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DEC 1. 9 E9-

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P. A.1torrie, Director, DPL -,_,

i'i,AN FOR PP.1: PAP!sT10N OF A ST!J:DAl:DI7.ED REVILi' PLAN.

Thic ner.c.ran?.uu i : for the purpor.e of nuhnittle, a proposed ninn for

preparation of tht- T.tr.ndr rd '.ev!w Plcn for t% reviev and concurrencee,f the DrL r.enf or s taf f. Cuapicsontal inferrction presented includes:

t (1) a lict of term sich in ny opinion rc:; eire definition (Attach-i nent A). (2) a su:rwr4 outline (Attechneat 3). (3) an annoteted outlise

of Volume I, Cennt ruction rcrnit Ap-'licatienn. Indicati:m the necernicontent of cach n ction cnd guidea for the r.uthors (Attach,cnt C). and

'

(4) a r,uide for tha prenaration of check li stn (Attachnent D). "y,,

ne::eral cer.mente on the nr:teri:1 prepared thus for ulll be nut,ittei,

' prri r.rini: a c.a :ple check list T'l _ later na At tach 2ent E. ^ In cddition,' ,I a:2

fcr one of the fccility ryste m.(O)-'

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?t in ny vic r thet concurrence of thc(DPL nenior staf f is needed en the.

folle.ii: p. ocintn prior to proceedin.g with any further '<riting on the --

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r::r: cf tic ntaff: (t) et:jgersven of t'm nom.*dard _'aviw Plep. (2). } gancral orscnizstion and format, (3) the title nnd cenere! centent, in

'prticular the list of fccility syst ms, and (4) the ensinnment_ of

i 9e rnor.rel . Only very linited dtncuasions of the proposed plan 1 nve'k' been held to date with the, confer ::.taf f bec.mu9e of the he::vy ense .

vor!:! cad in the pant neveral vackq. I have not atte :pted to r se

annig r.cnta'at thin tiae, heuever, in ny opinion, the pnrnennel uho ,/111 ultinntcly be reaponnible for the infety reviev and ovaluntion

unct punera the check list 2, discuss the enfety ic.Tues to be co :nidored:nd doce.ent' the imnin for acceptar.ce.

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The necpn involved '~in the prcper.ed pinn'are nn folions:~

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1. Revicu of the propered plan by the nenf or staff c.nd incorporationof ecm?nts ' agreed on. -

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2. Anninnnent of crecific technical personoc1 to the tasic of writingthe rw t draf t of the docuuent. The prernratiran of e. sche /ule forcoapletien based en a specific fraction of cr:ch individual's tic:e.being devoted to urition the document thould be a renuirenent. ~

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3. Edit and issue the draft for irnediate internal use and for con . .

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current review by DML per.ectrol vnd other DP, divirions.-

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4. Initiate work on Volurc II cnd Voltrac III. r. o

S. Incorporate ces,ents of other DP. divisions on Volune.I as neon-

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J.n<s ccm.cnts are r.ccived and diccuuued. . =- L

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| 6. Proceed in the s n o acacer vith Vo.luacs II r.nd III. '..

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' At no":c point it eaay very s:cIl be apprepriate to cor.vene a t::nk forec -~of AEC ..nd ir.dustric.1 peopic to review the pinn, heeever, if this is . 4

!done prior to our ie.plenenting the pinn, I 'eculd venture to' r.ucss that a.

uc will never he.ve a plan. ~ ,

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~Picasn 'ndvise t-e concerning he ticing for, a inecting with the nenior.- }. g

r.teff or' other sug.;ested action you recon:cend. . ." - ". - 5

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, - Acsist.nnt to the Director, DEL ' - - ';.i. ;

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f pacics:ura r. : -. --

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1. Attachment A '/ .-

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2. Attachnent B '-' ' '

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. . .m3. Attachnent C - - . .rj - .

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Attachment,

LIST OF STANDARD REVIEW PLANS _$

*,

I NT RO DU CT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .t*

Responsi' ole*

,

Branch *' CHAPTER 2.0 SITE C4APACTERISTICS,

AJ\B,

2.1.1 Si te Location and Description . . . . . . . . . . . . . . . . . . . . . . . . . . . .{ "

| 2.1.2 Excl us ion Area Authori ty and Contro1. . . .. . . . . . .. . .... .. . . ,

n.a

2.1. 3 Popul ati on Di s tribu tion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .n

.

2.2.1-2.2.2. Lccations and Routes . Da scri p tions . . . . . . . . . . . . . . . . . . . . . . . '

n

2.2.3I Ev aluation of Potential Acci dants. . . . . . . . . . . . .. . ... .. .. ... S /033

2.3.1 Regi onal C11 matology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..Sed 3

2.3.2 Local Meteorology........................................ .

n-

2.3.3 Cnsite Meteorological Heasurements Programs...............Bf

2.3.4 Short Tern (Accident) Diffusion Estimates................ n

2.3.5 Lcng Term (Routine) Dif fusion Estimates.................. .

n

2.4.1 . Hyd rol o gi c D e s crip t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .n

=

2.4.2 F1oods...................................................11

Probable Maximus Flood (FMF) on Streams and Rivers.......2.4.3 n

Potential Dam Failures (Seismically Induced).. ...........2.4.4 .---- _ ,,

2.4.5 Probable Maximus Surse and Seiche Flooding...............'

n

2.4.6 Probable Maxi mum Ts unami Flo odi ng . . . . . . . . . . . . . . . . . . . . . . . . -

. n

2.4.7 Ice Flooding..............................................

"2.4.8 Cooli ng Water Canal s and Res ervoi rs. . . . . . . . . . . . . . . . . . . . . .

n

2.4.9 Chann el Di v e rs i ons . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .'

,89

2.4.10 Fl c od P ro tec ti on Requ i re.T.ents . . . . . . . . . . . . . . . . . . . . . . . . . . . ._,_, _..

_-

^; n .

2.4.11 Low Wa ter Conside ra tions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Dispersion, Dilution, and Travel Times of Accidental n2.4.12' Rel ea s es o f Li qui d Ef fl uents . . . . . . . . . . .. . . . . . . . . .. . . . . . . . '

n' .

2.4.13 G ro undw a te r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Op

2.4.14 Technical Specifications and Emergency OperationPequ1rements.........................t...................

n .

2.5.1 Basic Geologic and Seismic Information............... .... .

.'(n, .

2.5.2 V ib ra to ry Gro und Mo ti on. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .- n

2.5.3 S u r f a c e Fa ul t i ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .n

2.5.4 Stabili ty of Subsurface Materi al s . .. . . . . .. . . .. . . . . ... . . . .n

2.5.5 Sl ope S ta b t 1 1 ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .i

j

|- -f* See attached key. ,

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LIST OF STANDARD REVIEW PLANS - Continued..

.

ResponsibleI CHAPTER 3.0 DESIGN OF STRUCTURES COMP 7;EtiTS,

-s EQuie.ui" Ai] SYST M5 Branch

RSBj *

3.2.1 . Seismic Classification...................................,,

"

$ 3.2.2 System Quali ty Group C1'as sifi ca ti on . . . . . . . . . . . . . . . . . . . . . .4 SE3

3.3.1 Wind 1.cadings............................................10'

3.3.2 To rn a d o 1.ca d i ng s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

APCS3.4.1 Ficcd Protecticn......................................... ,

SEB .

3.4.2 An a l y s i s P rec e d u res . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..

3.5.1.1 Internally Generated #11ssiles (Outside Containment)...... APCS

3.5.1.2 Internally Generated Missiles (Inside ccntainment)....... RSB,

AAB -

3.5.1.3 Turbine Missiles..........................................

AAB3.5.1.4 Hissiles Generated by I;atural Phenecena.. . ... ............

n -

3.5.1.5 Site Proximity Missiles (Except Aircra f t). ......... ......Il

3.5.1.6 Ai rc ra f t Ha z a rd s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.5.2 Structures, Systecs, and Components to be Protected. APCSf rem Ex ternally Genera ted M i ssil es . . . . . . . . . . . . . . . . . . . . . . .

SEB?.5.3 B a rr i er De s i g n Proc ed ures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

_3.6.1 .. Plant Design for Protection Against Postulated Piping APCS. .

,.

Failures in Fluid Systems Outside Containment............A

~ ; 3.6.2 Detennination of Ereak Locations and Dpanic Effects U3Associated with the Postulated Rupture of Piping......... -

SEE3.7.1 S ei sm i c I npu t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.7.2 S e i sm i c Sy s tem An alys i s . . . . . . . . . . . .'. . . . . . . . . . . . . . . . . . . . . ."

"~

3.7.3 Sei smic Subsys tem Anal ysi s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ,'

,

"-3.7.4 L Sei smic Ins trumentati on Program . . . . . . . . . . . . . . . . . . . . . . .. . _

1 "3.8.1 Concre te C on ta i nmm t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3.8.2 S t e el C on ta i nmen t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .- "

.-

3.8.3 Concrete and Structural Steel Internal Structures "of S teel or Conc rete Cen ta inmen ts . . . . . . . . . . . . . . . . . . . . . . . .

"~

3.9.4 C that Ca teg ory I St: uc tures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .Il

3.8.5 Foundations..............................................<

MEB 'k3.9.1 Spec i al Topic s for !!echa nical Co,ponen ts . .'. . . . . . . . . . . . . . .n

3.9.2 . Dynamic Testing and Analysis of Systems, Cogonents,'and Equipcent ...........................................

~.

3.9.3 ASME Code Class 1, 2, and 3 Cocponents, Component "e Supports , and Core Support Structures . . . . . . . .. . . . . ..... ..; n

3.9.4 C on trol Rod Dr ive Sys t ems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .vi

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-ft

f- . .. . .- . , _ - _ _ . _ . - , , _ _ _ . _ . _ u.

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h~

_._

- ;I,IST OF STA'ID.'aD REVIEW PIR:S - Continued Recron ible

. .__3 ranch

>

3.9.5 Rea c tor Fres sure Ve s sel Intern s1 s . . . . . . . . . . . . . . . . . . . . . . .. IE3

3.9.6 Inservice Testf rg of Pnps and Valves. . . . . . . . .. .... .... .. Mg3*

3.10 S'aisnic Qualificatten of Category I'Instrumentatten andf El ec tr 1 e a l Equ fpmen t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ME3

,

,

4

3.11 Envfren: ental Cesfgn of Mechanical and Electrical'

; E q u i;c 2n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .EICS3.11.5 Chealcal and Radf ological Envf rencental Estiinates........ AA3,

ig

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C MPTER 4.0 REACTOR -

4.2 Fue l Sys ta D es ig n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - . . . CP3 -

4.3 Jiuci c a r C e s i g n , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . "

4.4 Therea l and Hydraul ic Des ign . . . . . . . . . . . . . . . . . . . . . . . . . . . . . RS34.5 Reactivity Centrol Systems Functicnal Design ,,,,, pgk .

,,,,

4.5.1 Centrol Rod Systm Structural Materials ................. IEE34.5.2 Reac tor In tern al s Ma tar f a1s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 21TEB

'

CMPTER 5.0 REACTCit COOLANT SYSTEM MD CCNNECTED SYSTEMS

5.2.1.3 Coap1 f ance w f th 10 CFR I 50.55a . . . . . . . . . . . . . . . . . .. . . . . ... ES35.2.1.4 Appl ica ble Ccde Ca s es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . '"

-

5.2.2 Overpres sure Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . "

E 5.2.3 . Reactor Ccolant Pressure Bcundary Mate'rf a1s........ ......- hTEB <[^

5.2.4 RCF3 Ins crv ice Inspection & Testing. . . . . .. . . . . . . ... . ..... -"

5.2.5 F. CPS Lea k ag e De tec ti en . . . . . . . . . . . . . . . . . . . .'. . . . . . . . . . . . . . . RSB ~

5.3.1 Reactor Vessel Materials................................. Igg 3

5.3.2 Pre s s ure -Temp e rature Limi ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..

"

5.3.3 Kaa cter Ve s s el In te g r f ty. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . "<

, . . . _ .,

. , -

Pre fa c e to S ec tion 5.4 . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . .'

.

5.4.1.1 Ptep Flywheel Integri ty (PWR) . . . . . . . . . . . . . . . . . . . . . . . . . . . .- BTE3 f-,

5.4.2.1 S team Gene rator Ma terials . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . "'

, 5.4.2.2 Steam Generator Inservf ce Inspection.. . . .... ............. "

5.4.6 Reactor Core Isola tica Cooling Systm (SWR).............. RSB

5.4.7 Res idua l Hea t Recova l (RHR) Sys tem. . . . . . . . . . . . . . . . . . . . . . . RSB^

C- 5.4.8 Reac tor Water Cleanup System (SWR).. .. .. ~ :. . . . . ..... .... . ETSB - ' * '.

5.4.11 . Pre s sur f zer R e1 ie f Ta nk . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . A?CS

:i

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1'

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i. .

*

LIST OF STANDARD REUIEW PUJIS - Contin::ed- .

'

i Responsible jjCHAPTER 6.0 EMINEERED SAFETY iEAil; PES Branch

1

6.1.1 Engineered Safety Features itetallic !!aterials .......... HTE3

I 6.1.2 C rg a n i c Ma t e r i a l s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . AAB.

4 "6.1.3 Pcst-Accident Chemistry..................................

6.2.1 Con tainment Functional Des 1gn . . . . . . . . . . . . . . . . . . . . . . . . . . . . CSB^

n-6.2.2 Con ta ir. men t Hea t Ra oval Sys tems . . . . . . . . . . . . . . . . . . . . . . . . .

H

6.2.3 Seccndary Con ta ir.::en t Func t icnal Ca s i gn. . . . . . . . . . . . . . . . . ..98

-

6.2.4 Conta inment Isola ti on Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . .99

6.2.5 Ccobus ti ble Cas Control in Cen tainmen t. . . . . . . . . . . . . . . . . . .

6.2.6 Conta inment Le ahse Tes ting. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CSB

Emergency Core Cooling Sys tem. . . . . . . . . . . . . . . . . . . . . . . . . . . . RSB -.

6.3,

Hab i ta bi l i ty Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A'E6.4ETSB ->

6.5.1 ESF Filter Systems.......................................

Containment Spray as a Fission Product'Cicanup Systen.... N^

6.5.2:.

6.5.3 Fi s s i en Product Ccn trol Systems . . . . . . . . . . . . . . . . . . . . . . . . . . AAB .

" '

6.5.4 . Ice Condenser as a Fission Product Cleanup System........

6.6 ~ Inservice Inspection of Class 2 and 3 Cceponents......... MTEB_

v .. .

CHAPTER 7.0 INSTRUMENTATION AND CCNTROLS_ '

,

EICS -~

7.1 I n t r od uc t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .El

7.2 Reac tor Tri p System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .Il

7.3 Engin<:ered Safety Feature Systems........................-

4

"7.4 Systems Required for S afe Sht td own. . . . . . . . . . . . . . . . . . . . . . .

'

,

L.._. n,.

7.5 Safaty-Related Display Instrumentation................... ,

99

7.6 All Other Inst.ventation Systers Required for Safety...."~

7.7 Con trol Sy s tems f;o t R e qu i red fcr S a fe ty. . . . . . . . . . . . . . . . . ."

Appendix 7-A B ranch Technical Posi ticns (EICS3) . . . . . . . . .. . . . . . . . . . . .n

4p;endix 7-3 General Agenda, Stdtf on Sita Visits....................*

90

. Table 7-1 Acceptance Criteria for Controls........................

. ,.

4

' CHAPTER 8.0 Et.ECTRIC POWER _(d

"'

8.1 Introduction.............................................4

, "A

8.2 Offsite Pcwer System.....................................'

99

8.3.1 A.C Power Systems (Cnsi te) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .vtti

.

f

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.._ , . . _ ,

.-.

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_ ,

f y

'#m _g _t _ _ ii _ - . ' _ m _ C

.- , . . .. ,,

i- 'Ecoponsible

EranchLIST OF STA.TDARD REVIEV PLANS - Centinued

._

.

'

i

!8.3.2 D -C P ew ar Sy st ems (0n s i te) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . EICS

*

( "

Table 81 Acceptance Cri teria fcr El ectri c Pcw3r. . . . . . . . . . . . . . . . . . .,

.

CHAPTER 9.0 AUXILIARY SYSTEMS-

t9.1.1 ti ew Fu el S torag e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . APCS'

t' et

9.1.2 Spen t Fuel Stcra g e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ."

9.1. 3 Spent Fuel Fool Cooling and Cleanup System...............".

9.1.4 F u e l H and l i ng Sy stun . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .-

" -

9.2.1 Station Scrylce Water System (595) . . . . . . . . . . . . . . . . . . . . . . .' u

9.2.2 Co ol i ng Water System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ."

9.2.3 Daatneralized Water ' Hake-up System (CWMS)... ............. c,

ETSB9.2.4 Fotabl e and Sani tary Wa ter Systems . . . . . . . . . . . . . . . . . . . . . . .

APCS9.2.5 ' U l ti ra te Heat Si nk. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

tt

9.2.6 Condensa te Storage Faci li tie s . . . . . . . . . . . . . . . . . . . . . . . . .. . .n

9.3.1 Ccopre s sed Air System (CAS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .ETSB

3.3.2 ; Preces s Sampling System (PSC) . . . . . . . . . . . . . . . . . . . . . . . . . . ..APCS

9.3.3 Equip::ent and Flcor. Drainage System (EFDS).. .. ... .. .....

9.3.4 Chemical and Volt =e Control System (PWR) ,

(Including Baron Recovery System)........................ 1 .- ,- s.

I '

90

- 9.3.5 Standby Liquid Centrol System (SLCS) . . . . . . . . . . . . . . . . . . . . .n

9.4.1 Centrol Roas Area Ventilation System (CRAVS).. ............

",

Spent Fuel Pcol Area Ventilation System (57PAVS)......... .9.4.2-

",

Auxiliary and Radwaste Area VentiIation System (ARAVS)...-

9.4.3.

Turbine Area Ventil aticn System (TAVS) . . . . . . . . .. . .. .. .. .. ,

n-pa

9.4.4#

-- "4 '4

,_P 9.4.5 Engineered Safety Feature Ventilation System. (ESFVS)......j'.

,

.

n

9.5.1 Fire Protection Sy stem. . . . . . . . . . . . . . . . . . . . . . . . . : . . . . . . . . .'

9.5.2 , Cccc:u n i c a t i on s Sy stem (C5) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . -

" 'i

f " "

9.5.3 Li ghti ng Systems (LS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ."

9.5.4 Diesel Engine Fuel Oil Storage and Transfer Systtm.......It

9.5.5 Diesel Generator Cooling Mater Sys tem.. . . . ... ... ... .. .... *

n

9.5.6 ' Die sel Generator S tarting Sy st em. . . . . . . . . . . . . . . . . . . . . . . . . .. s

4n

9.5.7 Di esel Engine Lubrication System. . . . . . . . . . . . . . . . . . . . . . . . ."

Diesel Generator Ccnbustion Air Int 3ke and Exhaust System9.5.8. "

Main Steamline Isolatica Valve Scaling System (EWR)......9.5.9|

- 4g.

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LIST OF STAND.GD REVIE11 PLANS - Continued i

4

Responsiblei, CHAPTER 10.0 STE/M A.NO P0HR CCNVERSICN SYSTN _ Branch- i

| 10.2 Tu rb i n e G en 3 ra tor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . APCS.

10.2.3 Turbi ne D i sc Integri ty. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . MTEB'

f'

10.3 Mai n Steam Supply System (M555) . . . . . . . . . . . . . . . . . . . . . . . . . . APCS

10.3.6 Steam and Feeda ter System M a terials . . . . . . . . . . . . . . . . . . . . . MTEBt

10.4.1 M a i n Co nd e n s a rs (MC ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A?CS

10.4.2 Main Cond2nsar Evacua tion System (MCES) .. . . . . . . . .. .. . . .. . ETSBe

~

"10.4.3 Turbine Gland Sealing System (TGSS)......................10.4.4 Tu rbine Bypas s System (TB5) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . APCS ^ .

It *

10.4.5 Circ ul a ting Water System (CWS) . . . . . . . . . . . . . . . . . . . . . . . . . . . ,

n10.4.6 Condensate Cleanup Syste (C C 5 ) . . . . . . . . . . . . . . . . . . . . . . . . . . .--

n10.4.7 Condensate and Feodwa ;er System (C1FS) . .. . . . .. .. .. .. . .. .. -

98

10.4.8 Steam Generator Bi cwdown System (5G35) .. .. . . . .. . . . . .. .. ..n

10.4.9 Auxiliary Feedater System (AFS).........................'

CHAPTER 11.0 RADICACTIVE WASTE MANAGEMENT _

e

11.1 ' ,..

-~ -ETSB

.Source arms.............................................

./

"11.2 IJ qui d Wa s t e Sys t ems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

"11.3 Ga se ou s Wa s t e Sy s t em s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

".

11.4 Solid Waste Systems......................................

11.5 Frocess and Effluent Radiological Monitoring and ,,

Sepling Systems....................:....................

' "

CHAPTER 12.0 RADIATICN PROTECTION .

(. - r

,, ..

.- -

B- 12.1 Assuring That Occupational Radiation Exposures are As t.cw -As Prac ticabl e ( ALAP) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . RAB-g

12.2 Ra d i a t i on S ou ste s .' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . J'

"12.3 Radiation Frotective Design Features.. .... .. .... .... ....

"12.4 D o s e A s s e s s.r en t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

BE ~

12.5 He a nh Phys ic s Prog ram. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

CHAPTER 13.0 CONDUCT OF OPERATIONS ,N:~

-

13.1.1 - Management and Technical Support Crganization' .......... QA- , ...

"~| 13.1.2 Opara ti ng Organi za ti on. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

si " '13.1.3 Qualifications of Nuclear Plant Personnel ...............

-

''

98

13.2 Training ............................................... ,' . -

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i ISEP :13.3 Ecergency Pla wing........................................* '

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QAf 13.4 Review and Aw'.It..........................................

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,

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13.5 P l a n t Pr ec ed ur es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .'.

ISEP13.6 Industrial Security......................................

CHAPTER 14.0 PfANT TEST FROGR*WS '-

4.l.l* Ini tial Plan t Te s t Prcgrams - FSAA; . . . . . . . . . . . . . . . . . . . . . . . QA3" '

4.1.2 I ni ti al Pl an t Te st Prog rams - FSAR . . . . . . . . . . . . . . . . . . . . . . . .*

CHAPTER 15.0 ACCIDENT AV LYSES _

RSB '.15.0 Introduct1cn.............................................

15.1 INCREASE IN HEAT REMOVAL BY THE SECO*!OARY SYSTEM

13.1.1-15.1.4 Decrease in Feedwater Teaperature. Increase in Feedwater .

Flew, Increase in Stea:a Flcw, ar.d. Inadvertent Opening of ,,

a Steam Generatcr Relief or Safety Valve..................

15.1.5 Spectru:n of Steam System Piping Failures Insida and "Outside of Contai nmen t (FWR) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . -

',

15.2 DECREASE IN HEAT REMOVAL BY THE SECONDARY SYSTEM _4

15.2.1-15.2.5- Stea:n Pressure Regulator Failure (Closed). Loss of Ex- -

. ternal Lead cr Turbine Trip, Cicsure of Main Stea:s"

Isolation Valve (iNR). ard Loss of Ccndenser Vacuu:3...... RSB ,

15.2.6 Less of Non-Fr:ersency A-C Power to the Station ~"Auxi1iarles..............................................

"15.2.7 Los s o f Nomal Fe ed s ter F1 cw. . . . .,. . . . . . . . . . . . . . . . . . . . . . .

15.2.8 Feedwater Systen Pipe Breaks Inside and Outside Con- "ta i ncen t ( PWR) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

r _

.

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DECREASE IN REACTOR COOLANT FLC[ RATE __ , , .

u

15.3 ,'

15.3.1-15.3.2 Loss of Fcn:ed Reactor Coolant F1cw Including' Trip of .

"Pmp and Ficw Centroller Mal functions . . . . . . .. . . . . . . . .. . . .

15.3.3 15.3.4 Reactor Coolant Pmp Shaft Seizure and Reactor Coolant*

"Pump S ha f t B re ak . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

15.4 REACTIVITY ED PO*.:ER DISTRIS'JTION f,NC$ TIES

15.4.1 Uncontrolled Control Rod Assembly Withdrawal Frcn aCPBSubcritical or low Power Startup Ccndition............... ,.

's*

,,

15.4.2 Uncontrolled Centrol Rod Assembly Withdrawal at Pcwer....

15.4.3 Control Rod Misoperation (System Malfunction or Operator ."-Error)...................................................

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'

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15.4.4-15.4.5 Startup of an Inactiva Lcop or Recirculation Loop at an |>

Incorrect Tee;cratu*e, and Flow Controller MalfuncticaRSB.

Causing an Increase in 8%R Reactor Ccolant F1cw Rate......

15.4.6 Chunical and Volu a Centrol System fulfunction TiatResults in a Decrease in the Scrcn Concentration in '"'

the Reac tor Coolan t ( P.3) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .i

15.4.7 Inadvertent Loading and Oparation of a Fuel Assembly'

in an Imprcper Position.......................... ....... CF3"

15.4.8 Sp ec trua cf Rui Ejec ticn Acc id ents (P.12) . . . . . . . . . . . . . . . . . '

"15.4.9 Sp ectrum of Rod Drop Accidents (2WR) . . . . . . . . . . . . . . . . . . . . .

15.5 INCREASE IN REACTOR COOLANT INVENTORY _ .

*

15.5.1-15.5.2 Inadvartent Operation of ECCS and Chaical and VoluneCentrol System Malfunctica That Increases Reictor

RSSCo ol a n t I nv en tcry. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

15.6 DECREASE IN REACTOR COOLANT INVENTORY.

15.6.1 Inadvertent Opening of a PLR Pressurizer Safety / Relief ". Valve or a BWR Safety / Relief Va1ve. . . . . . . . . . . . . . . . . . . . . . .

,

15.6.2 Break in Instrus:ent Line or Other Lines from ReactorCoolant Pressure Boundary That Penetrate Containment..... AAB

"15.6.3; e Stes:a Generator Tube Failure Accident (PWR).. . .... .... . .. :,,

.' ,

"15.6.4 Main Steam Line Break Accident (S;G) . . . . . . . . . . . . . . . . . . .. .

i 15.6.5. Less of Coolant Accidents Resulting From Spectrum of- Postulated Piping Breaks Within the Reactor Coolant

Pres sure B oundary. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . RSB|.

q' I 15.7 RADICACTIVE RELEASE FRCit A St!35YSTs4 OR CO.MPC.*iEf1T

,

^ '

15.7.1 Wa ste Ga s Systes Fail ure. . . . . . . . . . . . . . . . . . . . . i. . . . . . . . . . . AAB...

'. '' 15.7.2 Radioactive Liqul'd Waste System Leak or failure...........

"... ,

_

~ 15.7.3 Postulated Radicactive Releases due to Liquid ETSB ~''

Tank Failures..........'...................................

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AABi 15.7.4 Fuel Har.dling Accidents..................................

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15.7.5 Spent fui ? Cask Crop Accidents . . . . . . . . . . . . . . . . . . . . . . . . . . .-

15.3 ANTICIPATED TRANSIENTS WITHOUT SCRAli.

MB15.8 Anticipated Transi ents Wi thout Scra:n. . . . . . . . . . . . . .. . . ... .

i

TECHNICAL S' ECIFICATIONS_-P~ ~ CPAPTER 16.0

16.0 Technical Specif t:at t ens . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . QA. ~

CHAPTER 17.0 QJALITY ASSURA'!CE_

17.1 Quality Assurance During Design and Ccastruction......... gr.

17.2 Quality Assurance During the Operations Piuse............ qA

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I KEY TO LICENSING BRA'iCH--'

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L L AAB - Accident Analysis Branch*

CPB - Core Performance Branch ,;

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! CSB - Containment Systcas Branch, ) -

: > ;MEB - Mechanical Zagineering 3canch .'

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! .MTEB - Materials Engineering Branch ,

| RAB - Radiological Assessment Branch .i

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--

,

RSB - Reactor Systems Branch. -

*

,

SAB' - Site Analysis Branch 7, ,

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SEB - Structural Enh;ineering Branch'

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QAB - Quality Assurance Branchi - _

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' ' OSB - Operational Safety Branch ,

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APCS - Auxiliary & Power Conversion Systems Branch'- , ,

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| 1,. EICS - Electrical, Instrumentation '& Control Systems Brancha ,.

b ISEP - Industrial Sec.urity'and Emergency Planning Branch'

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Um:Tt3D STATES I'IS :

MUCLEAR REGULATORY COMMISSION'

WASHINGTON, D. C. 20S55 i.mP ~ g

'.

No. 75-289 FOR IMMEDIATE RELEASE, f''Contact: Carl Gustin (Mailed - December 22,.1975) ~

Tel. 301/492-7771

%

NRC PUBLISilES STANDARD REVIEW PLAN W1- :.

s

The Nuclear Regulatory Commission's Of fice of Nuclear 1iReactor Regulation has published a Standard Review Plan for --

the NRC staff's sa fety review of applications to-build and, ,

operate light water-cooled nuclear power reactors.3;' 'dt

The purpose of the plan is to improve the quality," uniformity and predictability of the NRC staf f's review of e==applications to build new nuclear power facilities as well as ppmthe quality and uniformity of information supplied by appli- fCcants as the basis for the staff's review. The plan is a _

n maj or step in advancing the Nuclear Regulatory Commission'sI goal of enhanced consistency and predictability in the-

licensing process.

By providing more specific guidance to applicants on thekinds of safety-related information needed to review applica-tions to build and operate light water-cooled nuclear power 2-

$%^#plants and specific information as to the basis for the staff'sreview, it is intended that there will be a stabilizing effect_ Pon the licensing process that will benefit both the public andthe nucicar industry. -

The Standard Review Plan describes in detail the various #s -

sa fety- related technical areas reviewed by the NRC staf f, the, h,'

basis for the review, the procedures for accomplishing the LW -*

review, and the conclusions which are sought in each area. /y. .The format of the Standard Review Plan is consistent with t'#1 -Revision. 2 of the NRC's Regulatory Guide 1.70 " Standard Format Yand Content of Safety Analysis Reports for Nuclear Power M.N;.Plants - Light Water Reactor Edition." g .

The 1,414-page Standard Review Plan comprises 224 sub- hsections that have been made available to the public during e wethe past year in separate groups as they were completed. The MLcomplete plan incorporates some changes to improve clarity Qsp.and incorporate comments received. h.11= %. . .

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lNM Copies of the Standard Review Plan, which has been iden-

tified as NUREG-75/087, are available from the Natio'nal*

.

ym Technical Information Service, Springfield, Virginia 22161. .

j'R:> The domestic price is $60 and the foreign price $75 includings4 first-year supplements. The domestic price for individual .

Mg sections is $3.50 and the foreign price is $5.00.

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