ML20069F061

From kanterella
Jump to navigation Jump to search
Unresolved Safety Issues Summary.Data as of August 20,1982. (Aqua Book)
ML20069F061
Person / Time
Issue date: 09/30/1982
From:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
To:
References
NUREG-0606, NUREG-0606-V04-N03, NUREG-606, NUREG-606-V4-N3, NUDOCS 8209270450
Download: ML20069F061 (51)


Text

--._ha-*_

-ah..

m-*__-..

E 4

.4-Aa---.-m_s-m

-_aa

_a a_

m m

'I.

t 4

0 4

I I

i I

O O-W LDE 2

M 4

se P

'.T i

ss a

peg d

SQ td gN. 5 1'

=

1 3

o--gL

.y..

e

}O3,.NI-

,AQOO4"a

.2 p ass v,

t

,,J.

+.

- si

?w.

y

'~ 4 r

.L

. ;-j-2,j '

1

  • 1 g b

O,, a

l MUREG-0606 Vol. 4, No. 3 August 20,1982 UNRESOLVED SAFETY ISSUES

SUMMARY

AQUA BOOK Prepares for: OmCE OF RESOURCE MANAGEMENT Toe comu ssion WA$leNCTON,01 20555

/g w

I 1

l l

FOREWORD THE " UNRESOLVED SAFETY ISSUES *

SUMMARY

IS DESIGNED TO PROVIDE THE MANAGEMENT OF THE NUCLEAR REGUL ATORY COMMISSION WITH A GUARTERLY OVERVIEW OF THE PROGRESS AND PLANS FOR COMPLETION OF GENERIC 1ASRS ADDRESSTNG "UNRESOLV[D SAFETY 155UES* REPORTED TO CONGRESS PURSUANT TO SECTION 218 0F THE ENERGY RE0RGANIZATIDM ACT OF 1974 AS AMENDED.

THIS

SUMMARY

UTILI2ES DATA COLLECTED FROM THE OFFICE OF NUCLEAR REACTOR REGULATIDM. OFFICE OF NUCLEAR REGUL ATORY RESE ARCH, AND THE NATIONAL LABORATORIES AND IS PREPARED BY THE OFFICE OF RESOURCE MANAGEMENT.

THE DEFINITION OF WHAT CONSTITUTES COMPLETION OF AN UNRESOLVED SAFETY ISSUE TUSIT MAS RECENTLY BEEN EXPANDED TO INCLUDE iME IMPLEMENTATION OF THE TECHNICAL RESOLui!ON. THIS IS IN ACKNOW-LEDGEMENT OF THE FACT THAT REAL SAFETY BENEFITS OCCUR ONLY AFTER IME IMPLEMENTATION MAS TAEEN PLACE. IMPORTANT ELEMENTS OF THIS IMPLEMENTATION PHASE ARES 1

THF FROVISION OF A PUBLIC COMMENT PERIOD FOLLOWING iME ISSUANCE OF A DRAFT NUREO

.FPORT INCORPORATING TME STAFF'S TECHNICAL RESOLUTION FOLLDWED BY A DISCUS $10M AND DISPOSITION OF THE CofTTENTS RECEIVED IN A FINAL NUREG REPORT.

2.

THE PROVISION FOR INCORPORATION OF THE TECMMICAL RESOLUTION INTO THE NRC'S 2EGULATIONS.

STANDARD REVIEW PLAN REGULATORY GUIDES, OR OTHER NRC OFFICIAL GUICANCC OR REQUIREMENTS AS APPROPRIATE.

S.

THE PROVISION FOR APPLICAi!ON OF THE TECHNICAL RESOLUTION TO INDIVIDUAL CPERATING PL ANTS IN TKE FORM OF MARDWARE OR DESIGd CHANGES. TECHNICAL SPECIFICATION CHANGE. AND/OR CNANGE TO OPERATING PROCEDURES AS APPROPRIATE.

THE SCHEDULES IN THIS 500R INCLUDE A MILESTONE Af THE END OF EACM ACTION PL AN WNICM REPRESENTS THE IM!!!Ai!ON OF THE IMPLFMENTATION PROCESS 80iN WITN RESPECT TO INCORPORATION OF THE TECHNICAL RESOLUTION IN THE NRC OFFICIAL GUIDANCE OR REQUIREMENTS AND ALSO THE APPLICATI0M OF CMANGES TO INDIVIDUAL OPERATING PLANTS.

THE SCHEDULE FOR IMPLEMENTATION WILL NOT NORMattY SE INCLUDES IN y

THE TASR ACTION PLAN (S) FOR THE RESOLUTION OF A US! $1NCE IME NATURE AND EITENT OF THE ACTIdITIES NECESSARY 10 ACCOMPLI $N THE IMPLEMENT ATION CANNOT NORMALLY BE REASONASLY DETERMINED PRIOR TO THE DETERMINATION OF A TECHNICAL RESOLUTION. THE PROGRESS AND STATUS FOR IMPLEMENTATION OF UNRESOLVED SAFETY ISSUES FOR WhlCN A TECHNICAL RESOLUTION MAS BEEN COMPLETED ARE REPORTED SPECIFICALLY IN A SEPARATE TABLE PROVIDED IN THIS

SUMMARY

RARL RNIEL. CHIEF OF TME GENERIC ISSUES BRANCH. DIVI 410N OF SAFETY TECHNot00VINRR IS RESPONS!8tt FOR MANAGING THE CENERIC TASES INCLUDED IN TMIS

SUMMARY

TABLE OF CONTENTS PAGE NO.

TASK NO.

TASK MANAGER DESCRIPTION

\\

t-2

==

ASBREVIATIONS OVERVIEW 3-S 6-9 USI'S FOR WNICM TECNNICAL RESOLUTION IS COMPLETE 10-12 A-1 ALECK SERKtZ WATER NAMMER 13-14 A-3. A-4. A-S JACK STROSMIDER W. CE, AND $4W STEAM GENERATOR TUDE INTEGRITY IS-18 A-7 SYRON SIEGEL MARE I CONTAIMMENT LONG-TERM PROGRAM 19-29 A-tt RICNARD JOHNSON REACTOR VESSEL MATERIALS TOUGNMESS FRt.CTURE TOUCMMESS OF STEAM GENERATOR AND REACTOR COOLANT 21-22 A-12 RICNARD JOMMSON PUMP SUPPORTS 23 A-17 PAUL NORIAN (ACTING)

SYSTEMS INTERACTIONS IN NUCLEAR POWER FLANTS 24-26 A-39 TSUNG SU DETERMINATION OF SAFETY RELIEF vatVE (SEV) POOL DYNAMIC LOADS AND TEMPER ATURE LIMIIS FOR DWR CONT AIMMENTS 27-30 A-49 PATRICK SEAR $

SEISMIC DESIGN CRITERIA-SMORT TERM PROGRAM 31-32 A-43 ALECK SERKIZ CONTAINMENT EMERGENCY SUMP PERFORMANCE 33-34 A-44 PATRICK BARAN0WSKY STATION SLACK 0UT 35-37 A-4S ANOREW MARCNESE SMUTDOWN DECAY MEAT REMOVAL RE9UIREMENTS SEISMIC OUALIFICATION OF E90!PMENT IN OPERATING 38-49 A-46 PATRICE SEARS PLANTS 41-42 A*47 ANDREW SZUKIEWICZ SAFETY IMPLICATIONS OF CONTROL SYSTEMS NYDROGEN CONTROL ME ASURES AND EFFECTS OF NYDR00EN 43 A-48 CLIFFORD ANDERSON BURNS ON S AFETY ESUIPMENT 44-47 A-49 ROY WOOOS PRESSURIZED TMERMAL SNOCK

ABBREVIATIONS AAts Accident Analysis tranch (Former NRR Branch)

EEss Enverennente! Engineering trench. Olet elen Ass adelatstratten tranch. Tsalning and of Eng6neertog (NRR) g Adelaistratten Staff (IE)

EFPY Effective Fv11-Power Years ACs Alteraating Current Estos Edgerten. Germesssawson A erlee ACR$s Advisory Cemetttee en Reactor Safeguards EPs Emergency Preparedness ads assistant D6 rector EPRIs Electric Power Research Institute ADBs Analysis and Development leanch. Divlelen of EQ3s Egvepoent quellf6catten Branch. Divisten Reacter Safety Research (RES) ev Engineertag (NER)

~

AE9s accident Evaluat ten Branch. Olvisten of FINS financial Systems Integrat t en (NRR)

Fitte Frankita Institute Research Leberaterles AE00s office of the Analysts and Evaluatten of FSIs Flw6d Structure Interactlen Operattenal Data F$ ifs Full-Scale Test Factitty AIFs Atomic Industrial Forve FWs Feedwater APIS Actlen Plan Tracking System Gas goesciences Branch. Divisten of Engineering (MRR)

ARL:

Alden Research Laboratory GEs ceneral Electets 453:

Austilary Systees tranch. Olvision of gin:

Gener6c Isswes tranch. Divisten of Safety Systees integratten (NRR)

Technology Emet)

ASMEs American Sec6ety of Mechanical Engineers, MFggs Muean Facters Englatering Branch. Olvlelen ASIMs American Society of Testing Materials of Nealth. S6 t t ag and Maste Moot. (RES)

ATW$s Anticipated Trans ont Without Scree NFSs 06visten of Muman Facters Safety (NRR) 58Ws tabcock and Wilee. Company NSSTs Neavy Section Steel technelegy BMCS Brookhaven Nationas Conservatery 3C3Rs Instrweentatten and Centrol Branch.

SNLi Brookhaven Mattenal Laboratory Div6 ele.,of Facility Operatt ens (RES)

OOPS Balasce of Plant ICSBs Instrumentsteen and Centrol Systems Branch.

SWR Be616ag Water Reactee Diets 6en of Systems Integretten (NRR)

CE:

Ceebwstlen Engineerteg. Incorporated Its Office of Inspecteen and Enforcement CE9s Cheetcal Enq6 peering Branch. Dieteten of IEEEe lastitute of Electrical and Electronics Engineers Engineering (NWR)

INELs Idaho Nuclear Engineering Laboratory CFR Code of Federal Regulattens IEEPs Integrated Reliab616ty Evaluatten Progree CDs Condensatten Isoletten ISIS In-Service Inspeciten cps Constructlen Pero 64 LER:

Licenseo Event Report CPts Core Performance Branch. Olvlelen of LG3s Lleensing Guidance Branch. Divisten of Systems Integration (NRR)

Safety Technelegy (NRR)

CRs Centracter Report Ltte La rence L t wormere Laboratory CEGRs Comen ttee for Rowlees of Generle Requiremente LOCAs Less-of-Coolant Acc6 dent CSSs Containment Systems tranch. Divisten of LPPs toad Plant Program Systees Integratten (NRR)

LTPs Long fore Progree DCs Olrect Current LWRs Light-Water Reactee i

des Divisten of Engineering (MRR) -

Matt 1-!!!s Containment types fee Belling Water Reectors DF08 D6visten of Factitty Ooerattens (RES)

ME3 Mechanical Engineering granch.

DNFSs Divisten of Numan Facters Safety (MRR)

D6 vist en of Engineertog (NRR)

DNRS:

Decay Meat Remowat System MEggs Materials Engtmeertne Branch.

DLs 06visten of Licens6mg (NRR)

Otwisten of Engineer 6mg Technelegy (RE'll DCE U. S. Department of Energf MITs Massachusetts Institute of Techno3*gy DOR 8 Devlelen of Operating Reacters pysR S :

Metallurgy and Materials Branch.

(Former NRR Davtsten) 06 elst en of Reacter Safety Research (RES)

DRAs Olvleton of Risk Analysis (RES)

MSL3 Main Steen Line treak DSIs Olvisten of Systems Integratten (MRR)

MTEBs Materials Enq6aeereng Seanch. Olvleton DS$s Olvisten of Systees Safety es Enq6 peering ENRR)

(Former PRR D6 vist en)

MDEs Non-Destructtwo Enseinetten DSTs 06visten of Safety Technology (MRR)

MREPs Newtron Resonance Escape Probability Nav,al Resea,.rch La,boratoryReacterReg.iati.e insering NRLs E8 EnJercoment,anch. Enforcement and

,sR R s Of 6ce of s cies Ein EInvestigattens Staff (IE)

MSS Mwelear Stese System ECC Emergency Core Coeling MURE0s Nwetear Regulation 1

PROGRAM OVERVIEW PROJECTED DATES FOR ISSUING NRC STAFF REPORTS s

R.y. It) LPP - Lead Plant Program (2) LTP = Long Term Progree N/S - Met Scheduled USI MAY 21 1982 TITLE AGUA BCDK CultREMY REMARKS A-te Water Mammer August 1 1983 August 1 1983 NUREG/CR-2788 was lessed in July 1982. Devolereent of a technical findtags NURES is underwav. Thss MUREG ullt be used te develop receemenda% Ions to CR84 for resolution.

A-3, Stese Generater March 30. 1983 March 30. 9983 The draft MURES report has been reviewed by the A-4 Ivbe Integrity technical branches and

  • heir comments incorporated.

A-5.

The repeet is being prepared for management review and then tellt be leswed for pubtle comment. The NRC has formed e Task Force to prepara proposed requiremente.

A-7. Mark I Long Tore Supplement-Supplement-This issue is considered complete since the final Progree June 9 August. 1982 NUREG esas lesved July 1989 and eenfirmatory orders 1982 Septementing the findings in MURES 9661 were leaved on Janwary 13. 1981 for 22 operating State with Mark I containments. Meeeever. 94L has revieneed three confirmatory issues for an SER swpplement and issued a draft report for NRR review. The MRR supplement esas issued August, 1982.

A-II. Reactor vessel October 15. 1982 October 15. 1982 MUREG-0774 Rev. 9 was completed and subeltted Materlate for review.

This revisten addresses pubtle comments leughness received on the For Ceement report. assvance is espected in September 1982 thereby reselving this Unresolved Safety Issue.

3

s PROGRAM OVERVIEW PROJECTED DATES FOR ISSUING NRC STAFF REPORTS USI MAY 21 8942 11111 Atua RaDK Ct!RR EMY REMauS A-44. Statten Blackovt October IS. t985 Octobee 15. 1985 Technical Assistance Contracts with CRNL and Sandia have been issued. A reavest fee information en Olesen Generator reliab616ty was sent to a!!

Ilcensees 6n July 898ts responses from Alconsees have been received. Deafs centracter technical reports were prov6ded in May 1982.

A-45. Shutdown Decay September 30. 1985 October 30. 1985 A Task Actlen Plan was lesved en October 7. 1989 Heat removat and revised on June 2. 1982.

A techn6 cal assistance Requirements centract package was approved on April 9.

9982 and implemented with Sand 6a en May it. 1982.

A-46. Sele =6c evallff-May 9,

1985 May 1 1984 This program was redirected to be made compatibile cetten of tovip-e'Ith the favipment eva!6f6catten Program Plan.

The ment en Opera-final Task Action Plan has been lesved. Werk has ting Plants been init6ated en all tasks with all centracters well into their subtasks.

A-47. Safety Impilca.

M/S M/S A revised draft Task Attlen Plan was issued in tiens o f Centrol Apr61 1982 f ar staf f coneverence and approval.

Systems Management approval of the fast Actlen Plan is espected by Sept. 1982.

Technical Assistance' centracts have been establ6 shed with ORNL and INEl.

A-48. Hydrogen Centre!

M/S M/S A Task Manager has been selected. A draft Task Measures and Actten Plan was isswed on Apet! 2. 9982 for Nec comments.

Hydrogen Burns Werk has been suspended pending management decislen en Safety Equipment on the scope of the TAP.

A-49. Pressurt red May 30, 1983 N/S A-49 was designated by the Ce==tosten as an USI Thereat Shock

' en December 28. 1988 The Task Actlen Plan was approved and issued on March 26 1982.

The draft short term positica is under preparatten and ullt be completed in September 1982.

5

USI'S FOR WHICH TECHNICAL RESOLUTION IS COMPLETE IMPLEMENTATION i

TASE MANAGER #

USI TITLE DATE C0FFLETED REPOR11 PUBLISMED IMPLEMENTATION STATUS TELEPHONE A-7.

MARE I LONG TERM JULY 1988 NUREG-9661 t!CENSEES ARE IN THE PROCESS OF SYRON SIEGEL PROGRAM AUGUSI 1982 NUREG-9661. SUPPt. DESIGNING AND INSTALLING MODIFICATIONS 492-TS34 No. 1 10 MEET TME COMMISSION'S ORDER DATE FOR EACM OPERATING PLANT.

INE LICENSEES ARE IN INE PROCESS OF PREPARING PLANT-UNIOUE ANALYSIS FOR SUSMITIAL 10 THE STAFF FOR POST IMPLEMENT 4ft0N AUDIT REVIEW FOR COMPLIANCE WIIM THE ACCEPTANCE CRITERIA CONTAINED IN APPENDIX A TO MUREG-0461.

THREE LICENSEES / APPLICANTS NAVE SUBMITTED TMEIR PLANT UNIGUE ANALYSIS TO DATE.

,NUREG-A-5, MARE II CONTAINMENT AUGUST 1981 NUREG-8804 THE RE9UIREMENTS R!ro,fTTEE POOL DYNAMIC LOADS 3898 ARE DEING IMPLErt r se!NG THE OPERATING LICENSE REVIEW PC EACM PLANT WITN A MARE II CONTAINMENT. THESE REQUIREMENTS WILL ALSO DE INCLUDED AS AN ADDITION 10 THE APPROPRIATE SECTION OF THE ST ANDARD REVIEW PL AN.

A-9.

ATWS SEPT. 1989 NUREG $448.

TWO VERSIONS OF THE PROPOSED ATMS DAv!D FYATT. RES VOL. 4 IUtt NAVE BEEN ISSUED FOR COMMENT 8 445-$960 46FRSTS25 THE STAFF VERSION AND AN ALTERNAit VERSION OF THE RULE PREPARED AT THE DIRECTION OF CCMMISSIONER NENDRIE.

FOLLOWING THE ComENT PERIOD AND CONSIDERATION OF PUOLIC COMMENTS. A FINAL RULE WILL SE PREPARED FOR CoPrtISSION CONSIDERATION. A TASK FORCE MAS DEEN ASSIGNED TO FORM A SASIS FOR THE FINAL RULE.

7

USI'S FOR WHICH TECHNICAL RESOLUTION IS COMPLETE 1

1 1

i IMPLtMtNIAt:04 iAst MaNActPr u$t IHLE Mir cOMPittE0 pJr_pgr$ runnLNig gQggCQgg giggE A-St.

RES10UAL NEAT 1978 NO FCRMAL RFPORT RREC APPROvt0 IMPttf*tNTATION PLAN TOM Novat RLMOVAL REQUIREMENTS SRP S.4.7 RivlSION JfMUARY 39 9978.

IPPL E ME NI AllON 492-78t7 FOR OPERAf!NG REACT 0RS NOT COMPLE1E.

A-34.

CONTROL OF NtavY JULY 1989 NUREG-9412 IFetEMPNTAttr4 Rt9UIREMrNTS WERE SUD RftUA LOADS NEAR SPENT ISSUED TO ALL LICENSELS BY tEITER 492-787F FUEL DATED DFCEMBER 22. 1918.

INE LEtitt REQUElitDs INTERIM Act!ONS TO SE C&MPLEttD IN 90 0Av5. A FN ASE I r'

ACI!ON EREFORI. CONFIRMATION AND JUSTIFICalION) IN $1N ff0NINS ANO PNASE II (SPECIFIC RE9U18tMfM113 IN MINE MONIHS. MOSI LICENSEES Nave RESPONDED 10 INE DECEM9EP 22. 8988 GENERIC tfl1ER AND INEIR StSPON5ES ARE REING EvatD41tD. ABOUt NINE PLANil NAVE REQUES1ED EXIENSIONS TO INE SEPIEneER 22, 1989 RESPONSE Catt.

SEVERAL PLANTS NAVE NOT TET Act1UATELY RESPONCED 80 THE EXTENT INAT AN EVALUAI104 MAY BE COTLt1ED.

A-42.

PIPE CRACRS IN JULY 1989 NUttG-tSt3 REV. 1 IN FttPUARY 1989. NUff0-8313. Rfv. t'al DICE CLA#g s

SOILING WATER ISSUED to Att NotDFRS OF WWW OPERATING 492-7962 REACIORS LICFNSES OR CONSTRUCl!ON PERM 115 AND TO ALL APPLICANTS FOR OPERATING LICENSfS, ST JULY 9

1989 THE APPLICANTS /tICfMSEfS Witt to PPOVICE THEIR PROGRAM FOR REPLACEMENT OF SERVICE SENSITITIVE t!NES AND WELDS. THEtt PROGRap (CR AUCMENIED INSERV!CE INSPECTION.

THFIR PROGRAM FOR IMPROVING INE HATER CNEMISTRY tuv!RONMENT AND INCCPORAIION OF ADt0UATE LEAR DEffCTION CAPAA!!!IV. ALL LICENSEES But ONE NAVE RESPONDED AND TNf!R REPLitS ARE BEING EVALUAi(D OT A TECNNICAL SUPPORT CONTR ACIOR (INEL).

INI1!81 IER'S ARE SCNfDULED 80 9t CcMrtEffD IN ThE FIRSI AND SECOND OU AR T ERS OF FY83.

9

"h WATER HAMMER (A-1) s out...

-____,___e>_______=._..

.. =... =.,,

__.e c

i

..t

.;.-.,4

@~."

u t, _ = _ ',

= =..

i

... ___, g_ =.-

, ~. -4 g
=

45 u--------,,,,,,Q.,..

~

t.va,t,u,ar10N W

=

.m.e, g,g x.

a -.

'--- -= - - --- -- - - - $ >

.. e sveurs amo

'=E=

==

  • yy[ '

~ ~_'~2--------Q w---

~ ' ~ ~

".ESMUMS

===_-

. ~%

~~~

_ _ _ _ :::Q~g _ " _ _ _- o

~~ ~

~ _ = =

=a i.

r-- : -- - -- _ 4 7'

. S, w-

~~

O.* 9 3T Co s oe B 3.WT

.n

.g

" Uuv e-=.=.

N e.nwey,f c

m.

es s sue g

es e. ar? D

  • ~.-3 es ssagg

.o 9,%g, n

g y

.~

M 11

1 1

l WATER HAMMER (A-1) Continued l

g g

g g - g _

-=

= = =,.

e.,.,.,-

. m.n.

===_,==a, c

mm.w c

=

e -,,, m ca.a en nom

.g y

g g

g TASK 1 REPORTS TASK 4.1 REPORT TASK 4 4 REPORTS smo n L a. a,

e e. -

% a t.,...t.-e e e.n

.e a.=m. ens Sosseum GCo.Ramsemme hem e. Aeon.e f.hg M wendus m ng U"IOM h 8"MF #4 penessem stem sesmu,se.Summe m desseum Pienet s,e eeveesymmenen e

esamese a s he g m go. #a>=es,997B Imesnum met. CAAP a e3 fnom. 39. T

,99 o

Ass.CAAP,L *Weseus etmuume 9. seat" 9 6. Guerem ChaumustA a.s3 taan se e *aet s'espasm see metC Umst w D u,*ae ^ _

h se poem.mg -

TW O RWM ps.e.er.tt.et 3en.e, wa. -m._ e

-.&.sessed 8 hen, ggp-

+ Amme end

.s..

~

. c.

s,,e.e,s s.

enes m stet.

Desmem.af Heems seemsuur.* gem. emen ee===,979 EPsameses te e88tC es 9 team.=we.ef Camugus4Russ.e Deudet F EL.*A. ^. sea e=-

n.neaasas.

of th WE A F 444. Asse 9973 % to kfbC Uump Febsmay asmes West

. TASK 2 REPORT TASK 4.3 REPORT

,,,,4.%,,,,%,_

L. ; 74.W,';;- g-v,,**

.-.u--e.

...e..

-=u=====

se

e. - % -. -

-,,; - =-- -

-.C-TASK 4 5 REPORT e..,........

.e 12

i li!!illier

$$388e8s,

9 j$b

!!!!!!!Q i",j g

5 11111l i

!!!!!!!6 l 93

=

e Ilil.n.

l11 2

li'

,_____________.7.__

,l q)

E lii!!"ll!!!!!!(

ill

=

l ijg

!9:

i!!!!!*i'!!!

iiiii!!!v' l i!!

=

,,,,!, v

'lllhs,il I

E kjy!!!N l

$ '._gl glii.

giist

!.!E!!lil i

a::::

l ' "

i,j "nii a*!!!o 1

I'ff

)bg :!

it

[

q i!,'I

!jil:

jj l. I *jp i

i lI a[jk

".j s.,

~' !!k9!,l

!!!!!h!!h!!!@

!9?

l b Ti

y!!!, ![i!!,'I,Fl !!,>:,l!!i lll in 19iillil i!

l iw

, 4,~ m j;!j li)i, i

til q

m l

,g lii j

l 10 till t!!!lin!'

,ilj q:l.s!liill9-- t, t -

j9) 8 lill e

,rg-L 11 1 ill ill "ll e

e e

d>

llh a

>Il l

f o

e e

Ili!!!!!T

?

n i!,

!! Ilk-!!!

I[

'I

)

o.

il l

338 l /I j, fl

[->

vil 3

E is.

p___________

3 I

l l

8 ili 5

y,,ip i !i

!,i ;

11;,

i 19 d

I

~~I!F;%11llI!illi!lIh ili l

! t y-- :.!

ijj,ii I O e e l

i f, i!.IaillE I

.,1 l

8 ll ili a

\\1, inf F---

iIII.it si

! b

!! G !!

I j!!

I

,iT I,,i[i I l

ljlI!!e i

l il i

i II

ik_,

le u

,o i

~<=-....

..<,o oo.

/

e

MARK I CONTAINMENT LONG-TERM PROGRAM (A-7)

Page 3 au c

f o

. : _._ - ---.i g_

_ j_,,_a,y_

L<~

=.... a yfN

@- ' E-N T

7 8 g R gn==='e==T "ll 4" :==;=====" CLv4==~.:.

l--- g.m.

5 a g' g

=:-
=
= ~..

i N

NTEH

,h""',,,

2~

i an!

_.I AAI i

LLN e

t zu G

l ta

REACTOR VESSEL MATERIALS TOUGHNESS (A-11)

=-

_=

=*

. = _ _ ~ _ = =,

g O.'

=:

= ::

"g_- ~*"'*

Q a~a ~-~3 Q

';33 % --,. - L';~a:

a a i

l

^

.=- l 0.

I

~..

.=

=

=_ = 9== = : g ___ _ q _q

==

_ =.

_ = =_ 3 _ =..=_. 3 _ =_ _.___ Q. i _ - _._.

y.._

i

_ = =

=_ 6_

=_

-r E=_.4 O"4

= 5:.E= E

~

= _ _ _

o, ___=_-

c,s_ __ __-_ -_ _ o, _ =_ _=_ =3p_.x

{

..l __

.:=. l t

i.l.

.=..

- =

g

____.9:_=.g.q, e

=..i

(

_g-f

=.:.-.

g

= = =_-*=_==_

=g -- - - - _

=..

=-

g__--

,g=__

_n

.e

= -- -

4J 3

l

=::::

gi.a. _-

p 4s

$. Jus g

Q Q

  • ~

88

FRACTURE TOUGHNESS OF STEAM GENERATOR AND REACTOR COOLANT PUt.7' SUPPORTS (A-12)

=-

=-

u.

. _. =

=. _

=

= =-

= ::

(:) 5:,~.4E_59 4= @=EE-4 5:4EE-@E4- _=::E__.G-g

.3. 14 v.~.y

. = =.

- - m. ::,..,

._..:::.:.:.a := fi!!..N v _ = _ e __.= __ 4 : = q _s m _.e g -

e _,e

sm -.(3 n

i d.

SYSTEMS INTERACTIONS IN NUCLEAR POWER PLANTS (A-17)

.S o,

,N.

KEY PERSONNEL TASK REVIEWERS SCHEDULED COtpPLETION TASK MANAGER NAME BRANCH ma mwean w w.or tgyg ANNygt REPORT

[g 7%

.o massa.co esv s.e ns CURRENT MPA ANALYST a t taan.se maise

  • PROSLEM DESCRIPTION

. TECHNICAL ASS; STANCE CONTRACTS

. POTENTtAL PRO 98. EMS

.D vm*.=.=-===.

s-

.m n.

. = =.

m m-

. 7

=..w.,em.

,n

. oso a

..r.

e.

smsm. a..e

....m P

Th t.

m ac R.M.h y.p n

y a.

n.

    • **""*"*"O.;,"".*.'".

+ STATUS

SUMMARY

=

m.

va A 17

.e ek.a r t g.

m 9tk A s

q:g

m..,h.

_. ca

==

. 4

3. W t.

.g.

eea=

s._

= = -

rsT m

.v 6

. e c.%. as e

v.

v=. a

.e W M

.h.-.w'.

.""."."*.T.1"'O*".".".*."".*""

'""" 7.'.'**

. ACRS (NTERFACE INFORMATION sein n:o. crwernacrose oeucarto awren.oto s.

==

.m "E

3 E d

.N. ".

e.m_cm,.

n.

sesses.

  • "c"***"*"**T S

9..W---~_

S 4E9 A

A

. 9.

m

.p m

a a.t 4

g Dc e.J e3 3. S.

A.SW C

9 t

a.

t gg y

..m gg.g.,.,g ge g

355

~.

...c.m..

9v

.f. - r _

3e m 9M M

.43 T M4.D.R.

40 p p

1D

. 4SI.5T em.g g

u. ^

4 f.t.

I

^

N

../W1.

O.CA.g 3 A L.sA G4 09.A..O.

D 9

r i

DETERMINATION OF SAFETY RELIEF VALVE (SRV) POOL DYNAMIC LOADS AND TEMPERATURE LIMITS FOR BWR CONTAINMENT (A-39)

= = '

~,

" 'l:::::rn'th,0 EE~--G IC - CC=

=A 4.

e

=- e g.

AW Moded ro

=.

=p e

=.,..g.

4.'

==

= =

.=..

,p__.--

__q

~a p.

M umm W. tes.

F W

Q

~-~

gp

.:= -
  • A'-
=

==

g T. - h _. g

="ra.'. g

,= g

=-r.

Ch em m 25

R DETERMINATION OF SAFETY RELIEF VALVE (SRV) POOL DYNAMICS LOADS AND TEMPERATURE LIMITS FOR BWR CONTAINMENT (A-39) Continued

==

= -.

~ T5+.

HF

  • =iv sa-i-. s7 9
r;=h.

e

=_

4_____,:2.-~

4

. = - - - -

  • ~~

.15E2~.-5". -=.::.= E9 ::

., ;;',.:=l '.%~

  • g,,_T,,,@

T g'.~

4_-

g- _ _ _ :3 *""_
g a---J'g,*

emv voor T.=,.r.iu Liaisi SS S.

T3

.ese,.

gsg 91

.5

~ ay-e

-~ 4_

==

q"" --


.q gun esas men eu.a.es

-, v,

//

s','/

/ /

/

s g

___q________________.-

,e,e

,v -,,

,/

/

/

/

=:-

/

/

=.

g.,_.:; _ _ 4.

g f

x---

~

/

. x wu s. e, g_ =_ T

9. _ _ - _.-

--._. -_ - -._ -_m

/

~ - - ~. * *e g :""

....e,*"'" ""*"J E==. " O'"

....m

.r>

, us =

w.

fC ts.

l

=

l l

l l

i

/

e

4

,)

5 e

i c

a N

\\

" y i

k P

r 4

SEISMIC DESIGN CRITER:A - SHORT TERM PROGRAM (A-40)

Phase 1 i

g E=.-.

. E3=E'=...

_.T.

3g ~,

gi - -

=- --- E ~[' =:"


= S _'~ G g

- - -- _ --e._ = - - 2

-4 yg l

i

~

t e

p -.- -

..s L,,..-__ _ _=-4 e

@_J

=--

...... =_:-

=.. _. -

~.

1 g.= _g- - - - - s=__ m_ =....

=..

.=.

=.

g -- 4 _.-. y i

j.__..

i

..___ s__i

,__ 6, J L *--

=:: :-

y2_ e__=__e_: _ e _ - _

- ='.=*

_g---_,.e'"

q m n.g.,,...

=

  • ".= =

l

._ 1

h Task 4 Doested ea y

SEISMIC DESIGN CRITERIA - SHORT TERM PROGRAM (A-40)

, _.

M 0

E:~d ~-

~

~*

~~

~

1., g___-._ _ q _-- -

. _ -,,. -+=..::-

~~

7,.

ll

,,7

== -1 n _..

l =-- -.

s --

i

__.e_ _ i l

J 1

1 1

,_,:lll...

i "O:7.r.:::

"O 10:::.T-

  • O
-~2"
"~A 1 m g ""
@,1 7 "**** : ^ " **
^

- - q -- AM

=".7

:::.W.

j a

"."=._. t,"-*-

\\!

!;',1 n

P )3 M4 UA g

S(

E g

Y C CN N

-giii -

A E

GM 7,' g RR g.

EO gr,,3

.-,t MF E R m.n.g e._.

=

E TP

=

N

~

_ c.

e

_ u.,:

E

,,;, s.g

~

w M

,if l

4

_I,..'E"3"g___-

N e

A

.e.

I

_g..

_g e

T0 o

N.m C-

=:

7_...'-

Oo

,s

_= _.g g _,;;n.

_n

, :4_ __,= 9_

De

_ e Eq t ^V.,.

= n

. ^

I

.=__=g

=

.=

_ =.

{-

e

. =. n

_,_ __=_ =_ g = _.... i ong. ===4.:

_*".._==__:_=m

_.n..

...ov s

=

o s

o.

x ~.

t n

5

_ n. -

i,-

.s-

. =__

h; E

~:: __

_.2,v E _

=_

.. = _

s_ =. = ~

4_ 7q_ t+(= @

g f:nO,.

=>

a.

=q. )_4_m.. >

.d

=

i

. =.

.n

.e s

_. =

.. 4 d

.=

. _ p_ __ =

=_ =-

.e

,e...._.

.o

= _

=q:nq_.:,.n'..-.e._

s

.. e

.O'.

n 3

e e

n.ev b

H.

e e

~

R

.m L

~ e. _ _

W

= _ _

. =

.=_

E__

l a.O.

.-~:

.Q.rm.

.@a

.g g

. F b

u. ~

a

- "=

.

=-

= ~.

g

=

=.

lltl i.

1 l

I

i STATION BLACKOUT (A-44)

-s

'1%*.7

.n mc sea a

l

.=

= - -

==.

, ";"' T =;='

- =~,_-_4=,vg=,,4

=~ Q ~ q -

4._.E_."dp.[.

~

25 = _. =E. -.=i g

s.

V.

_,:=

l l

""~';

=
=

w,,,,,,,,,,,,EAG:,"2,T,'2,'%,,g

- _../

~'

Cmaseuse

.msgg u t r of e m837 ep 3s.syrg g, g gy, g

.. =_

2" "' c et sytg" a=,,,,"== :::l-

  • ":::". n ga,a a * =

..,,,,,=, ===

y -

e e

e

,e re 3-s re

,e e

e%,e :: '"'

c e

e 34

5K Wg

)

4R L

AO 3

\\

S W

(

S T T E N N m.

E p

M Y

.o R

=

E g

RA

=

g s

N I

UI o

g QM f,

EI Wq g

L R E f-LR

,?=y::=.

4 4

n AP 2

It.

V 1

1 1

r. _- _; _,,

O s

9

. m a-

.e

~

. ne

~

M

,a C'-

2

,m I

3, M

. e h

u _

.e-E

^

.s R

^9 s,

,w^

.s 8e eh T

t

,,8#

fo*

m 3

,4 1

=*

3 A

9 r

,s E

H

~I h

I s

,', g e.

me Y

e-n m-s A '~

e

.=

.tte~

A a

8

.e.

s

  • O" C

a E

2&m.

m 1

.g,g D

5 6

3 g

g 2

,9 N

g g

se W

es *

,e m

Y p

s e

e g

e e

e g

.m O

t.

, W _a- -.-

cN es

.a v

s v.

s D

M T

.s

  1. @p m.e, EW&.

C, E,

m' I

.=

3 e

.7 U

s

.E.

o H

m htA

.~,e, s

M m

S 8e"

e r

ae

,e M e-nM r

e t

7, e,.

ee k

se

,C F

a m.

,,M e

a m

t

,e.

V M

.s 2

-h h

g g

c

~l e

m

==

m e

~

~

W~

~

e, s

c

..- s

~

.e e

e

=

.m s

e 1l;Ill.

SHUTDOWN DECAY HEAT REMOVAL REQUIREMENTS (A-45)(CONTINUED)

PRELIMINARY NETWORK

" * "EsE.7E ".,.w = =. _

= _

. !=

sms=.gz;gmy

_. g _.... y' _=. ji s._

.. g g

e g

q

=-

7 = ;'g' =. g' := g'.

g' :.= g' :=- g* = g' =. g' _=.. g 37

" ~ ~ ""

SEISMIC QUALIFICATION OF EQUIPMENT IN OPERATING PLANTS (A-46)

== r._., V w.

Test 9:

23 e

,2 WB27

a. -.-

p=_q=__q.__ "*4g '

~

g" - - [

.r w.

"~

e g

.U g

,,,,,,,,,, " *" o a Yu.wY

-. =

es man %

. = an v:

@%=

n." __ 4 w q ~ c g

l

.km g.____.e s_ g

r..

- -. 242C

,e,,,

99 gm e

.,,.,- n

'-J:'~'*6 9==

m,. c CF N32C m,,,e

^

,m -

TE M.,,

M* *

  • gw,-*. m ean,,,

-p---., g=:=.$ **'* 1"_"*.e.1= _ _ ;___ 4

o - - c c -- g me w w.

,, men Y

l

=,: = ;.

. L.

l_

=

n I

l 1

l l

l I

SEISMIC QUALIFICATION OF EQUIPMENT IN OPERATING PLANTS (A-46)

Continued i::::.:;E..==

rh f"*" ;--...

s k *.~* Q %-- 4==-

Q

~

= *-..I..

l t

s_ -V.

_ m

.n

-4,.

3C.-

=.

2 y = &==,cp L' ~4,===4 c'4FY i

,.u..:

.e 2

.,7 ii i &

j - _., a

. = _ -

- --' " E'= ::::::'

w..y. y.::..

g~~ q g

g g

gy l

1

...e_.

..,e

..c....,

y.

g_.,.,- g._.g.,+e c '-~'-'e

.. =

ll1l

  • eh.

y w

2 e

4

)Ko tR

    • m 7

fR R om b*

4 oY 9aJ OT tS T a0 uA w

86 sN m"

A W sF L

(

sN n.

s a

eam S ETv co T

nC "aP-U na wo,u M No A s

ss

  • Qyk_py E

es S R sH a,

e A

s TYt uT e

r n.

oE s

^

e s

a c

e uT m

,m_-

wo,v cn Y A sf "r.

su o

~

S N Rt E

a a

ygg ua v

I Tv L MFm uo r

,~

OI g

n=.

c

P e, = o a

R LsA n :-;,

, eDn T E cT w "Q ii l m

t

  • 3 rE m.o.

Scv aH o

1 g

m.

m ab '

gc

,r R )s N P wt o

.Ca ha-

.g O

a o n r

to C

a.

s.

s ur 9,,

oa v.

=

F um 1U **

tp con

,v co O

'c s

ew wo sc

.e.

tE a

n r

,es oR

. :g~

~

nA ms S

N.Z",.

  • f, a

Ce.e sw N

.*,,3 g,

O

..".C",",a pv s

$,.,p,,

i.

  • .a 1

A-e.

I h.

!" mO T

v m.t T

g e

A 4.E,Q).

sw,

(

{

t g

e C

w p**n.

I L

a P

.~

',,=

d e.

M

-.O

.s.

a.

co Y

_.U",g i i,'

I

  • oy m,

a T

- -.c=

a.

E s.

h

, n..i -

~

a.

,i

,t F

e.

.a c

I-

,m,uQ5,;A..n@.

soqj A

s au i

,e S

, m.. L 2 -

g*g=v.y 2.r O *f "..=

_,.=

,.=

_',oa m=

egu s

m o.

,v e

..n,_

maq e

_ om

.'?.

e

,4 n

  • O,4iggg6 l

n.

.o co oo'*,n

.a

/

.e r

m ee cg..

r oH

\\

me e

m..o s

s.

ca f.

t e

r l'

e eo c

tem n

sy s

ia.

e*

Sse

.ts oe n

".~.,..

T e

r m

M ** e o

8m.e

.n e

.n s

o.

f eR o

o f*1 e '" V

.m e

t m.y

c. e Esa^

h o.

_ Ms

  • a 1

n-c t. e m's P

s

.e emT e

fe 1 e.n t.

i ne s

s a h a. n s

e 3

e e

s e e

.n edr s

h m. 8M s

=

. e.s*l s

s s

e e

e. e e

y*

=.. "

o

  • a e s e

e T ELC T IG T itT T ESs 2

T.

llll

,l

,I lIl!

i

1 1

i HYDROGEN CONTROL MEASURES AND EFFECTS OF HYDROGEN BURNS ON SAFETY EQUIPMENT (A-48)

AS o,, tex.No,NO KEY PERSONNEL TASK REVIEWERS SCHEDULED COMPLETION TASK MANAGER

\\

NAME BRANCH cLeomo anoanson urnus

()

.()

)[

mov samomeo CURRENT MPA ANALYST es av anaev unmiss

  • PROBLEM DESCRIPTION
  • RES INTERFACE INFORMATION
  • TECHNtCAL ASSISTANCE CONTRACTS
  • POTENTIAL PROBLEMS e

..um w e.mac m to se oevatoreo to se oevetoevo L

4

._-..= =f.= =.

%.*, *e, n

g M:

c:.I;"** **

-""~yE[8[

g -

, 2 1

  • ACRSINTERFACEINFORMATION FIN NO. CONTRaCTOft OettGATED EXPENDED
  • STATUS

SUMMARY

vo se oevetoreo a

e v,a

,.rt,an mac e emOICAYet & Co.ANGe s.e 186 0mwar.om gg

l sT5 x001 a

i i

i i

E I

I i

i b

I l

I i

I I

I F

i I

I i

b bi l

I i

a i

i i

1 jQ+'

lh b

b b

I

$l9?'

[ji I

i

" " jg)

"[9

"[9 59 'T 'T l

1:1 kl i

iT :, i! 1i@1!11 i @ 1111i;;8598%k 59 i

6 i,l 1

e,3

. i

=.

1' p

a p,1$jaA

[qp 54>-*59?-@+59!i

.i l

111 il 1il l

=

=

jf

,:11 jill) jlljj ijjj E.]

Ii

}

j9 l p IF*!f~~'W

i. i ita n a1"

.l l ui lii m

6 Ir'e e

ee Ge

{-

ll i

I)E i

..)

sL s us i

.r

ih 4

PRESSURIZED THERMAL SHOCK (A-49)

Continued Ts.k 7:

p.r no PTE 5.n lw.ny o

ea.

m s *.

W wv e c

  1. 9

,g u.os I,g m.-

s..e,.m

,.~

gyg g_g i

i i

ce i

r =_.

=.

I i

1

.~

.o

-v 4

I a

i I

-e e *'s

'd ma** a l

w.

.s.

a.e q-

~

l

/

T

t. 8:

O oi.o gt,

, P nn f _ _ _ _,,,,,,,,,,,_____./

(

.Y

a~

+

C":M=caa *"-" Q-~

-=

=c.

.* ~

O" C" @,,,a.@ ~ @~'I @

.w. c.

w on

@ _ re- @ **'

47 l

l

+

_.~

c' i

i ateuat =cea n sea,..* aucs

,I,i[****

u s nuclean assutaronv comu.ss.o.

NUIEG-0605. Vol. 4. Sto. 3 Bl8LIOGRAPH4C DATA SHEET i ritte ano suenrts sans v-=...aaw.

s

a.

..e Unresolved Safety Issues Susumery 3 as c'e'a =r s acca ssics. =o (Aqua Book)

s. oars atront courta vso aur ons

.o,-

August 1982-e cameoaw =o onca= sano= =aus o waiuno acoasss a rw i, c.=es care aiconi em,o wo='a J ama Of fice of Resource Manageauent we ions Managerient Information Branch e a.'-. was U. 5. Nuclear Regulatory Coussission Etshington. 0.C.

20555 e n.

w s is secs.sonimo onca= sation =awa amo wa:L4=c aooress ar.r6ari, c.ars

,,, g y, Office of Resource Management

,, co,,,,c,,,

Management Information Branch U. 5. Nuclear Regulatory Commission Washington. 0.C.

20555 j....o. _... o i,..c. o...co.,

May 21. 1982 - August,20.1982 is sueetaws ran, mores

. e4 m.-- = e s is a.s.. ac, -..,

P.cride an overview of the status of the progress and plans for resolution of the i

gintric tasks addressing " Unresolved Safety Issues" as reported to Congress.

i T

17 at t WonOs a%o doc #M %T aNatts's s 'a tX SC a'e f G*et is* oe%tiris as ors = s-.on o ve aus

r E.

$~-}

e is ava>us uv staram%r sg-g g Unlimited

" M cTa's'sified' '*' h ~

}

i 4

f

-,__m

,. ~ _ _.-.-.

.