ML20024B447

Forwards Reply to Notice of Noncompliance Dtd 800410. Denies Each Alleged Item of Noncompliance,However Proceedings Under 10CFR2.205 Would Be Time Consuming & Expensive.Check in Payment of Civil Penalties Encl

ML20024B447
Person / Time
Site:	Crane
Issue date:	05/20/1980
From:	Guilbert D BABCOCK & WILCOX CO.
To:	Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
TASK-*, TASK-GB GPU-0252, GPU-252, NUDOCS 8307080752
Download: ML20024B447 (19)

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P.o. 3:11250.tyn:.:w; va. 2305 Te s:. :ns:(act 254 5:11 1

May 20, 1980 l

i Mr. Victor Stello, Jr.

Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Co= mission Washington, D.C.

20555 Re:

Your. letter dated April 10, 1980 Dea.: Mr. Stello:

In accordance with 10 CFR 2.201, I an enclosing the Babcock and Wilcox Reply to the Notice"of Noncompliance which was attached as Appendix A to your letter referenced above, along with a statement of the actions which 3&W has taken to address the =atters raised in the Notice.

3&W denies each of the alleged items of noncompliance contained in the Notice of Noncomoliance.

Nevertheless, 3&W believes that proceedings under 10 CFR 2.205 would be time-consuming, expensive, and needlessly divert critical personnel and resources.

Accord-ingly, I an enclosing a check, in paymen for Items 2 and 3 oniv, for the total amount indicated in the Notice of ? o-posed Imposition of Civil Penalties.

Very truly yours, j.

/

D.E.

Guilber.

l Vice President and General Manager Nuclear Power Generation Division DIG /jck

(, @ U InClosures Ben. Ed.Rrin MA rit. 5.agg. W _

Charles ShaPif0 CSR eso7oso7s2 soosao gg PDR ADOCK 050002e9 Doyle ReportingInc.

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• 357

In accordance with 10 CFR 2.201 and the instru=nien.s contained in the NRC Notice of Ncnc==pliance dated April 10, t

1980, Babco=k & Wilcox (3&W) hereby files its v-itten state =e.:

or explanation in reply to each of the alleged ite=s of non-conpliance.

In what follows, B&W will:

1) ad it er deny each allege:. ites of noncomp_,iance, and 2) address actions w..nics have been or will be taken which are appropriate to the matters raised in the Notice.

I.

ADMISSION OR DENIAL B&W denies each of the four r11eged itens of'non-co=pliance.

EI.

ACTIONS The Notice of Nencompliance required that 3&W provide (3) the c.orrective steps which have been taken and the results achieved, (4) the corrective steps which will be taken to avoid further nonce =pliance, and (5) the date when full ec=pliance vill be achieved.

As noted previously, B&W does not believe that any nonec=pliance has occurred.

Nevertheless, 3&W hai previously instituted a series of actions and is ccatinuing to address nat'ers such as those raised by NRC in the Notice of Nonco=cliance.

Actions have been and will be taken which are:

1) gene-ic, and 2) appropriate to the specific natters reised in the Notice of Noncompliance.

In what follows the generic actions, as well as the specific actions taken which are a.:.crocriate to t.ne natters raisec in the No:1c e w:_,.'. be c.es= rime =.

A.

Generic Actions During the su=mer of 1979, 3&W initiated an intensive review of N?G-1707-01, 3&W's internal procedure fer the processing of safety concerns (PSC) which i=plements the requirements cf 10 CFR Part 21.

This review cu1=inated in he-issuance of l

Revisions 7 and 5 to NPC.-1707-01, dated Noverime 2C, 1979 and A=ril 1, 1980 rescectivelv, wn...len are ces gnec to :.nprove the

~over-all effe=:iveness of this procedure and =cre sha.rply define its pu pose and a:c. licability.

More specifically, these revisions l

will =rovide additional assurance ta.a any sare:y con==-" -= sec by 3&h e=ployees will be reported and processed in accordance with 3&W's Part 21 =.rocedures, regarc. ess c:. t.ne :c: n in vn:.=n :nese conce ns originally arise.

Tn.ese revas:.cns, inter a_,1a, spec:.:y the contents of any evaluations pursuant to.the PSC procedure and contain actien-forcing provisions which ensure tha ap:repriate follown: actions will be taken with respe=t to each safety concern l

which is reported.

Copies of these revisiens are enciesed as Attachnents 1 and 2.

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Further, on April 10, 1980, the.Mhnagers o' ell

' cognizant depart =ents within the B&W Nuclear Power Gt aratic Division (N?GD) issued Management Directive 205 T4.4 assigning i

priorities for the pr'ocessing of safety concernt within NPGO, establishing evaluation

'i-a limits, and insuring appropriate notification of customers with respect to safety concerns being processed by B&W.

The issuance of this management directive is a further step in the continuing co=mitment by B&W =anagement ro

=onitor the PSC process and insure that evaluations will be con-ducted and action taken in a timely manner.

A copy of this

=anac.e=ent directive is enclosed as Attachment 3.

on Dece=ber 12 and 14, 1979, the Licensing Section also conducted training sessions. for all NPGD E=ployees to re-e=phasize the purpose and scope of the PSC procedure, to explain the availability of this system for implementing safety concerns and to encourage the use of this procedure by all caployees.

These for=al training sessions, which included presentations by senior B&W management, will be supple =ented from time to tir.e by workshops on specific safety subjects.

Finally, the PSC syste=

bas been,. and will continue to be, audited on a regular basis by B&W Quality Assurance and licensing personnel and 3&W's utility customers, as well as the NRC, in order to continually monitor the perfor=a.nce of this system, measure cc:3pliance with the recuirements of Part 21, and make any additional revisions which may be necessary or ac.crocriate.

3.

Soecific Acticns Item 1 B&W has undertaken a series of actions designed to i= prove the capability of operators to manage transients.

Additional guidance designed to preclude operaters fro: in-terrupting high pressure safety injection in the event of a

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small break LOCA was promulgated by NRC and 3&W by April 4, 1979, following the TMI-2 incident.

B&W, in cooperatica cith NRC, then established special training proga=s for operaters dealing with this phenomenon.

3&W subsequently e= barked c an extensive re-analysis of s=all break LOCA's with emphasis on scenarios related to the TMI-2 sequence of events.

This effort enhanced the understanding within the industry and NRC of s=all break LOCA perfor=ance and resulted in the prc=ulgarien of a series of additional operating guidelines for small break LOCA's.

The operator response in connection with the Crystal River inciden; wculd suggest that these programs have been effective and that the operating guidelines for s=all break LOCA's have been successfully implemented at cperating plants.

The engeing review of the Crystal River incident resulted in NRC Staff recc =endations to reassess certain elements Of the small break guidelines, an endorsement of 3&W efforts to devel:p abncr=al transient cperating guidelines (ATO3), and a recc==en-dation of full utility support for the ATOG progra=.

These lenc.e. -ter= efforts should further impreve the capability of operatcrs to manage transients.

Item 2 j

This item is applicable only to Davis-3 esse.

An al)..:

i for small bre.ak LOCA's using an auxiliary feedwater (ATW) level control of 10 feet fer the Davis-3 esse plant were reviewed in Decamber of 1978.

This review led to the conclusica that such a conditien wocid not result in a significant departure in expected perfor=ance from the cases previously analyzed with 3&W's NRC-approved evaluation model (less than 2 0 *F. peak cladding ta=perature increase relative to the 32 foot case).

Subsequent analysis in B&W's May 7, 1979 submittal to NRC confirned 3&W's initial judgment that the 10 foot control level, co=bined with the high auxiliary feedwater injectica point at Davis-3 esse, was consistent with the heat transfer assumptien i

presented in the NRC-approved LOCA evaluation model.

i Item 3 An analysis of small break 'L'OCA's on 3&W plants with reactor coolant pu=ps. hng was performed during Januarf of 1979.

These analyses and subsequent analyses confirmed 3&W's initial judgment that the pu=ps running case would not represent a limiting or unacceptable case from the standpoint of peak cladding ta=perature.

IA should be noted that at the time that the alleecd

.:e= arose, t,ne basic assumption throughout the incastry and NRC was that the effects of small break LOCA's would be bounfed my the pu=ps-ofr case and that the pu=ps-off case was the appro,=riate case for analyses of smell break LOCA's.

In this

,nac been assumed that the pumps would either continue

regarc, ru.7.ning or re=ain off throughout the LOCA.

During the serine anc st:ner of 1979, B&W's extended analysis of small break L6CA resulted in the identification of system thermal hydraulic cenavic:

conditions which gave rise to a separate concern over interrt=: ion of reac:cr coolant pt=p operation in a time frame after initiazion c: a Lo T n, i s, in turn, was psomptly identified to the NRC and resulte:gA.

In generic requirements from NRC applicable to all ?WR's vnic are =esignec to insure that reactor coolan:==nes are triceed at tne outset of conditions which indicate a small'br'eak LOCA.

Iten 4 4

With the ccmpletion of the extensive small break LCCA analysis dccu=ented in 3&W's May 7, 1979 submittal to NRC (see Chapter 6 and the Appendix thereto),

3&W has c=nfirmed its initial judgmen that there are no outstanding issues raised in the "ichelson Report on small break LOCA's.

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'III.

CONCLU.9 ION B&W realizes that the effectiveness of any procedure 3

cesigne. to..centify, evaluate, and resolve safe:y concerns may i

be strcngly dependent upon management ec:=aitments and attitudes regarding such a procedure.

During the past year, B&W has taken a number of significant steps designed to further enhance empicyee awareness of this procedure.

S&W is corr.itted to improving the use of its procedure and encouraging individual employees to initiate the procedure whenever they feel it is appropriate te do so.

3&W agrees with the Staff that a company cannot ask fer un-evaluated. suspicions that an item is a safety matter.

In the conte.xt of Part 21, a company must, however, rely upon the jufg-ment, as.areness, and expertise of the individual engi:ieer te initially distinguish the undefined safety questica from the substantial safety hazard, and also assure that the quality of evaluations conducted by the company.is high.

The timeliness of evaluations warrants particular effort, and S&W has taken manage-l ment action to control and expedite the evaluation process.

As l

noted previously, 3&W has established-goals for continuous measure-ment of performance in evaluations.

Moreover, 3&W has increased

-le frequency of internal audits to reinforce the need for tir.ely evaluation and identify appropriate action.

3&W recognizes the importance of the ca.tters addressed in 1.he Notice of Nonco=pliance.

Needless to say, it has been pre-foundly influenced by the TMI experience.

From senior manage-

=ent ta the individual engineer, B&W and its employees continue to be ev _.itted to improving the safety of its product and lea:ning the lessons of TMI.

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,j PROCESSING OF SAFETY LvuCEF.NS i

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APPLIC'5 _ITY COMPLETE REVISION j

ALL HPG0 PERSCNNEL i

i II.

PURPOSE y

To provide an orderly and visible process for identifying, evaluating and initiating the resolution of safety concerns related to or affecting HPGD-supplied cc:nponer.ts, systems and services.

To assure compliance with HRC regulations (e.g.,10CFR21,10CFR50,* et:. ).

I!!,

EF.:ECTIVITY All safety concerns identified after the issue date of this procedure.

Safety concerns idantified prior to the issue date of this procedure may be processed in accordance with this procedure.

IV.

P.EFERENCES H?G-1703 Preparation and Processing of Internal Deficienef Report /

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Restraint Order / Corrective Action Request

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1715-Al Policy for Reporting of Defects and Noncompliance as Required by 100FR21 V.

FORMS PRO ~ESSED (See Forms Section Manual)

SWHP-20203 - Preliminary Report of Safety Concerns (PSC)

VI.

GE!!ERAI_

A.

If guidance in interpretation of the -following definition or other aspects of the procedure is needed, consult with Licensing.

3.

The gir.eral d,afinition of a safety concer.4 as used in this procedure is:

Any ite: which has been discovered during design", enclysis, fabricati n, ins:aiiation, testing, inspection, trainin;, and cperaticr.s activities of a nu: lear scxer plant and which has or c!y have safety implica:icns.

i C.

Reporting of safety concerns to the customer or the KRC is not required if MP3D Licensing has documented evidence that the enncern is adequately kn0wn to the affcc ed NPGD customers in the case of potential significan; deficiencies, or is accquately known to the NRC in the case of pc:entia'.

substantial safety hazards.

C.

Recurrence of a previously reported safety concern shall de reported as t

a ns.. safety ccncern.

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0..:e a PSC is isssed, the originatcr may rescind it by documentine the basis in a ceco to the fianager, Licensing, and atta:ning supportir.c c::u-cantation as necessary.

The originator's canager shall indicate c5nce -

rence on the remo.

Appropriate action shall be taken by the Manager, Licensing.

VII.

RESP 3.*:5ISILITIES FOR REPORTING All I!P3D 2rsonnel are responsible for originating form 3',1NP-20203 when the"v discover potential safety concerns that are suspected of falling within the definition given in Section VI.B. above.

VIII.

oROCEDURE Rcfer to fle.ichart, Exhibit A, for the procedure to process safety concerns.

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1.

All correspencence related to safety concerns shall reference file pein:

205/74.4 plus the PSC number.

2.

A safe y cor.cern that is fou'nd to duplicate the subject material of a previ-ously su' mitted concern shall he returned to the orioinator with explanation c

3 and ccpy of the previcusly submitteo safety concern.

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DIST?.15UTIO ::

.a Origleihter a

t kecords Center Manager, Quality.Arsurance Mantger, Licensing F.anager. Fiald Engineerir49 and Services Man ger, Generic Projects kanager, ir.tegration Manager, Engineering i'znager, Plant Design Manager, Safety Analysis Affactad Preject Panager(s)

Cther Affected Fersonnel, as, applicable

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4.

Evaluatiod Rapcrt chall contair., as a minimum, the follovring:

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Dascriativn cf cor.cern b.

Nov cor.cser us.s Giscovered c.

Analysis of safety conside-ations d.

Ecuipment and piants Lifectad e.

Reportability under 10CFR50.55(e) and/or 10CFR21 f.

Corrective actions, as applicable, taken or to be taken 5.

QA Manager's concurrence indicates that the applicable !!PGD organizations have participated in the evaluation and that an assessrent has been cade to determine if changes are needed to the QA Program recuirements de.g.,

increased number of QC Surveillance inspections, increased number cf ver.dcr audits, etc.).

Engineering F.anager's concurrence indicates that the e.'aiuz:icn repor; has been reviewed for accuracy with respect to:

a.

Components, systems, services and plants affected b.

!;1:ure of the cafect or failure to comply and evalut:icn of the safety concern C.

CerrP.C ive action

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(cont'd.)

6.

Follot,-up action is defined, for purposes of this procedure, as follous:

a.

To bring deficient items into conformity with recuirements b.

To identify causes for deficiency c.

To prevent recurrences of deficiency d.

To make such other investigations or analyses or take such other follcw-up acticns as are deemed necessary because of the repsated concern.

7.

The follow-ep action plan shall include as applicable:

Actions to be taken b.

Individuals o. organintions responsible c.

Senadule for ccgletion including milestenas d.

Decision points and alternete actions s

Funding source i

c 1

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Ne 11-20-79 Fage 6 (?.ev 7)

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f SIC 7J C'.

SuaJECT

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-1 ALL N.:JD PERSONNEL

'II.

FURPOSE To provide an orderly end visible process fer identifying, evaluat'n; and initiating tne rasolution of safety con: erns related to or afft:tir.; N?G.

supplied com;onents, systecu and services, To assure compliance with NRC regulations (e.g., 30CFR21, ICCFR50, etc.).

III.

EFFECTI V_I.T..Y All safaty concerns identified after the issue dits of this pro:coure.

Safety concerns identified prior to the issue care of this pro:edure may te processad in accordance with this procedure.

2 IV.

FEFERENCES.

.y l

,3.g NPG-1703 Preparation and Procetsin; cf Ir. ernai Leficiency Report /

Restraint Order / Corrective Action Request 4

V.

_F, EROS FROCES3ED (See Fer.:s Saction Panual)

S!!s?-20202 - Preliminary Report of Safety Ccnc. rns (P! )

VI:

GENERAL A.

If guidance in interpretation of the following definition er other aspects of the procedure is needed, consult with Licensing.

B.

The general definition of a safety concerr. as used in ; itis procedure is:

Any. item which has been discovered curir; design, ar.alysis, fabricati:n, installa:icn, testing, inspection, trainir.;, and opera-icns activi-iss of a nuclear pc.ter plant and which has or ray have safc ;. icpiicc-icns.

C.

Reporting of safety concerns to the sus;oter or the NR; is not repuired if NpGD Licensing has documented eviden:e that the con:ern is ade:vately kn:wn to the affected N?GD custcmers in the case of p::ential si;r.ificant deficiencies, or is adequately known o the NRC in :ne case of p :ential substantici safety hazards.

D.

Recurrence of a previously reported safs:y con:ern shall be reported as

...s'.

a new safety concern.

. : :2.

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e.

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VI.

GENERAL (cent'd)-

E. 'Once a PSC is issued, the originator may rescind it by dcccrenting the basis in a car.o to the Manager, Licensing, and attaching su perting dcc.-

mentation as necessary.

The originator's manager shall ir.dicate con:gr-rente en the meto.

Appropriate action shall be taken by the Manager, Licensing.

VII.

RESPO!!S!5ILITIES FOP. REPORTING All ::PGD personasl are responsible for originating form BkH?-20205 when the_.

discover potential ;afety concerns that are suscected of falling within the definitica given in Section VI.B. above.

V!?I.

PRCCED'i?.E

'Wefer to flowchart, Exhibit A, for the procedure T? process s.tfety concerns.

7 o

-END-I i

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I 31_:c_7; Fage 2 (Rev 7)

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s NOTES:

4 1

4 1.

Correspondence related to safety concerns shall reference fila poir.: 2:5/T4.4 plus the PSC number.

2.

A safety concern that is found to duplicate the subject raterial cf a creviously submitted concern shall be returned to the originator with explanati n and cocy of the previously sub=itted safety con:ern.

a 3.

DISTRIBUTIO:':

a Originator Records Center Manager, Quality Assurance l'.anager, Licensing 1

Managar, Field Engineering and Services F.anaaer, Genaric Projects Manager, Project Engineering

+

Man:ger, Engineering Manage'r, Plant Engineering

+

Manager Safety Analysis Affected Project Manager (s)

Other Affected Personnel, as. apolicable

-s s i

f 4.

Content af the evaluation report shall be in accordan:e with the follo.png:

s_. e.

.(a) The requirements of paragraph 21.21(b)(3) of 10CFR21 shali be f:li:wed if concern is reportable under Part 21; this for:at may aisc be fc'.lc.eed, as applicable, for con: erns reportable ender 10CFR50.55(e).

i (b)

For concerns that are not reportable under Part 21 or 50.55(e), the report shall contain the same type of inforcaticr. as ur. der (a), as applicable, and shall also include a discussion of the basis for i

i determining non-reportability to I;RC.

i Y

(c-)

For all reports, include-how the concern was dis: overed.

5.

QA Manager's concurrence indicates that the appl.icable I:FE3 or;anita:icns hhve parti:ipatad in the evaluation and that an assesster.t has been r2de to detercine if changes are needed to the QA Program recuirerer.ts (e.g.,

increased num:er of QC Surveillance inspections, in:rease: nur:er of ver. der l

audits,etc.).

Engineering Manager's ccacurrence indicates that the evaluttica rescrt has been reviewed for accuracy with respect to:

a.

Components, systems, services and plants affected.

b.

Nature of the defect or failure to cc ply and evaluaticr. cf the safe y i,. --

concern.

i, Ccrrective action.

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l'eatf tte-t te**e'e

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(cont'd.)

6.

Follow-up action is defined, for purposes of this procedure, as folicus:

To bring deficient items into conformity with requirements a.

b.

To identify causes for deficiency c.

To prevent recurrences of deficiency d.

To make such other investigations or analyses or take such other folicw-up actions as are deemed necessary because of the repor ed conterr..

7.

The follow-up action plan shall include as applicable:

a.

Actions P.o be taker, b.

Individuals or organizations responsible c.

Schedule for completion including milestones d.

Decision points and altarnate actions e.

Funding source f.

Specific description of actions or documentation tha; cefine cicscre of follow-up action.

The c6rrective actions recommended by the PSC evaluation report.

g.

e O

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1

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• 4 Engineering, Custc. car Service, Project Management N ~ 8 *

..J ar.d Quality Assurar.:e Personnel Manager, :spartments of Engineering. Custc=e-Service.

as 66s.

. Project ".ar.3;t.cer.t and Quali ty Assurance l

st.

Fi l e No. _0: _,,

All or Ref.

4 8

• I v bj.

Manaescent Directive - Assiennent of PSC Priorities, Date April 10,1330 Evaluatica Span Times, and Customer l'otification l

m...........................

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ANroved by:

Manager, Engineering Department 1-

\\ TA A. Ti

".Mr ;$. [.- %7 Jh ]1 Mar.ager, Custcmer Service Departr:'ent Manager, Project Management Department

1. Mb

[Ed.D Manager. Quality Assurance Department

/ &/.

m[ F /f,.

I /

Assiencent of PSC Priorit'v and Evaluation Times I.

Asolicability I

N inis Eirective applies to the Engineering, Custerer Service, Prcje:t

.i Management and Quality Assurance Departments.

11.

Purpos e To provide guidance regarding (1) priority of PSC work, (2) evalua icn time limits, (3) reports to management, and (4) customer n:tification re:uirement(

for PSC evaluation reports.

III.

Effectivi ty in'.s instruction shall apply to,all PSC's originated subse:;uent to the issue.

date of this directive.

Actitionally, felicy:-u:: to ensure ci:st::.er action as described in V-4 shall be effective for all PSC's being evaluated at the time this directive takes effect.

I V.

I ns t *uctie ns A.

Pri ori ties All PSC's will be assicned a pricrity by Licensin: folicwinc the front end caeting; the prior.ity will be indicated ir. tr.i front eni.ae:ine cinutes and will be reflected in ne evaivation s:hedule agreed u:ca.

Many factors can affect prioritics for PSC wer.;, but, as a cer.eral cuide:

PSC's affecting operating pian:s sh:uid be civen the nichesi :-icriiv of any werk within "TGD.-

..nere : nflicts de ci:;

s-..ein 75C'1.

n'i to t 10x;r.; crder cf precedcnce w; ii c.over:::

l k b the event a Prici-ity i S:

geror7.tes a T>rierity ' PS (er vi-e ve-9.).

tr.e re::cnsibit r.:: nager shali ass 19n the ne:esscry res: r:es tu c: +.2.c t:th cc:iv tics-wi nin the ;:rcscriced s:nscule.

t

/t. ;.

- s, Priority 1 - Operating Plant - High Prebability Event Priority 2 - Operating Plant - Low Probability Event j

Priority 3 - Plants Under Constructica B.. Evaluation Time Limits An evaluatica completica date will be established in the frcnt end meetings ' consistent Rith ' safety' significance.

These dates will be shown on the status reports.

A performance mansurement target has been established to cc plete 90t of the evaluatier. reports witnin the established dates.

Performance will be re:Orted against this target for PSC's filed after the effective date of this directive.

C.

Reoorts to Manec_ement The Licensing Section will maintain status records on all PSC's and will provide a conthly status report to the ab:ve Department Managers.

V.

Cus tor.er Notification The following actions will be taken to appropriately inform and involve our custo:ers in the PSC process.

x j

1.

Projec.t Management

• will transmit preliminary ?SC evaluation reports of PSC's affecting their plants where it is ir.dicated that the PSC is likely to be reportable.

2.

As appropriate, Project Management

• will transmit for informatien final evaluation reports for PSC's affecting their piants, includin; tnese that are determined to be not reportable under federal regulations.

3.

Licensing will recommend to Project Management

• cther co= unica:icns with customers regarding selected PSC's prior to c:: pie:ing the preliminary evalua tion.

This will involve cases where it is clear the issue is poten: icily quite significant in ter=s of evalua i:n effort, safe:y in-plications, or possible significant hardware cnangas.

4.

For PSC's where (a) operating plants are affe: ed, (b) a very significan safety issue is inveived, ano (c) custc=er a::ic.c is required, a date will be established, as agreed to between Licensic;, Projec:/5ervice Panagers, and cognizan: technical perscnnel, f:r re:eip of a cus oner cocnittent to take the required acticn.

If su:n c: mi en is n:: re-ceived, the tatter will be escalated to NPGD canagement for fellow-up.

5.

Notifications o cus:0mers of significant safe y issues on cpera-ing plants shall be addressed : the utility upper =anage. ent.

Service Manager for Operating Plants

-