Text

Slide Presentation Entitled ACRS Subcommittee on Cessar
	ML20040E242
Person / Time
Site:	05000470
Issue date:	10/19/1981
From:	; Advisory Committee on Reactor Safeguards
To:	;
Shared Package
ML20040E240	List: ML20040E239; ML20040E242;
References
	ACRS-1926, NUDOCS 8202040056
	Download: ML20040E242 (39)
	v • d • e

,

ACRS SUBCOMMITTKE ON CESSAR

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AGENDA-NOVEh.sER 19,1981

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PJ:OO og WINDSOR, CONN.

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o-m PRESENTATION SPEAKER TIME ACTUAL TIME E

1. INTRODUCTION

o A. SUBCOMMITTEE CHAIRMAN'S OPENING M. BENDER 5 MIN.

8:00 - 8:05 am STATEMENT (ACHS)

B. NRC i

1. OVERVIEW OF FDA REVIEW C. G RIMES 5 MIN.

8:05 - 8:15 mm (NRC)

2. SER OPEN ITEMS

,C. G RIMES 5 MIN.

8:15 - 8:25 am i

(NRC)

C. COMBUSTION ENGINEERING (C E) 1.

INTRODUCTION D. E. LYONS/

5 MIN.

8:25 - 8:35 am j'

P.L.McGILL l

2.

RESPONSE TO SER OPEN ITEMS A. E. SCHERER 5 MIN.

8:35 - 8:45 am l

II. DISCUSSION OF FDA REVIEW ISSUES i

l A. CESSAR FSAR l

1. C E APPROACH TO STANDARDlZATION A. E. SCHERER 5 MIN.

8:45 - 8:55 am l

2. PLANTS EXPECTED TO REFERENCE A. E. SCHE RER 5 MIN.

8:55 - 9:05 am j

CESSAR-F

3. SCOPE OF CESSAR.F G. A. DAVIS 10 MIN.

9:05 - 9:25 am I

3 a.

REGULATORY UPDATE

b. APPLICABLE TMI ISSUES 5!

i c.

INTERFACES I

g l

~

i 4

ACRS SUBCOMMITTEE ON,CESSAR AGENDA-NOVEMBER

,1981 WINDSOR, CONN.

(Cont'd)

PRESENTATION l

SPEAKER TIME II. DISCUSSION OF FDA REVIEW ISSUES (Cont'd)

_ ACTUAL TIME B. DESCRIPTION OF SYSTEM 80 NSSS R. W. KNAPP

1. OVERVIEW OF DESIGN 5 MIN.

9:25 - 9:35 am l

2. UNIQUE FEATURES 5 MIN.

9:35 - 9:45 am

3. COMPARISON WITH OTHER C-E PLANTS 5 MIN.

9:45 - 9:55 am

- BREAK -

10 MIN.

9:55 - 10:05 am C. SELECTED DESIGN FEATURES

1. DECAY HEAT REMOVAL (INCLUDING R. S. TURK 5 MIN.

10:05 - 10:15 am DISCUSSION OF FEED AND BLEED)

2. SEISMIC DESIGN T. E. NATAN 5 MIN.

10:15 - 10:25am l

3. ACCIDENT MONITORING SYSTEM J. L. PUCAK 5 MIN.

10:25 - 10:35 am D. TRANSIENT AND ACCIDENT RESPONSE C. L. K LING 10 MIN.

10:35 - 10:55 am (INCLUDING PRESSURIZED THERMAL SHOCK) i E. SUPPORT GIVEN TO UTILITY J.M. WESTHOVEN 5 MIN.

10:55 - 11:05am l

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ACRS SUBCOMMITTEE ON CESSAR AGENDA-NOVEMBER 19,1981 WINDSOR, CONN.

(Cont'd)

PRESENTATION SPEAKER TIME ACTUAL TIME Ill. DETAILED RESPONSE TO ACRS LETTER OF SEPTEMBER 15,1975 A. COMBUSTION ENGINEERING PRESENTATION 45 MIN.

11:05 - 12:35 pm

- PROGRAM TO PERMIT DESIGN CHANGES G.A. D AVIS 5 MIN.

-PROTECTION AGAINST SABOTAGE G.A. DAVIS PERITEM

-GENERIC REVIEW OF LUBE OIL AND J.E. WATERS COOLING WATER FAILURES l

- MAINTENANCE, INSPECTION, AND G.F. CARUTHERS OPERATIONAL NEEDS THROUGHOUT LIFE

-CLEANING AND DECONTAMINATION G.F. CARUTHERS

- DECOMMISSIONING G.F. CARUTHERS

- CHANGES MADE TO CPCS AND COLSS D.S. E ERTO FROM ANO-2 EXPERIENCE

- OPERATING EXPERIENCE WITH 16 x 16 M.G. ANDREWS FUEL

- lMPROVEMENTS IN ECCS SYSTEMS J. LONGO AND MODELS

- DEST ESTIMATE ANALYSES IN DESIGN J. LONGO

- LUNCH -

12:35 - 1:35 pm B. NRCS AFF PRESENTATION 30 MIN.

1:35

- 2:35 pm IV. ACRS CONCLUDING REMARKS AND M. BENDER 10 MIN.

2:35

- 2:45 pm DISCUSSION OF FUTURE AGENDA ITEMS V. ADJOURN 2:45 pm

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"CE S S A R-F" (COM BUSTION ENGINEERING STANDARD SAFETY ANALYSIS REPORT - FSAR) i l

CESSAR-F IS THE LIbENSING DOCUMENT TH T DESCRIBES THE SYSTEM 80 NSSS DESIGN 1

j

4 I

NRC POLICY STATEMENT ON STANDAR DIZATION i

1 l

t OPTIONS:

4 REFERENCE SYSTEM CONCEPT l

DUPLICATE PLANT CONCEPT I

MANUFACTURING LICENSE CONCEPT REPLICATE PLANT CONCEPT i

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l

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NRC POLICY STATEMENT 1

ON STANDAR DIZATION l

l OPTIONS:

PRELIMINARY DESIGN APPROVAL (PDA)

REFERENCE SYSTEM CONCEPT FINAL DESIGN APPROVAL (FDA)

DUPLICATE PLANT CONCEPT i

MANUFACTURING LICENSE CONCEPT i

i REPLICATE PLANT CONCEPT i

i 1

4

i j

CESSAR-P WAS REFERENCED BY:

4 i

{

ARIZONA PUBLIC SERVICE

]

P A LO VER DE 1, 2,

3, 4,

&5 WASHINGTON PUBLIC POWER SUPPLY SYSTEM WPPSS 3 & 5 4

TENNESSEE VA LLEY A UTHORITY YELLOW CREEK 1 & 2 DUKE POWER COMPANY CHEROKEE 1, 2,

&3 PER KINS 1, 2,

&3 i

NEW YORK STATE ELECTRIC AND GA S NEW HAVEN 1 & 2

PRESENT SYSTEM 80 CUSTOMERS EXPECTED TO REFERENCE CESSAR-F CONSTRUCTION UTILITY PLANT No. OF UNITS PERMITISSUED ARIZONA PUBLIC SERVICE PALO VERDE NUCLEAR 3

MAY 1976 (APS)

GENERATING STATION (PVNGS),

WASHINGTON PUBLIC POWER WPPSS NUCLEAR PROJECT 2

APRIL 1978 SUPPLY SYSTEM (WPPSS) lENNESSEE VALLEY YELLOW CREEK 2

NOVEMBER 1978 AUTHORITY (TVA)

DUKE POWER COMPANY CHEROKEE 3

DECEMBER 1977 PERKINS 3

PENDING

. - ~

l ANTICIPATED FSAR LICENSING SCHEDULES l

FOR PRESENT SYSTEM 80 OWNERS i

OL

_ HER0KEEIPERKINS _

C l

YELLOW CREEK OL

=

I WNP 3/5 OL l

I I

PVNGS OL I

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CESSAR-F l FDA

=

1 1

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i 78 79 80 81 82 83 84 85 86 87 88 89

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CESSA R-F IS A PPLYING FOR FDA-1 i

ADDRESSES ALL APPLICA BLE NRC GUIDELINES EVEN i

AFTER CUT-0FF DATE I

REFERENCEA BLE IN OPERATING LICENSE (0L) APPLICATIONS FOR PLANTS WHICH REFERENCED PDA AT CONSTRUCTION PERMIT (CP) STAGE i

REFERENCEABLE IN NEW APPLICATIONS FOR CP OR COMBINED CP/FDA UNTIL EXPIRATION l

l

i l

CESSAR DOES REPRESENT IMPLEMENTATION OF OUR i

STANDARDIZATION PHILOSOPHY j

I "IF IT IS NOT NECESSARY TO CHANGE - IT IS NECESSARY NOT TO CHANGE" 4

O t

e a

STANDARDIZATION DOES NOT REPRESENT A

PERMANENTLY FIXED DESIGN i

IT REPRESENTS A DESIGN THAT IS UPDATED AT SPECIFIC IN

RARF RYSTFMS lilTHIN CESSAR-F LICENSING SCOPE

- REACTOR

- REACTOR COOLANT SYSTEM

- SAFETY INJECTION SYSTEM

- REACTOR PROTECTION SYSTEM

- ENGINEERED SAFETY FEATURES ACTUATION SYSTEf1

(

- FUEL HANDLING _ SYSTEM

- SHUTDOWN COOLING SYSTEM

- CHEMICAL AND VOLUME CONTROL SYSTEM

- SUPPLEMENTARY PROTECTI0i1 SYSTEM t.

l r

SUPPORTIffs SYSIBIS

WITHIN CESSAR-FLICENSING5 COPE

- C0llTROL SYSTEMS

- MONITORING SYSTEMS

- CONTAINME!1T ISOLATION SYSTEM

- NUCLEAR li1STRUMENTATION

(

- STARTUP TEST GUIDELINES

~

l

'THESE SYSTEMS APPLY ONLY TO THE BASE SYSTEMS FROM THE PREVIOUS SLIDE.

INTERFACE CATEGORIES A.

POWER B.

PROTECTION FROM NATURAL PHENOMENA C.

PROTECTION FROM PIPE FAILURE D.

MISSILES E.

SEPARATION F.

INDEPENDENCE G.

THERMAL LIMITATIONS H.

MONITORING I.

OPERATIONAllCONTROLS g

J.

INSPECTION AND TESTING K.

CHEMISTRY / SAMPLING L.

MATERIALS M.

SYSTEM / COMPONENT ARRANGEMENT N.

RADIOLOGICAL WASTE 0,

0VERPRESSURE PROTECTION P.

RELATED SERVICE 0.

ENVIRONMENTAL R.

MECHANICAL INTERACTION BETWEEN COMPONENTS m-p

.,,y

mm NEW lICFNRING GUIDELINES

- L'IST OF " ADDITIONAL MATTERS" ISSUED BY REGULATORY REQUIRE-MENTS REVIEW COMMITTEE (RRRC) IN OCTOBER 1978 ADDITIONAL MATTERS" CONSISTED OF REGULATORY GUIDES, STAN-DARD REVIEW PLANS, AND BRANCH TECHNICAL POSITIONS ISSUED l

AFTER AllGUST 1974

- CATEGORIZED BY RRRC ACCORDING TO SAFETY SIGNIFICANCE MATTERS" ADDRESSED IN APPENDIX A 0F CESSAR-F

- APPENDIX A UPDATED IN 1981 i

TMI REQUIREMENTS (NUREG-0737) l

- ADDRESSED IN APPENDIX B 0F CESSAR-F i

- LIMITED TO NUREG-0737 ITEMS AFFECTING SYSTEM 80 NSSS 4

- MAJOR IMPACT ON SYSTEM 80:

ACCIDENT MONITORING SYSTEM i

4

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ENVIRONMENTAL QUALIFICATION (NUREG-0588)

I SYSTEM 80 IS IN CATEGORY I 0F NUREG-05'88 I

ADDRESSED IN C-E TOPICAL REPORT REFERENCED BY CESSAR-F 8

1 i

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REEULATORY UPDATE

SUMMARY

NRC REQUIREMENTS UP TO AUGUST 197/1

+-

" ADDITIONAL MATTERS" THROUGH 1981

+

TMI REQUIREMENTS (NUREG-0737)

+

=

ENVIRONMENTAL QUALIFICATION (NUREG-0583)

SYSTEM 80 NSSS WilICH MEETS ALL CURRENT NRC REQUIREMENTS

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1 1

UNIQUE FEATURES OF SYSTEM 80

1. CORE OUTLET FLOW VIA CALANDRIA REGION

2. CONTROL R0D GUIDANCE AND SHROUDING j

3. EGGCRATE CORE LOWER SUPPORT STRUCTURE l

4. AXIAL-FLOW ECON 0MIZER SECTION IN STEAM l

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SYSTEM 80 LOWER SUPPORT STRUCTURE

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OTHER FEATURES i

1.

BOTTOM - MOUNTED IN - CORE INSTRUMENTATION (FIXED PLUS MOVA BLE) 2.

SUPPLEMENTARY PROTECTIVE SYSTEM 3.

DOUBLE OUTLET N0ZZLES ON STEAM GENERATORS CONTAINING INTEGRAL FLOW RESTRICT 0RS i

i i

G t

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n.

I COMPARISON OF PARAMETERS AFFECTING CORE PERFORMANCE

, BETWEEN SYSTEM 80 AND EARLIER PLANTS PARAMETER ANO-2 SONGS 2,3 SYSTEM 80 CORE POWER, MWT 2,815 3,390 3,800 NUMBER OF FUEL BUNDLES 177 217 241 AVERAGE POWER PER FUEL BUNDif, MWT 15.9 15.6 15.8 COREINLETTEMPERATURE, OF 553.5 553.0 565.0 CORE AVERAGE MASS VELOCITY, 2

6 6

LBMlHR-FT 2.60 x 10 2.61 x 10 2.61 x 106

~

COMPARIS0N OF PARAMETERS AFFECTING CORE PERFORMANCE BETWEEN SYSTEM 80 AND EARLIER PLANTS i

j PARAMETER ANO-2 SONGS 2, 3 SYSTEM 80 2

5 5

5 AVERAGE HEATFLUX, BTUIHR-FT 1.89 x 10 1.88 x 10 1.89 x 10 R0D RADIAL PEAKING FACTOR (DESIGN) 1.55 1.55 1.55

(

AVERAGE LINEAR HEAT RATE, KWlFT 5.52 5.47 5.53 ALLOWA BLE PEAKING FACTOR 2.57 2.48 2.48 ALLOWABLE PEAK LINEAR HEAT RATE, KWIFT (AT 102% POWER) 14.5 13.9 14.0

i 1 +

ALTERNATE DHR CAPABILITY SECONDARY FEED AND BLEED STEAM GENERATOR DEPRESSURIZATION WITH ATMOSPHERIC DUMP VALVES.

FEEDWATER MAKEUP USING LOW HEAD PUMP (E.G. FIRE PUMP),

1 l

l 1

I SECONDARY FEED AND BLEED FEATURES:

1.

RCPB iMiliTAINED INTACT 2.

CONSISTEliT WITH NORiML DHR PROCEEDURES 3.

DOES iiOT REQUIRE PRIMARY DEPRESSURIZATION.

1 4.

g TIME FOR OPERATOR ACTI0li IS AVAILABLE.

5.

EQUIPMENT IS ACCESSIBLE.

e I

i

QUALIFIED SAFETY PARAMETER DISPY SYSTEM, (QSPDS) BLOCK DIAGRAM t

i l

l OTHER IE PLASMA ACCIDENT MONITORING INPUTS DISPLAY HDT LFG TEMPERATURE PROCESSING

~

DISPLAY COLD LFG TEMPERATURE MARGIN i

PRESSURIZFR PRESSURE M0filTOR CORE EXIT THERM 0COUPIFS CORE EXIT THERMOCOUPLES

- ' EATEU JU5CTIUN

' ~

H HEATED JUNCTION THERM 0 COUPLES THERMOCOUPLE SYSTEM

.6 l HEATED JUNCTION THERMDCOUPIF POWER HEATER CONTROLLER l

CHANNEL - A CRITICAL FUNCTION MONITORING SYSTEM t

) CHANNFI - B INPUTS QSPDS CHANNEL - B DISPLAY

NSSS DIFFERENCES IMPORTANT TO SAFETY TYPICAL ANALOG PARAMETER PLANT SYSTEM 80 POWER, MwT 2560 3800 Fa 5 1.7 5 1.63 r

ASI

.3

.3 6

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6 CORE FLOW, tan /sa 139x10 157x10

% RANGE 100-110 95-116 T nter, F

540-551 560-570 i

RCS PRESSURE, PSIA 2150-2350 1785-2400

i NSSS DIFFERENCES IMPORTANT TO SAFETY (CONTINUED)

=.n TYPICAL ANALOG PARAMETER PLANT SYSTEM 80 MTC,10-4 ao/F 12 *-2.9 0.* -3.5 CEA WORTH, %AP AT FP

-5.7

-8.8 RV CLOSURE HEAD q

VOLUME, FT3 1300 2000 HPSI SHUT 0FF HEAD, PSIA 1300 1750 SIT PRESSURE, PSIA 600 600 STEAM GENERATOR NO N0ZZLE FLOW YES RESTRICTORS PRESSURIZER RELIEF CAPACITY,106 LB/HR 0.6 2.0 SURGE LINE EFFECTIVE LENGTH, FT 330 441

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=

700 p

600 Y

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SYSTEM 80 AFFECTED COLD LEG e

5 g

400 u

5b b

300,

ANALOG AFFECTED SG COLD LEG 200 0

100 200 300 400

-500 TIllE, SECONDS FULL POWER LARGE STEAM LINE BREAK WITH CONCURRENT LOSS OF 0FFSITE POWER REACTOR COOLANT TEMPERATURE vs TIME

ML20040E242

Text

SUMMARY

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