 3, 1990i-regarding the adjustments of molded-case circutt breakers (MCCD) at Susquehanna. We agree that this activity is tiot pry ibited by acy NRC requirement. However, we also conclude.
that the reuse of a ircuit breaker which has been unsealed and adjusted without the manufactut r's approval and outside NEMA guidelines, and which has lost its UL approval in the process, constitutes a modification to'the facility subject to the provision of 10 CFR 50.59. The unsealing and adjustment of a molded-case circuit breakt cannot be treated as'a normal maintenance activity by licensens. Additional          scussion on the basis for concluding-that such activities constitute modifi tions is included in Enclosure 1.
Since the unreviewed safety qu tion tests included in 10 CFR 50.59 appear be adequate and appropriate for control of this type of activity, we do not}o intend to issue any additional gu ance suggesting that such adjustments are either endorsed or prohibited. We ould, of course,,be available to assist the Region in decling with any spec ic technical issues where you chose to inspect a licensee's 10 CFR 50.59 eva untion.                                                .
Bosed on my staff's discussions with yo and your staff on August 9, 1990, I understand that you are in agreement wit this approach. In addition,-I understand that your staff will review thgcircumstances surrounding the-molded. case circuit breaker adjustments at were, or will be, handled as facility modif{usquehanna          to assure ations subject        that they to 10 CFR  50.59.
              .I believe that this approach and the factual nformation included in your memorandum will form the basis for our resolution of the relateQllegation-(RI-89.A007).
William T. Russel , Associate Director-for Irapection a d Technical Assessment
 
==Enclosure:==
As Stated cc:  B. Grimes, NRR              W. Brach, NRR U. Petapovs, f!RR          S. Varga, NRR D. Letts, t'RR              J. Lee 'MRR' R. Brady '.NRR-SEE PREVIOUS CONCURRENCE R :SELB/ DST A[
3
:SC/SELB/ DST :BC/SELB/ DST /:4D/ DST        :D/05T        :ADT/NRR      :
____:............:....__......:..___...... v..-..____....:............:...........            :.........
1AME :*PGill:en      :*JEKnight      .:*FRosa.      :GHolahan      :ACThadani    ;WTRussell    :
  -....:. ..........:..........__:..__... ..__:___e......__:_...........:. ..........:....__.,_
yPATE:8/1/90-            :8/ 1/90        :8/ 1/90      :8/jd/90      :0/ /90      :8/ /90      :
e            OFFICIAL RECORD COPY 1 --Document Name: MEMO MARTIN
 
T. T. Martin                                -2 NRC Bulle n 88 10 addressed this issue and it states "Since molded case CBs have facto      calibrated and scaled elements, any unauthorized modifications or refurbishing f these CBs could jeopardize their design capability and reliability."      It was the it, tent of Bulletin 88-10 to prohibit the unauthorized o>ening of MCCB in the field. During the development of the Bulletir. 88 10, t11s issue was di ussed and it ras concluded that suc5 utauthorized opening and adjustments ren *r MCCBs as having been modified and no longer provide the assurance of reliabi 'ty, capability and qualification of the original product as purchased from the , nufacturer. Also, in our view, in accordai,ce with 10 CFR 50.59, the use in' safety systems of MCCBs which have het, opened and adjusted in the field wcu        constitute an u1res iewed safety question. It is unlikely, based on the abov discussions, that an analysis performed per
:0 CF2 5b.59 would find use          such MCCBs acceptable.
Based on the above, we conclude hat there are sufficient technical and regulatory bast s for not condonin the unsealing of the MCCB in the field for the purposes of refurbishment, mod ication or trip adjustment whether or not it is performed under a utility qual'ty assurance program.- Therefore, I recommend that Region I take the appr riate actions to inform the Susquehahna licensee of the NRR decision on this m ter.
W. T. k ssell, Associate Director For Insp.ction & Technical Assessment cc:    B. Grimes, NRR W. Brach, NRR U. Potapovs, NRR S. 'larga D. Letts, NRR J. Lee, NRR R. Brady, NRR lFC    :SELB/ DST        :SC/5ELB/ DST :BC/SELB/ DST :DD/D3T        :D/ DST      :ADT/NRR    :
.....:.........f.:_______,.bp:FRosa.....gr'          ..:__.._____...:._______....: .. ___.____:_..._____
LAME    :PGill:cn        :JEKnighti                    :GHolahan    :ACThadani    :WTRussell  :
.....:........___.: _____        _J...:______  ..___:....... __..:............:.. __.......:... ___..
LATE :8/ / /90            :8///90      :8/ l /90      :8/    /90  :8/      /90  :8/  /90  :
0FFICIAL RECORD COPY Document Name: MEMO MARTIN
 
ENCLOSURE-The following items-indicate the-significant technical considerations relating to molded-case circuit breaker adjustment which lead us to conclude that it must be viewed as a facility modification rather than as normal plant-maintenance:
i
: 1. The manufacturers of MCCBs intertionallj seal the    trip units to prevent.'
any lieid adjustments hy unauthorized personnel to ensure that the design capability and reliability of the MCCB is not compromised. ' MCCBs have-
_ very critical internal components, clearances,- and adjustments, and therefore.a'high level of skill and detailed knowledge is< required when making such adjustments to the NCCBs.= Testing to' verify the functional.
capability of a breaker throughout its range of operation requires strict adherence to manufacturers' detailed test procedures. -In addition,.the test environment must be tightly controlled:and the ac current level and
                  -sinusoidal wave shape kept constant throughout the test.
: 2. Since the MCCBs are_ sealed units, any attempt to unseal them by using a soldering gun or other means may have deleterious effects on-the MCCBs.
There is a potential that the comercial compounds (lock-tite) used in the-field to lock the trip unit set screw in place after~ adjustment may' a migrate into the operating mechanism and prevent proper operation of the MCCB. Also, if the MCCBs are not_ reasser' bled correctly (i.e., installation ofninter-phase barriers and other components)_after they have been unsealed-in the field, catastrophic failure may occur under normal:or fault condi-tions 'due to lack of insulation integrity. We have discussed with the-manufacturer and industry standards representatives and they: corroborate the above stated: reasons for sealing the MCCBs.- This: is why the:manu-facturers of MCCBs strongly oppose the opening of sealed MCCBs in the-field.
: 3. Your-letterandtheRegionIinspectionrepor_t(50-387/388-90-22) indicate that_theSusquehannaSteam-ElectricStation's(SSES).licenseeperforms-adjustments of: sealed tr.ip units of MCCBs without manufacturer's specific-authorization or procedures. - In fact, the reason that the SSES_ licensee has no such authorization and procedures is:that the MCCB' manufacturers (or national standards making bodies for perfor;ning this activity) do not publish any procedures for user's use because of the difficulty in perform--
ing correctly such. activities outside a factory facility.'.
: 4. NRC Bulletin 88-10 states "Since molded case CBs have factory calibrated and scaled elements, any unauthorized modifications or refurbishing of            '
E              these CBs could. jeopardize their design capability and reliability." tit.
was the intent of Bulletin E8-10 to prchibit the unauthorized opening-of-MCC3s in the field. During the development'of the Bulletin 88-10, this-issue was discussed and it was concluded that such unauthorized cpening          <
and' adjustments render MCCBs as having been modified and requires that the licensee-reestablish the assurance of reliabliity, capability, an.c
                -qualification-of the original product as purchased frcm the manufacturer.
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                                                        . UNITED STATES :        .
        .[
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:()i            NUCLEAR REGULATORY COMMISSION:
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                                                  . ASHING    TON, D, C. 20566 -
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              .....                                                August-1361990                                                      t HEMORANDUM FOR: . Thomas.I.. Martin, Regional Administrator c grJegion I.      I FRCM:                                            Associate Director                                            .
                                - William  T. Russell,d
:for Inspection      an Technical: Assessment Office of Huclear Reactor Regulationt
 
==SUBJECT:==
ALLEGATION (RI-89-A-0072 ADJUSTMENT-0F MOLDEU CASE RCuli BREAKERS (MCC              T SUSQUEHANNA i
s            We have reviewed your memorandum of July 3,1990, regard ng Tlic adjustments of molded-case circuit breakers.(MCCB) at Susquehanna.. We agree 1that this activity-is not prohibited by any NRC requirement, However, we also ' conclude -
1i sealed and. adjusted .
tht.t the reuse of a circuit breaker which has                                                                    '*:
without the manufacturer's approval and outsid                          ,W      huidelines,andwhichhas                    ;
lost its UL approval in the process, constitut                      ._
dification to_the faclHty subject to the. provisions of 10 CFR 50.59. The unsealingiand adjustment of a                                            '
          . molded case circuit breaker cannot be treated as a. norma l(mait                        n enance ac vti ity by' licensees. Additional discussion on the basis for concluding'that such; activities constitute e difications is included in Enclosure'1.-                                                        :r Since' the .unreviewed safety- question tests. included in 10 CFR 50.59 appear to:
be adequate and appropriate for_ control of this type of activity,lwe-do not intend to issue any-additional guidance-suggesting:that such adjustments are either endorsed or prohibited.. We would, of course, be available to-assist                  -
the. Region-in dealing with any. specific technicaltissues where you choselto
          -inspect a' licensee's 10 CFR'50 59 evaluation..                            .
Based on my staff's discussions with you-and your-staff on- August 9,-1990,:1                              ~
understand that you are in. agreement with this approach.- -In addition, I~
understandithat.your: staff will review the circumstances surroundingTtheL i
                                                                                                                                .r molded-case circuit l breaker adjustments at Susquehanna to assure that they                                          ,
were,Jor will.be, handled as' f acility modifications subject to.10 CFR 50.59./
11 believe that this approach and the factual information included J your?
            . memorandum will form tie basis for our ' resolution of the related Lallegation; (RI-89-A00g a
du/ W William T. Russell, Associate Director-Efor Insoection and Technical: Assessment-
 
==Enclosure:==
-As Stated
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