ML19308B888

Submits Proposed Plan for Preparation of Srp.Requests Concurrence on Objectives,General Organization & Format, Title & General Content & Assignment of Personnel.Lists Steps Involved in Proposed Plan

ML19308B888
Person / Time
Site:	Crane
Issue date:	12/19/1969
From:	Wilson T US ATOMIC ENERGY COMMISSION (AEC)
To:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML19308B877	List: ML19308B875 ML19308B884 ML19308B888
References
TASK-TF, TASK-TMR NUDOCS 8001170498
Download: ML19308B888 (2)

Text

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DEC 1. 9 E9 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 concurrence e,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 necerni content 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

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_ 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 r::r: cf tic ntaff:

(t) et:jgersven of t'm nom.*dard _'aviw Plep. (2)

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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

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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.

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

~

1.

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

2.

Anninnnent of crecific technical personoc1 to the tasic of writing the rw t draf t of the docuuent. The prernratiran of e. sche /ule for coapletien 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.

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

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Initiate work on Volurc II cnd Voltrac III.

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

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.n<s ccm.cnts are r.ccived and diccuuued..

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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 -

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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..

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,i,,T. R. Wil. son Acsist.nnt to the Director, DEL ' -

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Attachment A

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Attachnent B

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Attachnent C

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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............................

{

l 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 /03 3

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 n

2.4.12' 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 Operation Pequ1rements.........................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.........................................

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• See attached key.

I

,.. ~ _ _ _ _ _ _

1

LIST OF STANDARD REVIEW PLANS - Continued Responsible I

CHAPTER 3.0 DESIGN OF STRUCTURES COMP 7;EtiTS,

-s EQuie.ui" Ai] SYST M5 Branch RSB j

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.........................................

APCS 3.4.1 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.........................................

AAB 3.5.1.4 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

. APCS f 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

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3.6.2 Detennination of Ereak Locations and Dpanic Effects U3 Associated with the Postulated Rupture of Piping.........

SEE 3.7.1 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........................

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

Il 3.8.5 Foundations..............................................

MEB

'k 3.9.1 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................................

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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 and f

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................................................

.EICS 3.11.5 Chealcal and Radf ological Envf rencental Estiinates........

AA3, i

g 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.............................

RS3 4.5 Reactivity Centrol Systems Functicnal Design,,,,,

pgk 4.5.1 Centrol Rod Systm Structural Materials.................

IEE3 4.5.2 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..........................

ES3 5.2.1.4 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

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

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

RSB

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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

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

Responsible j

j CHAPTER 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'E 6.4 ETSB 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

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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....

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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)...............................

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i-Ecoponsible Eranch LIST OF STA.TDARD REVIEV PLANS - Centinued i

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

EICS

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

CHAPTER 9.0 AUXILIARY SYSTEMS t

9.1.1 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 ETSB 9.2.4 Fotabl e and Sani tary Wa ter Systems.......................

APCS 9.2.5

' 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)............................... -

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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 4 n

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

Diesel Generator Ccnbustion Air Int 3ke and Exhaust System 9.5.8 Main Steamline Isolatica Valve Scaling System (EWR)......

9.5.9 l

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l LIST OF STAND.GD REVIE11 PLANS - Continued i

4 Responsible i,

CHAPTER 10.0 STE/M A.NO P0HR CCNVERSICN SYSTN

_ Branch

- i l

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.....................

MTEB t

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)..................

ETSB e

~

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)...........................

n 10.4.6 Condensate Cleanup Syste (C C 5 )...........................--

n 10.4.7 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 ',

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ETSB Source arms.............................................

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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..........................................

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

CHAPTER 13.0 CONDUCT OF OPERATIONS N:

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13.1.1

- Management and Technical Support Crganization'..........

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l 13.1.2 Opara ti ng Organi za ti on..................................

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13.1.3 Qualifications of Nuclear Plant Personnel...............

98 13.2 Training...............................................

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LIST OF STANDARD REVIEW ?LANS - Continued Responsible Branch i

i ISEP 13.3 Ecergency Pla wing........................................

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

OLB r

13.5 P l a n t Pr ec ed ur es..........................................

ISEP 13.6 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 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 a CPB Subcritical 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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LIST OF STAbTiARD REVIE'.i PLA!;S - Continued Branch 15.4.4-15.4.5 Startup of an Inactiva Lcop or Recirculation Loop at an Incorrect Tee;cratu*e, and Flow Controller Malfunctica RSB Causing an Increase in 8%R Reactor Ccolant F1cw Rate.....

15.4.6 Chunical and Volu a Centrol System fulfunction Tiat Results 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 Volune Centrol System Malfunctica That Increases Reictor RSS Co 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 Reactor Coolant 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 l

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

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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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P sponsible LIST OF STAND.nD REVTU1 PLA?:S - Contimred oranch AAB i

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

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

15.3 ANTICIPATED TRANSIENTS WITHOUT SCRAli MB 15.8 Anticipated Transi ents Wi thout Scra:n.....................

i TECHNICAL S' ECIFICATIONS_-

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QA

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CHAPTER 17.0 QJALITY ASSURA'!CE_

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

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

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MTEB - Materials Engineering Branch l

RAB

- Radiological Assessment Branch.

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- Reactor Systems Branch.

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- Site Analysis Branch 7,

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- Structural Enh;ineering Branch t

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Um:Tt3D STATES I'

IS MUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20S55 i.m P ~ g No.75-289 FOR IMMEDIATE RELEASE, f

Contact:

Carl Gustin (Mailed - December 22,.1975)

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Tel.

301/492-7771 NRC PUBLISilES STANDARD REVIEW PLAN W1 s

The Nuclear Regulatory Commission's Of fice of Nuclear 1i Reactor 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.

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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 ppm the quality and uniformity of information supplied by appli-fC cants as the basis for the staff's review.

The plan is a n

maj or step in advancing the Nuclear Regulatory Commission's I

goal of enhanced consistency and predictability in the licensing process.

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

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plants and specific information as to the basis for the staff's review, it is intended that there will be a stabilizing effect_

P on the licensing process that will benefit both the public and the 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.

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The format of the Standard Review Plan is consistent with t'#1 -

Revision. 2 of the NRC's Regulatory Guide 1.70 " Standard Format Y

and 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-h sections that have been made available to the public during e

we the past year in separate groups as they were completed.

The ML complete plan incorporates some changes to improve clarity Qsp.

and incorporate comments received.

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l NM 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.

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The domestic price is $60 and the foreign price $75 including s4 first-year supplements.

The domestic price for individual Mg sections is $3.50 and the foreign price is $5.00.

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