ML20094J286

From kanterella
Revision as of 00:09, 3 May 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Forwards Table of Contents Illustrating Integrated Modules 6 & 8 Re Secondary Side Safeguards Sys & Steam & Power Conversion Sys
ML20094J286
Person / Time
Site: 05000601
Issue date: 08/02/1984
From: Rahe E
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NS-EPR-2945, NUDOCS 8408140278
Download: ML20094J286 (11)
v • d • e


Text

n (v ,;}

/

l l

Box 355 Westinghouse Water Reactor PittsburghPemsyfvanb15230 Electric Corporation Divisions l

NS-EPR-2945 '

August 2, 1984 i Mr. Harold R. Denton, Director Docket No. STN-50 601 l Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SJBJECT: RAPWR RESAR-SP/90: Consolidation of PDA Modules 6 and 8 l 1

ATTENTION: K. T. Eccleston, Project Manager, SSPB Dear Mr. Denton

{

During the course of developnent of RESAR-SP/90 PDA Module 6, " Secondary Side j Safeguards System (SSSS)" and PDA Modale 8, "Stean and Power Conversion System" it has become apparent that in order to have a clear understanding of the ,

interrelationships between these two areas of the plant, and to avoid extensive cross-referencing, it.is advisable to consolidate these two modules into one <

integrated module. The resulting module entitled, " Integrated Modules 6 and 8:

SSSS/ Steam and Power Conversion System" will then contain a complete safety analysis report (SAR) Chapter 10 augmented by supporting information from other SAR chapters as appropriate. Enclosure 1 illustrates the approximate Table of Contents for the integrated module.

'Ihe Emergency Feedwater System will be located in SAR sub-section 10.4.9 (which is traditionally entitled " Auxiliary Feedwater"). A new sub-section,10.4.10, will be added entitled "Startup Feedwater System". Interface criteria for those areas of the plant outside the scope of the HAPWR Nuclear Power Block (e.g.,

detailed design criteria for the Startup Feedwater System, etc.) will be provided in an appendix to Chapter 10.

F

[ 000 M284o*Cl'o*%!n 98 A

Mr. HJ 'R De6toit Page Two The current PDA licensing schedule targets Modules 6 and 8 for August and October 1984 sutxnittals, respectively. Instead, we plan to submit the consolidated module in September 1984.

Please cor. tact Mr. Douglas G. Bevard if you require any additional information relative to the Westinghouse planned module consolidation.

Very truly yours, f) ,

E. P. Rahe, Jr. , Manager Nuclear Safet'y 2 Department MDB/kk Enclosure ec: D. Eisenhut R. Bernero F. Miraglia, Jr.

C. Ihmas

_ _ , , . . . .. . - e Ry: ' i ?-" MODULE 6 f .' 8 08/0I/84 I:[U'iin:. -

'SECTION DESCRIPTION CATEGORY n,'w;pp; , ' - -

Oshtifk . INTRODUCTION I WM .

pp ; } r.2,3. 2 , ,

SECONDARY SAFfGUARDS SY3TEMS. II. .,

W4112.3. 5 .

, STEAM AND POWER .CordERSION -!!

? .. . '1 . . . .

p .g.1.,3.1 x...- -

COMPARISON WITH SIMIL W FACILITY DESIGNS. Il K #1;SO MATERIAL INCORPORATED BY REFERENCE II ekB?lt:4s.

1,7 1 ELECTRICAL. INSTRUMENTATION. ANO . II F> , ^ i ~

. -CONTROL DRAWINGS Wil7521 '.E ' PIPING AND INSTRUMENTATION DIAGRAMS II-s

~ g;1.7 N ),3' . OTHER DETAILED INFORMATION II L 1 ; 8.; ' CONFORMANCE WITH THE STANDARO REVIEnt II-PLAN pp 3.1 CONFORMANCE WITH NRC GENERAL II w .:^ - .:31! DESIGN CRITERIA.

'~~

?3.2 CLASSIFICATION OF STRtlCTURES. 11 MR.~ t:

..3 ,2 ,3.. , SAFETY CLASSES. II

~ >

" 3.~2. 5 % -REFERENCES II

! lh,4.9 MAIN STEAMLINE AND FEEDWATER PIPING I R'~" .

1 ?Melo , ENGINEERED SAFETY FEAIURES II.

w Q f _. ENGINEERED SAFETY FEATURE MATERIALS .II i

4 3.3.4 -MAJOR SECONDARY SYSTEM PIPE FAILURE II 1

e

?

~y ' *

~

MODULE 6 /,8 08/01/84 ^

3 .

F': ,  : SECTION~ DESCRIPTION' CATEGORY-6:h,'3.3.5 '

' STEAM GENERATOR TUBE FAILURE I!'

, iG.3.3.6 FEEDWATER SYSTEM PIPE BREAK II 3-2~ .. .

! 10.0 - STEAM AND POWER CONVERSION SYSTEM I y ~ :.

  • 0 *:110.t?

SUMMARY

DESCRIPTION 'l

  • 4.. _ .

j0,2 TURBINE-GENERATOR III s '. 10. 2 .1 DESIGN BASES- 111 C% :... . . .

4 0,0,

2.2 DESCRIPTION

.III 910.243' ' TURBINE DISR INTEGRITY  !!! <

f f

..III

,10,2.3.1 MATERIALS SELECTION PEG 10.2e3.2 . FRACTURE TOUGHNESS III I

  • 4 ...t..... .

, . s O,, 2 . 3 . 3 _ .

.HIGH - TEMPERATURE PROPERTIES

  • III L

9 N10.2.3.4 TURBINE DISK DESIGN '!II' I b..,.. .

,,10.2.3.5 PRESERVICE, INSPECTION III j i' T10.2.'3.6 INSERVICE INSPECTION 111 q &c j , 1d,2.4 EVALUATION III If : 10.3l MAIN STEAM SUPPLY SYSTEM 1 4 m I 10,3>- 1 DESIGN BASES I l g- a l

1 f

i

4

"~k , MODULE O/ 8 -08/01/C4

^

SECTION DESCRIPTION CATEGORY n

10:

3.2 DESCRIPTION

1 l ?? . .. . .

10.3.3 EVALUATION I.

I c--  !!O.3.4 INSPECTION AND TESTING REQUIREMENTS ,  !

,10.3.5 WATER CHEMISTRY (PWR) I

' 110.3.6 - -STEAM AND FEEDWATER SYSTEM MATERIALS

- >I s's /Mf..

+

10,3.6.I. FRACTURE TOUGHNESS I ms 9:I51013.6.25 s - 'sMATERIALS SELECTION AND FABRICATION I

  • 'A i"" , <

. . s 10.4 OTHER FEATURES OF STEAM AND POWER I W'"' ' '

. CONVERSION SYSTEM-

'MA10.4 s t . MAIN CDNDENSERS. -III' it .s'.. . . .. . . . ..

10,4.2 MAIN CONDENSER EVACUATIDN SYSTEM III ws - s L10.4 3 *

. TURBINE GLAND'$EALING SYSTEM III-EF'EL . . .

~

., JO,,4.4 ,TUR8INE BYPASS SYSTEM III a.:. >

..~ . -

't0.4.5 CIRCULATING WATER SYSTEM  !!!-

p ;;;s ' .

10,4.6 CONDENSATE CLEANUP SYSTEM III

% 10C4.7 '

CONDENSATE AND FEEDWATER SYSTEMS III

'is . . .

10.4.8 , STEAM GENERATOR BLOWDOWN SYSTEM (PWR) I i.10.4.8 f t : DESIGN BASES- I W

1 4 #

' MODULE. G / 8 08/01/I4

^

-.SECTIDN- DESCRIPT!DN CATEGORY 10.4.d,2 SYSTEM DESCRIPTION AND OPERATION I .

J10.4.8.3 SAFETY EVALUATION 1 ,

l

,1O',4 . 8 . 4 TESTS AND INSPECTIONS I 1: <

j W10.4.9 EMERGENCY FEEDWATER SYSTEM (PWR)  ! -

10,4.9.1 DESIGN BASES I l

71014.9.2' SYSTEM DESCRIPTION I f

4 I

10.4.9.3 SAFETY EVALUATION I . ,

) n'~10.4.9.4 INSPECTION AND TESTING REQUIWEMENTS I i . . . . . .

10,4.9.5 INSTRUMENTATION REQUIREMENTS. I i htO.4.10 <

STARTUP FEEDWATER SYSTEM I 15,b ACCIDENT ANALYSIS II N {15.011'  : CLASSIFICATION OF PLANT.CCONDITIDNS '

'I ,

'_ '15. 0.1, 4 '

CONDITION I - NORMAL OPERATION AND I

OPERATIONAL' TRANSIENTS 215.0.1.2- CONDITION II -- FAULTS OF MODERATE 'l FREQUENCY l 15,0.1,3 CONDITION III - INFREQUENT FAULTS I

. u; ~ -

. L tS.O.1.4 - CONDITION IV - LIMITING FAULTS I i

f U- .,

__,.15,0.2 OPTIMIZATION OF CONTROL SYSTEMS I s

l 4

1 i

i

i

(

fCTsi' ' ' , ^'

W MODULE 6 /' 8 .' -

t08/01/84- .

~

Ml, L. . .

SECTION DESCRIPTION CATEGOR'Y

. , . x . ,

'iiiMtS.O.3' '

PLANT CHARACTERISTICS AND INITIAL COND- 1

~ITIONS ASSUMED IN THE ACCIDENT ANALYSES Ed . . .. x .

g3.,5,0.3,1 1 c.

DESIGN PLANT CONDITIONS I *

5 3
  • F' $1510.3.2 INITIAL CONDITIONS  !

,u; - ...: '

15,0.3,3 POWER DISTRIBUTION I s l'iS.O.4 - -

-REACTIVITY COEFFICIENTS ASSUMED IN THE I

, ACCIDENT ANALYSIS t ..

3 15,0.5

^

ROD CLUSTER CONTROL ASSEMBLY INSERTION I 4

CHARACTERISTICS 2

3  ?? f16.0.6 . TRIP POINTS AND TIME DELAYS TO TRIP I

$ ASSUMED IN ACCIDENT ANALYSES i

l 5 15,0.7 3

4 INSTRUMENTATIION DRIFT AND CALORIMETRIC I I ERRORS - POWER RANGE NEUTRON FLUX v15.0.8 PLANT SYSTEMS AND COMPONENTS AVAILABLE

  • I FOR MITIGATION OF ACCIDENT EFFECTS

+ v J5,0.9 FISSION PRODUCT INVENTORIES I N n15.0.9.1 LACT!v1 TIES'IN THE CORE I

=

.s b .. . .

4 15,0.9.2 - ACTIVITIES IN THE FUEL PELLET.CL%D GAP I

- &s- 4

' diSiO tO s 2 RESIDUAL'DFCAY' HEAT: -I-Sin. 3.. _ . , f .s . . '

1$,0. 10.1 TOTAL RESIDUAL HEAT I

p. f ..,

s-

)

i R ntSiO.'10:2- ' DISTRIBUTION OFfDECAY HEAT FOLLOWING- .I '

LOSS-OF-COOLANT ACCIDENT Ni2Fii~ . . s '

I

,g.y 15,+,0.11 . COMPUTER. CODES. U.TILI2ED

4. n -

N fl.15.O'.11.1.~ '

FACTRAN' I-1 i

4 e

b

m + = .

x .

MODULE 6/ 8 C8/01/84

.SECTIDN' DESCRIPTION CATEGORY' '

4 15,0.11.2 LOFTRAN I

, 3.. .

M .15.0.11.3 LEOPARD I J. .

15,0.11.4 TURTLE I r.:'

115.0.11.5' TWINKLE I s-.

15,0.11.6 THINC I

15.0.12 LIMITING SINGLE FAILURES I s

,'t 5 ,0.13 OPERATOR ACTIONS I 15.0.14 - REFERENCES 'I' 5.1 INCREASE IN HEAT REMOVAL BY THE I SECONDARY SYSTEM 15.141 FEEDWATER SYSTEM MALFUNCTIONS THAT I RESULT IN A DECREASE IN FEEDWATER TEMP.

I' 15.1.1.1 IDENTIFICATION OF CAUSES AND ACCIDENT I l

.' ' DESCRIPTION

.15.1.1.2 ANALYSIS OF EFFECTS AND CONSEQUENCES I' >

~15.1.

1.3 CONCLUSION

S I 15.t.2 FEEDWATER SYSTEM MALFUNCTIONS THAT .. I RESULT IN AN INCREASE IN FEE 0 WATER FLOW 15,1.2.1 IDENTIFICATION OF CAUSES AND ACCIDENT I

' * ' DESCRIPTION 215.1.2.2 ' ANALYSIS OF EFFECTS AND CONSEQUENCES I s- S

'j5.1.2,3 CONCLUSIONS k I

Es MODULE 6' / ' 8 08/01/84 x 4 ^

_SECTION DESCRIPTION CATEGORY L15.1.3' EXCES$1VE INCREASE IN SECONDARY STEAM I* *

,y.. , ,

Flow 15 1 3.1 7 IDENTIFICATION OF CAUSES AND ACCIDENT I DESCRIPTION

1541.3.2 ANALYSIS OF EFFECTS AND CONSEQUENCES I 15.1.3,3 CDNCLUSIONS I
    • <t5.1.4- INADVERTENT OPENING OF A STEAM GENERATOR I RELIEF OR SAFETY VALVE 15,1.4,1 IDENTIFICATION OF CAUSES AND ACCIDENT I

F:- DESCRIPTION

-i t s . t . A . 2 ~ <

ANALYSIS OF EFFECTS AND CONSEQUENCES I

, th, h,.4 3 7 CDNCLUSIDNS I

N: 15.' t . 4 . 4 ' . RADIOLOGICAL CONSEQUENCES I 15,1 5 STEAM SYSTEM PIPING FAILURE I

'15;t.5.1- IDENTIFICATIDN OF.CAUSES AND ACCIDENT I DESCRIPTION 15.1.5.2 ANALYSIS OF EFFECTS AND CONSEQUENCES I

' .Il5. t .5.3 - RADIOLOGICAL CONSEQUENCES. I >

l ~

15.1.

5.4 CONCLUSION

S .I

/1 5.t'5.4.1. ANALYTICAL ASSUMPTIONS

  • I r,

15.1.5.4.1.1 SDURCE TERM CALCULATIONS I

' K1511.5.4.1.2L MATHEMATICAL MODELS USED IN THE' ANALYSIS.  !

4 >

p ,, ,

MODULE . G/8 08/01/84

~<

EC ' 4SECTION DESCRIPTION CATEGORY; "

T'~: , .

15,1 5,4.1.3 IDENTIFICATION OF LEAMAGE PATHWAYS I

, " ' AND RESULTANT LEANAGE ACTIVITY i

ST , 15. t .S . 4 . 2 - INDENTIFICATION OF UNCERTANTIES AND I CONSERVATISMS IN THE ANALYSIS 15.').5.4.3, CONCLUSIONS I st5ft.5.4.3.1 FILTER LOADINGS 1

% b , r . .. . . . , o 15,1.5.4.3.2 DOSE 10 RECEPTOR AT THE EXCLUSION AREA I BOUNDRY-AND LOW-POP OUTER BOUNDRY 1 -

j

^

4J1512 DECREASE IN HEAT REMOVAL BY THE

~

I SECONDARY, SYSTEM 15,2 t STEAM PRESSURE REGULATOR MALFUNCTIDN OR I FAILUREETHAT RESULTS IN DECR. STEAM FLOW

t5.2.2 LOSS OF EXTERNAL ELECTRICAL LOAD I

'15,2.2,1 ' IDENTIFICATION OF.CAUSES AND ACCIDENT I DESCRIPTION

~

i:1512.2.2 ANALYSIS OF EFFECTS AND CONSEQUENCES I .

15.2.

2.3 CONCLUSION

S I 1

i 15.2.3.1 IDENTIFICATIDN OF CAUSES.AND ACCIDENT I OESCRIPTION

'15.2.3.2 - ANALYSIS OF EFFECTS AND CONSEQUENCES I +

I 15.2.3.3 CONCLUSIDNS I i

I 15.2.4 INADVERTENT CLOSURE OF MAIN STEAM I ISOLATIDN VALVES I 15.2.5 LOSS OF CONDENSER VACUUM Af40 OTHER I i

  • * ^

i EVENTS RESULTING IN 1URBINE TRIP

4 NODULE G/8 08/Ot/84 s

- a ;. .

.. SECTION DESCRIPTION CATEGORY -

q 4O15.2.6~ LOSS OF NONEMERGENCY AC POWER TO THE- I STATION AUXILIARIES '

. . . . . c . . ..

15,...2...6.1 . "

IDENTIFICATION OF CAUSES AND ACCIDENT I g ' DESCRIPTION. ,

J15.2.6.2 - ANALYSIS OF EFFECTS AND CONSEQUENCES I pil . . . ,

15.2.6.3 RADIOLOGICAL CONSEQUENCES I pj:; 2 . - . -

  1. 0615.2.G.4 ' CONCLUSIONS I

>^ w. . 1 -C

,.,15.2.7 _ _ LOSS OF NORMAL FEEDWATER FLOW I va-e ..e .-

.n?its:2.7 d ' ' ' .' IDENTIFICATION OF.CAUSES AND-ACCIDENT- I' DESCRIPTION

au . . . . . , . . . .

l .j5,2.7,2 ANALYSIS OF, EFFECTS AND CONSEQUENCES .

I ms ' s.- ,

F*19512.7.3 : 4 CONCLUSIONS '

I

  • i F?% . . t >

15,2.8 y.c . . . ,

- FEEDWATER SYSTEM. PIPE BREAK I

"095.2.8.t' ' IDENTIFICATION OF CAUSES AND ACCIDENT. I DESCRIPTION UGL - .'. .

,15.2.8,2 ANALYSIS OF EFFECTS ANO CONSEQUENCES I

15.2.s J- CONCLUSIONS I j ,- . s i

d i

t j s s -

1 4

( ( ,' -

N )

a

  • 1 4

I . _

,

Retrieved from "https://kanterella.com/w/index.php?title=ML20094J286&oldid=2786912"