ML19312A224

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App a of S&W SWESSAR-P1, Encl Bldg W/O Mixing.
ML19312A224
Person / Time
Site: 05000495
Issue date: 12/29/1978
From:
NEW YORK STATE ELECTRIC & GAS CORP., STONE & WEBSTER, INC.
To:
References
NUDOCS 7909060021
Download: ML19312A224 (53)
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SWESSAR-P1 APPENDIX A ENCLOSURE BUILDItU WITHOITF MIXING LIST OF EFFECTIVE PAGES Page, Table (T) , Jtwrdment Page, Table (T) , a:nendInent or Fiqure (F) No. or Fiqure (F) No.

A-a 39 A-i 23 A-ii 33 A-iii 7 A-1/2 18 A-2A 18 A-3 18 A-4 23 A-5/6 34 A-7/8 18 T A2.3.4-3 22 T A6.2.3.1-1 7 T a6.2.3.1-4 18 T A8.3-1 (W) (3 sheets) 20 T A8.3-2 (W) (2 sheets) 20 T A8.3-1 (W-3S) (3 sheets) 20 T A8.3-2 (W-3S) (2 sheets) 20 T n8.3-1 (BLW) (3 sheets) 20 T A8.3-2 (B&W) (2 sheets) 20 T AB .3-1 (C-E) (3 sheets) 20 T A8.3-2 (C-E) (sheet 1) 20 T AB .3-2 (C-E) (sheet 2) 7 T A15.1.13-2 18 T A15.1.23-3 33 F A3.8.4-1 7 F A6A.3.2-1 23 F A6.2.3.1-1 21 F A6.2.3.1-2 18 F A9.4-1 21 F A15.1.13-2 19 F A15.1-13-3 (3 sheets) 19 F A15.1.13-4 19 F A15.1.13-5 19 F A15.1.13-8&9 23 A-a Amendment 39 7/14/78

SWESSAR-P1 APPENDIX A I ENCLOSURE BUILDI?G WITHOUT MIXI?G TABLE OF CONTENTS Section Pace A

1.1 INTRODUCTION

A-1 A1.2.3 Structures A-1 A2.3.4 Short Term (Accident) Diffusion Estimates A-2 A2.6 INTERFACE REQUIREME?TTS A-2 A3.8.4 Other Category I Structures A-2A A3.8.u.1 Description of the Structures A-3 A3.8.4.4 Design and A.'alysis Procedures A-3 A6.2.3.1 Supplementary Leak Collection and Release System A-4 A6.2.3.1.1 Design Bases A-4 A6.2.3.1.2 System Design A-4 A6.2.3.1.3 Design Evaluation A-4 A6A.3 Analysis of SLCRS Performance A-4 23 A6A.3.2 Extiltration Analysis A-4 A15.1.13 Loss of Coolant accident A-5 A16.4.4 Containment Structure Leakage Rate Tests A-5 A-i '

Amendment 23

(,]p, 3/31/76

SWESSAR-P1 LIST OF TARTRS Table

_A2.3.4-3 A Set of Limiting LPZ Outer Boundary Atnospheric D_ispersion Factors A6.2.3.1-1 Supplementary Leak Collection and Release System Component Design and Performance Characteristics A6.2.3.1-4 Design Parameters for Areas Served by SIERS A8.3-1 Loading Capacity in Horsepower AB.3-2 Emergency Diesel Generator Loading on Loss of Offsite Power Plus DBA A15.1.13-2 Parameters Used for the Ioss of d>olant Accident

_ Analysis 33 A15.1.23-3 Fuel Handling Accident in Containment Thyroid D_ose

/ /f \ l O ! u; LJJ (L

W A-il Amendmerit 33 6/30/77

SWESSAR-P1 LIST OF FIGURES 1

Ficure A3.8.4-1 Arrangement Enclosure Bui.7. ding Containment Structure, Option A A6.2.3.1-1 Supple.nentary Leak Collection and Release System A6.2.3.1-2 SLCRS Pulldown Time A9.4-1 Reactor Plant Ventilation A 15.1.13-2 Loss of Coolant Accident, Dose vs CHI /Q, 2 Hour Dose I

at Exclusion Boundary A15.1.13-3 Loss of Cooldnt Accident, Dose vs CHI /Q, 30 Day Dose at Low Population Zone, Sheet 1 A 15 .1.13 -3 Loss of Coolant Accident, Dose vs CHI /Q, 30 Day Dose at Low Population Zone, Sheet 2 A 15 .1.13-3 Loss of Coolant Accident, Dose vs CHI /Q, 30 Day Dose at Low Population Zone, Sheet 3 A 15 .1.13 -4 Loss of Coolant Accident, Dose vs Distance, 2 Hour Dose at Exclusion Boundary A 15 .1.13 -5 Loss of Coolant Accident, Dose vs Distance, 30 day Dose at Low Population Zone A-iii Amendment 7 2/28/75 e7c ,, ,

( ..

SWESSAR-P1 A2.3.4 Short Term (Accident) Diffusion Estimates The short term diffusion estimates are described in Section 2.3.4 with two modifications under Option A as discussed below.

The limiting exclusion area boundary short term (0-2 hr) atmospheric dispersion factor, CHI /Q, for the Option A design of g the Reference Plant is approximately 9.0 x 10-* sec/m3 (B&W, CE, less than or W) . For sites with an exclusion boundary CHI /Q equal to this value, the 0-2 hr doses at the exclusion area boundary will be less than the 150 Rem and 20 Rem thyroid and whole body doses, respectively, as discussed in Regulatory Guide 1.4 (Section 3A.1-1.4) .

IB A set of limiting low population zones (LPZ) outer boundary CHI /Qs (B&W, CE , W) for the Option A design of the Reference Plant is given in Table A2.3.4-3. For sites with an LPZ CHI /Q for each time interval less than or equal to the corresponding CHI /Q given in Table A2.3.4-3, the 30 daf doses at the LPZ will be less than the 150 Rem and 20 Rem thyroid and whole body doses, respectively, as discusced in Regul:2:ory Guide 1.4 (Section 3A .1-1. 4) .

A lower power level for W-3S results in a slight increase in the 18 limiting CHI /Qs. The limiting CHI /Qs will be addressed in the Utility-Applicant 's SAR.

A2.6 INTERFACE REQUIREMENTS

.Interf ace requirements for Option A are given in Section 2.6 with substitution of the following information for atmospheric dispersion factor CHI /Q.

Atmospheric Dispersion Factor (CPI /0)

The maximum value at the exclusion area boundary:

9.0 x 10-* sec/m3 The maximum value at the low population zone outer boundary:

Refer to Table A2.3.4-3.

These values are flexible within the limits stated in Section A2.3.4.

The following relation must hold:

IB X/Q)1 xA $1 --T (X/Q) { ((j []'}  ?'

A-2 Amendment 16 10/30/75

SWESSAR-P1 where (X/Q) = X/Q for the worst 5 percent meteorology (X/Q)2 =occurs X/Q for any windspeed at which exfiltration 18 A = ratio of the iodine release with exfiltration I

to the iodine release without exfiltration as given in Fig. A15.1.13-8.

A3.8.4 Other Category I Structures The following s ections are added to the text for the Option A enclosure building.

A-2A Amendment 18 10/30/75 6_/ 0 236

SWESSAR-P1 A6.2.3.1 Supp:amentary Leak Collection as/ Release System The f unction ci the SLCRS is as stated in Section 6.2.3.1. Under (

Option A the SLCRS collects leakage into the enclosure building in addition to the annulus building, fuel building, main steam and feedwater valve areas, and electrical tunnels in the annulus building as shown in Fig. A6.2.3.1-1. Principal component design parameters are given in Table A6.2.3.1-1.

A6.2.3.1.1 Design Bases The design bases of the SLCRS are as listed in Section 6.2.3.1.1.

A6.2.3.1.2 System Design The SLCRS under Option A is designed to collect leakage into the enclosure building in addition to the annulus building, main steam and feedwater valve areas, and electrical tunnels in the annulus building and fuel building. The system is designed to function with the enclosure building isolated, if necessary. The flow diagram (Fig. A6.2.3.1-1) indicates all spaces served by this system. The free volume, design leakage rate, and exhaust rate for each area are listed in Table A6.2.3.1-4. The remainder of the system design description is as discussed in Section 6.2.3.1.2.

A6.2.3.1.3 Design Evaluation The design evaluation for the SLCRS is as described in Section 6.2.3.1.3 with the f ollowing modifications :

1. The SLCRS collects leakage to the enclosure building (Fig . A6.2. 3.1-1) .
2. The SLCRS pull-down time with enclosure building is shown in Fig. A6.2.3.1-2.

A6A.3 Analysis of SLCRS Perforrance For a general discussion, see Section 6A.3.

23 A6A.3.2 Exfiltration Analysis The exfiltration analysis is as discussed in Section 6A.3.1. The exfiltration rates as a function of wind velocity with an enclosure building are shown on Fig. A6A.3.2-1.

/

A-4 Amendment 23

- r , - . 3/31/76 b/d CJ/

SWESSAR-P1 A15.1.13 Loss of Coolant Accident 1

he loss of coolant accident is as described in Section 15.1.13 except that Section A6A.3, Table A15.1.13-2, and Fig. A15.1.13-2,-3,-4,-5,-8, and -9 are used in place of Section 6A.3, Table 15.1.13-2, and Fig. 15.1.13-2,-3,-4,-5, 8, and -9 respectively.

A16.4.4 Containment Structure Leakage Rate Tests

@e applicability, objectives, and specifications for this section are stated in Section 16.4.4 with the exception that Type C' tests are not required when an enclosure building is used.

The description of Type A, B, and C tests for Option A are listed below. They are adapted from section 16.4.4 with Type C' tests removed for Option A.

A. Type A Tests Pretest requirements shall cceply with paragraph III .A.1 of Appendix J except that type B and C tests shall be performed prior to the Type A test. Repairs or adjustments shall be made befort testing to correct abnormalities found in the 34 pretest inspection.

Periodic Type A leakage rate tests shall be scheduled in accord-ance with paragraph III.D.1 of Appendix J.

All Type A tests shall be conducted in accordance with ANSI N45.4-1972 "Imakage Rate Testing of Containment Structures for Nuclear Reactors" with the following exceptions:

1. Scheduling of leakage rate tests to account for the effects of weather conditions is not necessary for a concrete containment structure.
2. Leakage rate shall be calculated from a linear least squares fit to the calculated mass of containment air as a function of t, mo (refer to Section 6.2.6). An instrument error analysis shall also be performed.
3. Leakage rate shall be based on the reference volume or absolute method. The makeup air method shall be used for supplemental verification (refer to Section 6.2.6) .
4. Reference vessel system if used shall be at a pressure below 0.95 Pg at the start of a Type A test and shall remain below P3 throughout the test.

Preopera t.ional and periodic Type A tests shall be performed in accorda.nce with the peak pressure program defined in Appendix J, paragraphs III.A.4 (a) . (2) and III.A.5 (a) . (2) . Test pressure shall be as specified in Table 6.1-1, the calculated peak A-5 Amendment 34

/, 7 n '"^

' /22/77

SWESSAR-P1 containment internal pressure (P,). The design basis accident leakage rate (La ) shall be less than 0.2 weight percent per day

(

(

of the containment structure air content at pressure Pa acceptance

. The criteria for Type A tests shall satisfy the requirements of paragraph III .A.4 (b) and III .A.5 (b) of Appendix J. The measured leakage rate (L ,,) shall be less than 0.75 L a (L, < 0.15 percent per day) . Thus, the maximum allowable Type A test measured leakage rate L , is 0.15 wt %/ day.

The additional leakage testing requirements of paragraph III.A.6 of Appendix J shall be satisfied in the event of Type A test failure.

B. Tyne B Tests Preoperational and periodic Type B tests shall be performed at a teat pressure equal as P a. Test methods are described in Section 6.2.6. Type B tests on air locks shall be conducted at intervals specified in " Reactor Containment Leakage Testing Requirements ," Draft 1, by ANS Committee N274, Work Group 56.8, dated April 22, 1975, paragraph 5.3.3 (1) as follows:

" Personnel air locks shall ba tested prior to initial criti-cality and at six month intervals thereaf ter at an internal pressure of Pa. Air locks opened during periods when containment integrity is not required need be tested only c the end of at these periods. For air locks opened when containment integrity is required, the air locks shall be tested within three days after such opening.

For air locks opened more frequently than once every three days, the air locks hall be tested at least once every three days.

a. Ebr air lock doors having testable seals, testing the The seals fulfills the three day test requirements.

test pressure shall be in accordance with door manuf acturer's recommendations. Seal tests shall not be substituted for the six month air lock test.

b. For containments utilizing continuous leakage monitoring systems, only the six month testing requirements need apply to air locks."

Other Type B tests shall be conducted during each reactor shutdown for refueling at intervals not greater than two years.

O/U m

'J/

O A-6 Amendment 34 7/22/77

SWESSAR-P1 The acceptance criteria for Type B tests shall satisf y the requirements of paragraph III.B.3 of Appendix J. The total of Type B and C measured leakage shall be less than 0.6 L ,

which equals 0.12 percent per day. "

C. Type C Tests Preoperational and periodic Type C tests shall be performed at a test pressure equal to P . Test methods are described in Section 6.2.6. Type C tests shall be conducted during each reactor shutdown for refueling but in no case at intervals greater than two years. The acceptance criteria for Type C tests shall satisfy the requirements of paragraph III.C.3 of Appendix J. The total of Type B and C measured leakage shall be less than 0.6 L ^, which equals 0.12 percent per day.

D. Speciul Testing keouirements Type A, B, and C tests , as applicable, shall be conducted following containment structure modifications in accordance with paragraph IV (A) of Appendix J.

E. Inspection and Reporting on Tests 18 A general pretest inspection of the containment structure shall be performed in accordance with paragraph V ( A) of Appendix J. Technical reports for preoperational and periodic tests shall be submitted in accordance with the requirements of paragraph V (B) of Appendix J.

Bases

1. Appendix J to 10CFR50
2. The maximum allowable containment leak rate (L a ) of 0.2 percent per day is chosen to ensure that the radio-logical consequences of the design basis accident are below the limits suggested in 10CFR 100.
3. The maximum allowable measured leakage rate (Lam ) is 0.15 percent / day.

The basis for these values is as follows:

Ld = Primary containment design leak rate 0.2 wt

%/ day Lg = Maximum allowable primary containment leak rate = 0.2 wt %/ day e7e ,.

o/U J40 A-7 Amendment 18 10/28/75

SWESSAR-P1 L am = Maximum allowable measured primary 0.75 = 0.15 wt -

containment leak rate = La

%/ day However, the radiological consequences of an accident are b6 sed on no uncollected leakage and 0.2 percent per day leakage that is collected and treated before release.

18 4. Type B and C tests ensure that leakage through is less contain-than ment isolation valves and penetrations 0.6 L . This provides a high probabilif.y that the Type A measured leakage rate (Lam) will be below 0.75 Lg.

The peak containment internal pressure related to the 5.

design basis accident (P, ) is calculated by means of the LOCTIC computer code as described in Section 6.2.1.

g g ;/ r Ue t- f A-8 Amendment 18 10/28/75

SWESSAR-P1 TABLE A2.3.4-3 1

A SET OF LIMITING LPZ OUTER BOUNDARY ATMOSPHERIC DISPERSION FACTORS Time Interval CHI /O (sec/m3 )

0-8 hr 2.7x10-*

8-24 hr 1.2x10-* l2 2 1-4 days 4.1,~9-5 4-30 days 9.0x10-*

1 of 1 Amendment 22

,c.9

,, ,c 3/17/76 (37 0

SWESSAR-P1 1 TABLE A 6.2.3.1-1 SUPPLEMENTARY LEAK COLLECTION AND RELEASE SYSTEM COMPONENT DESIGN AND PERFORMANCE CHARACTERISTICS Design and Performance Component Characteristics

1. Filter Bank Capacity 20,000 cfm
2. Exhaust Fan 7

Capacity 20,000 cfm Head 15 in. W.G.

Motor 70 hp

3. Charcoal Filter Decay Heat Removal Fan capacity 120 cfm Head 3 in. W.G.

Motor 1/2 hp

, 79 m ,,

O/u (_'i.)

1 of 1 Amendment 7 2/28/75

SWESSAR-P1 TABLE A6.2.3.1-4 i

DESIGN PARAMETERS FOR AREAS SERVED BY SLCRS Estimated Free Volume Leakage Fan Exhaust x106 ft3 Rates * (cfm)_ Rates (cfm)

Annulus Bldg 3.30 6,000 9,000 Fuel Bldg 0.93 2,000 3,000 18 Main Steam and Feedwater 0.16 1,000 1,500 Valve Enclosure Electrical Tunnels 0.27 1,000 1,500 in The Annulus Bldg Enclosure Bldg. 1.3 3,500 5,000 Totals 5.96 13,500 20,000

  • At 0.25 in. Hy O differential pressure 6/0 2.'44 1 of 1 Amendment 18 10/30/75

.4 - , . , , . , ,s ShtSSAR-P1 TAlt!.E A H .1- 1 IA)ADING CAI'ACITY IN HOPEFP(4fEP (UtTIESS OT!!EkWISE STATED)

NORMAL PUSE;.

13.8 KV load liun f40 IN Bus No. 2 nil Itus No. 2f;A Ilu s tio . 3N Feactor coolant pump 8,000 R,000 0,000 8,000 20 circulating water pump 7,000 -

7,000 7,000 i Cooling tower Ituel centers Later -

Later later ,

480 V norinal load centers 5,000 -

4,000 5,000 20 Condensate pump 4,000 -

4,000 4,000 C3 4,i60 v road aus No. iN eus f:o. 2N nos No. in

($,,.,Y,

,3 .

- 4th point heater drain punp 2,000 2,000 2,000 Turbine plant service water pump 1,000 1,000 1,000 a Fire pump 400 - -

in Doron evaporator reboiler pump - -

250 "3

no==

Condenser air removal 250 -

250

{p vacuum priming pump 500 -

500 {rg Tucbine plant empnent cooling 400 900 400 pump hermal reoeneration chiller cmpressor - -

250 20 Mechanical retrigeration units 650 650 650 DTEGENCY DUSES 4,160 V load flus No. 10 bus No. 2P Ims No. 3G

@ High head natety injection pump 900 900 900 C Ixw head safety injection pump 400 000 400 70 Charging pump 500 500 -

W .)

Containment spray pump 500 500 500 Ln W 1 of 1 imiri ee n t 10 1ll < fir.

SWE.S. CAR-P 1 TABIE AR .1-1 (COffr)

' sus No. 10 Inns No. 2P Ilus No. 3G Auxiliary feedwater pump 750 750 750 Reactor plant crupine ,t cooling 800 H00 800 pimg> (tkate 1)

Reactor plant service water 600 600 600 p_arp (tJotes 1S 2)

Residual heat rmoval pump 275 275 275 Control building chiller 450 450 450 4 80 V load Containment atmosphere recir- 75 75 75 culatitm tan (Note 1)

Feactor plant service water 3 moling towe r f ans (f kst e 2) later later later Fuel pool cooling pump 150 150 -

Contsul and diesel bldg IIVAC 225 225 225 Boron injection pump 150 150 -

Boric acid transfer pump 21 21 -

Baron inject ton tank recir- 5 -

culation purnp Baron injection tank heaters 12 kW 12 kW -

luiron injection surge tank 3 kW 3 kW -

heaters Pressurizer heaters caratrol -

480 kW -

group Pressurizer heaters backup 810 kh -

810 kW group NJ CD bJ J. u O

N 2 of i 13.*ndm. n t 20 1/23/7h

SkTSSr R-P 1 TAblJ. A tl .1 - 1 (COffr) fus tks. TO Ihts No. 2P Ilus tui. 'IG Battery chargers 100 kW 100 kW 200 kW lleat tracing 100 kW -

100 kW 11ydrogen record >iner 10 kW 10 kh -

Motor operated valves later Later Later E*usent ial lighting 75 kW 75 kh 75 kW Supplementary leak collection 172 kW 172 kW and release systesn 20 Control sud drive cooling f an 25 25 50 Positive displacerrent pump - - 100 Diesel generatur fuel pump 5 5 5 Diesel generator lube oil ptop 10 10 10 Diesel starting air com- 15 15 15 pressors (Note 1)

Diesel generator circulating Later Tater Later water pump 12nergency Generator Continuous rating 5,500 kW 5,500 kW 5,500 kW CN N

C FJ zu

'-l Note 1. TWo UK) tors of the giVen horsepower are proviJed per tals.

Note 2. Dependent. on site.

W 1 <.f 3 TJwn Doo m t 20 1- Fe,

SWES StJ< -P 1 TABLE A8.3-2 UtEFGENCY DIESEL GENEFA*IVI' LOADING ON IDSS OF OFFSITE POWEP PLUS DFF.

Aut o Se<1uance Timin<t- loading Ier Diesel Load DescrMion St art Sec i1) lip (21 Iw ( 3)

High head saf ety injection grunp Yes 10 900 750 Low head saf et y in jection purep Yes 5 400 330 Containment sg. ray pump Yes 30 500 415 20 Reactor plant coengwnient cooling Yes 20 600 500 '

PN Reactor plant service water pump Yes 25 1,000 (4) 830 Auxiliary f eedwater purup Yes 15 750 625 Cbntairusent atmosphere recir- Yes 0 75 63 7, culation tan Reactor plant service water Yes 0 600 500 Cooling tower f ans (Note 4)

Fuel pool cooling pump No -

150 125 Boric acid transfer pump No 60 min 20 17 lioron injection purnp Yes 0 150 125 Supplementary leak collection and Yes 0 172 release systen Battery chargers Yes 0 -

60 Essential lighting Yes 0 -

75 Valves (motor olierated) Yes 0 100 85 Heat tracing No 5 min -

100 Control and diesel building HVAC Yes 0 675 565 10 Doron injection surge tank No - -

3 heaters CN y Ilydrogen recombiner No - -

10 Diesel generator auxiliaries Yes 0 50 ti l Total Est irnut ed load 5,391 V' )

W I of '/ /em n d m" sit 10 1 '1 1/ 11.

SWESSAF-P1 TALIl AB.3-2 (CONT)

NUTES:

(1) Maximum time to close the breaker with zero as the time when enernency diesel generat or energizes the bus (2) llorsegewer required at driven equipment (3) F.M input t o electric mtor = Inad in hp x 0.746 0.9 averaqe for mtor ef ficiency (4) Dependent on sit e t

t CT N

CD b)

~

G w 2 of / An..nar. n t 50 17 1/7,

SWESSAR-P1 TABLE A8.3-1 LOADING CAPACITY IN !!ORSETOWER (UNLESS OTIIERWISE STATED)

NORMAL BUSP.S 13.8 KV Inad Bus No. 1N Bus No. 2ND Bus _No. 2NA Bus No. 3N Heactor coolant pump 7,000 7,000 7,000 7,000 Circulating water pump 7,000 -

7,000 7,000 Cooling tower load centers Lacer -

1,it er Later 480 V normal load centers 5,000 -

4,000 5,000 Condensate p.nnp 4,000 - 4,000 4,000 4,160 V Imd Bus No. IN Bus No. 2N Bus No. 3N 4th point heater drain pump 1,250 1,250 1,250 Turbine plant service water pump 1,000 1,000 1,000 78 Fire punp 400 - -

Doron evaporator reboller - -

250 punp Condenser air removal 250 -

250 Vacuum priming pump 500 -

500 Turbine plant cruisponent cooling 400 400 400 IMP

'Iternal regeneration chiller - -

250 cumprassor Mechanical ref rigeration units 650 650 650 EMERGmCT BUSES C 4,160 V 10ad Bus No. 10 Bus No. 2P Safety injection pump 400 400

p. .

Pesidual heat removal pump  %'. 450

.}

C Charging ptanp (Note 3) 600 600 Containment spray ptnnp 650 650 W-3S 1 of 3 Aren twnt 20 1/?t/76

SWESSAR-P1 TABLE A8.3-1 (CONT)

Dus No. _12 Bus No. 2P Auxiliary f eedwater pianp 750 750 Reactor plant ctmponent cooling 700 700 A pump Reactor plant emponent cooling 1,300 1,300 B P2P Reactor plant service water 600 (00 pump (Note 2)

Reactor plant service water 800 800 D pump (Ned e 2)

Control building chiller 450 450 (Note 3) 480 V Ioad 70 Containment atinosphere recircu- 75 75 lation fan (Note 4)

Reactor plant service water cooling tower fans (Note 2) Later Later Fuel pool enoling pump 150 150 Control and diesel b1dg INAC 225 225 Doron isajection pump 150 150 Doric acid transfer ptamp 15.5 kW 15.5 kW Doron injection recirculation 2.5 2.5 PmP 0% Doron injection tank heaters 12 kW 12 kW C Doron injection surge tank heaters 3 kW 3 kW Pressurizer heaters control group - 400 kW B _) Pressurizer heaters backup group 700 kW 700 kW (3

~

Dattery chargers 200 kW 200 kW Heat tracing 100 kW 100 kW W-3S 2 of 3 Anen1-ent 70 1 /

  • I /~f 5

SWESSAR-P1 TALLE A8.3-1 (Cotrr)

Bus No. 10 Pus No. 2P If ydrogen rectxnbiner 10 kW 10 kW Motor operated valves Lat er Iater Essential lighting 75 kW 75 kW Supplementary leak collection 172 kW 172 kW dnd release System control rol drive cooling fan 70 70 Diesel generator f ucl immp 5 5 Diesel generator lube oil pump 10 10 28 Diesel starting air ccxnpressors 15 15 (Not e 1)

Diesel generator circulating water Later Iater Pump Emergency Generator Continuous rating 6,000 kW 6,000 kW J.

' ' Two motors of the given horsepower are prmrided per bus.

Note 1.

N Note 2. Dependent on site.

Note 3. One spare motor of the given horsepower is additionally provided which can be manually connected to either of the two emergency inanes.

Note 4 Four motors of the given horserwwer are provided per bus.

W -3 S 3 of 3 Am.ndw nt 20 1 *If/6

SWP.SSAR-P1 TABLE A8.3-2 PEERGENCY DIMEL GENERA 1DP LOADING ON IDSS OF OFFSITE IUWER PLUS DBA Auto Sequence Tinti ng- Insd i ng Per Diene _-1 Innd Deseription St att See fIl fily d. KWlQ Charging pump Yes 5 660 550 Safety injection pump Yes to 420 350 Cbntainment spray pump Yes 30 650 540 Reactor plant ccx:rponent moling Yes 20 1,300 1,080 B pump Reactor plant service water B pump Yes 25 800 (4) 665 Auxiliary feedwater pump Yes 15 750 625 Residual heat removal pump Yes to 450 375 Containment atmosphere recir- Yes 0 75 63 0 culation fan deactor plant service water Yes 0 600 500 moling tower fans (Note 4)

I'uel pool cooling pturp Nr, -

150 125 Svuplementary leak collection and Yes 0 172

. lease system Battery chargers Yes 0 -

60 Essential lighting Yes 0 -

75 Valves (antor operated) Yes 0 100 85 Heat tracing No 5 min -

100 Control and diesel building INAC Yes 0 675 565 C% lioron inje<7_lon surge tank No 10 min -

6 N heaters CD Ilydrogen recornbiner No - -

10 Diesel generator auxiliaries Yes 0 50 43 BJ

(,1 Total Est inuted Load -

5.989

(,*J W-3S 1 of 2 Ame r+ en t 20 1/ ? e 7 7*.

SNESSAR-P1 TABLE A8.3-2 (CONT)

NCYTES:

(1) Maximura tinw= to close the breaker wit h zero as the time when energency diesel generator energizes the bus. 70 (2) Ilorsepower required at driven equipment (3) KW input to electric motor = Inad in hp x 0.746 0.9 average f or erntor et ficiency (4) Dependent on site N

O r- J L "

1 of 2 nmendr.mt 20 W-1S 3 ,q . ,

SNESSAR-P 1 TABLE AR.3-1 f IDADI!JG CAPACITY IN IR)RSEPOWER (UNLESS (rrlitJNISE STATED) 40FMAL ISUSES 13.8 KV Inad In s No. IN Pus No. 2 Nil flus No. 2NA Bus tkm. 1N Re actor coolant pump (Not e 2) 12,500 12,500 12,500 12,500 Circulating water pump 7,000 -

7,000 7,000 Cooling tower load centers Later -

Later Later 480* normal load centers 4,000 -

4,000 4,000 Coadensate pump 4,000 - 4,000 4,000 4,160 V Inad Bus t30. IN nus tkm. 2N Bus No. 3N Condenser air resixwal 250 250 250 4th point heater drain pump 2,000 2,000 2,000 3 Turbine plant service water pump 1,000 1,000 1,000 Fire pump -

400 -

Tur bine plant cmponent cooling 400 400 000 PNP Mechanical refrigeration units 650 650 650 FJtERGFNCY PUSFS 4,160 V Inad luss No. 1Q Iha s th > . 2P

1. tilqh head saf ety injection 900 900 pep /inakeup pump (tk>te 4)
2. Inw head saf et y injection pmp/ 700 700 Intr pump
3. Contaninment spray pun.p 1,000 1,000 C' 4. Auxiliary feedwater putp 1,000 1,000

~~j C7 5. Reactor plant comIw>nent cuxTling 1,500 1,500 pump (t;ot e 1)

6. React or plant nervice water 1,000 1,000 I' ) pump (Not e 1)

L 'l LJ 's Btw 1 of 1 Ar nament 20 1/2 t/ 76

SWESSAP-P1 TAllIE A8. 3-1 (CUPTP)

Pus th). 10 Pus No. 21'

7. Control 1milding chiller pump 450 450 4 80 V Ig1
1. Puel piol cuoling pump 150 150
2. Contr ol armi diesel blog IIVAC 225 225
3. Ik>ric aci t pump 3 3 .
4. Reactor plant service water I-s t e r Later cooling tower f ans
5. Pressurizer heate rs backup 726 kW 726 kW yroup
6. Pressurizer heaters control -

290 kW group

7. nattery chargers 200 kW 200 kW
8. Ileat tracing 100 kW 100 kW
9. Ilydrogen recombiner 65 kW 65 kW
10. Motor operat ed valves I-it e'r later
11. Essential lighting 75 kW 75 kW
12. Supplesnentary leak collection 172 kW 172 kW and release system
13. Control rod drive cooling f an 50 50 I t4 . Containment atm> sphere re- 75 75 circulation tan (not e 3)
15. Diesel generator lube oil pump 10 10

& 16. Diesel generator starting air unnpt e s sur s (Not e 1) 15 15 C 17. Diesel generator circulating water pump I.a t e r fater b)

L7 IGW 2 of 3 /ev r td o r r. t 20 1/ 21/7 ti

SwFf>SAR-P1 TABIE A8.3-1 (COhT)

Bus No. 10 Pus No. 2P Enw=rgency Generat or Continuous rating 7,000 kW 7,000 kW 23 Note 1. Twn motors of the given horsep w r are provided per Inns.

Note 2. Cbid running capacit y given.

Ik>t e 3. Four rnotor s of t he given inersepower are provided ler bus.

!*>t e II . One spare motor of t he given luirsepower is providal which can te m.inually cunnect ea t o either of the t wo ern. rgency buses.

Ox

'd C:

63 L7 nsw 3 of 3 reendment 20

,j 1/21/76

SWESSAR-P1 TABLE A8.3-2 EPOJtGl.tCY DIFSPL CENTRATOR IDADING ON IDSS OF OFFSITE POWElf PIUS DBA Ayato Sequy ce Timinq- Inad irvi Per Diesel 14Md Description Start Sec (1) HP (Not e 2) FW (Note 3)

Yes 5 900 747 liigh head saf ety injection ptmep/inakeup pump Iow head safety injection pump /DHR pump Yes 10 700 581 Yes 30 1,000 830 Oantainment spray pump Yes 20 1,500 1,245 Reactor plant cevonent cooling pump Yes 25 1,000 830 Re.sctor plant service water pump (Note 4)

Yes 15 1,000 830 Auxiliary feedwater pump Containment atJnosphere recirculation Yes 0 75 63 29 fans Yes 0 600 (t) 500 Reactor plant servim water cooling tower fans (Note 4)

No -

150 125 Fuel pool cooling ptnap No 60 min 3 3 Boric acid pump 0 172kW Supplementary leak collection and Yes release system Yes 0 -

60 Battery chargers Yen 0 -

75 Essential lighting Yes 0 100 85 Valves (r.u> tor operated)

No 5 miin - 100 lleat tracing

.~

Control and diesel lxxilding IIVAC Yes 0 675 565 Yes 0 50 43 C? Diesel generator auxiliaries No 65 Ifydrogen recvanhiner - -

6,919 p }s Tot al Estimated In.nd CO 1 of 7 A:nen hent 20 Il&W 1,'? V7 f,

8 >

7 0t 77

/

t 1 n2 e/

m1 d

n e

m.

p y

c n

e q

r e

m y n c e n h e i

w c

e i f

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  • A -

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L t s B h n t a A t e r T i m p i n e v

w s i a ru u q d a 9 eb k

ae e n0 I eh rt n e =

b v s i r ee r ot hz d ti o g t m er a c se on d i l e e r e c r t t

r i c oo uq el tt i

s a e e n er r o me r o in t te e t g w t n n

a l op p u e d

n is ze es i n n e

xe r p ai o W e

Md l l K D S w E t, T ) ) ) )

4 n U 1

(

2

(

3

( (

N 1O C' a DsC Nt%

SW ESSAIt-P 1 TABI.E A ft . 3- 1 IDADING CAPACITY IN llORSEIUWEE (ITNLFSS OT!!EishISE STATED)

NOI< PAL ICSES

13. fi KV Indil Ilus No. IN Bus No. 7 Nil Itus No. 2NA Itus No. 3N Reactor coolant pump (Note 2) 12,250 12,250 12,250 12,250 Circulating water ptmp 7,000 - 7,000 7,000 Cooling t(wer Ichid centers la t e r -

later later 480 V normal load centers 5,000 -

4,000 5,000 70 Condensate pump 4,000 -

4,000 4,000 ,

4,160 V Inad Itus No. IN Pus No. 2N Ilus No. 1N Condenser air removal 250 -

250 4th point heater drain ptmp 2,000 2,000 2,000 Turbine plant service water pump 1,000 1,000 1,000 Fire pump 400 - -

70 Boron evaporator retx>iler prunp - -

250 Turbine plant cairnponent cooling pump 400 000 400 Vacuum priming pump 500 -

500 Mechanical ref rigerat ion unit s 650 650 650 EMEPGFNCY BUSES 4,160 V Inad lius No. 1Q This No. 2P

!!igh pressure sat ety in ject ion H00 800 pump lew pressure saf ety in ject ion 500 500 pump Shutdown cooling ptwp 550 550 yo

@ Containment spray ptmp 1,000 1,000

~J Aux i)iary f cedwat c' ptm p 700 700 C ~'

Heactor plant n wnponent cooling 600 600 I' )

C' C-E 1 of 3 Amendrent 20 O 1/2 1/ 10

SWESSAR-P1 TABLE A8.3-1 (Cottr)

Bus No. 1Q Dus No. 2P A ptmp React or plant comp >nent cool- 1,200 1,200 ing 11 pump Reactor plant service water 800 800 A pump (Not e 4)

React or plant service water 1,100 1,100 Il ptm p (Not e 4)

Cont ral building chiller 450 450 480 V Imd Puel pool cx>oling pump 150 150 control and diesel b1dq IIVAC 225 225 78 Doric acid makeup pump 30 30 Reactor plot service water Inter I.it er cooling tower fans (Not e 4)

Pressurizer heaters backup 750 kW 750 kW group Pre =ssurizer heaters cont rol 150 kW 150 kW group Itatt ery chargers 200 kW 200 kW

!!ea t tracir 4 100 kW ;20 kW liydrogen recombiner 20 kW 20 kW Motor operated valves later I. iter Essential lighting 75 kW 75 kW N Supplementary leak collect ion 172 kw 172 kw a and release system control rod drive cooling fan 50 50 0 Containment atmosphere re- 75 75 1h cir cul a t ion tan (Not e 3) a C-E 2 of 3 Amendme nt 10 1/23/76

SWESSAR-P1 TABLE AB.3-1 (Cottr)

Bus No. 10 Bus No. 2E Charging pu:np 100 100 (Note 1)

Diesel generator fuel pump 5 5 Diesel generator lube oil pump 10 10 23 Diesel generator starting oil canpressors (Note 1) 15 15 Diesel generator circulating water pump later later meernency Generator Continuous rating 6,500 kW 6,500 kw Note 1. Two motors o' the given horsepower are provided per bus.

Note 2. Cold tunning capacity given.

Note 3. Four motors of the given horsepower are provided per bus.

Note 4. Dependent on site. 21 CS

- J.

C)

W3 C'

N C-E 3 of 3 Amendsw'nt 20 1/21/76

SWFliS AP-P 1 TAILLE AB . b2 EMEFGENCY DIESEL GENF.RA1DR IDAD IN(. OU 1AGS OF OFFSITE MMFR PIUS dim Auto Sequence Timing Inad i rw] Per Diesel Nud Description Start Sec (1) HJP _[Not e /1 rw (thit e 3) liigh pressure saf ety in jection pump Yes 10 800 650 low pressure saf ety injection immp Yes 5 500 405 Containment spray punip Yes 30 1,000 830 Reactor plant component cooling Yes 20 1,200 ' 9 6- 7g B pump Heactor plant service water B pump Yes 25 1,400 (Note 4) 1,162 Auxiliary f eedwater pump Yes 15 700 580 Containment. atmosphere recirculation Yes O 75 63 fans Reactor plant service water cooling Yes 0 600 (Not e 4) 500 tower fans Puel pool cooling punp No -

150 125 Boric acid makeup inunp No -

30 25 20 Supplementary leak collection and Yes 0 172 releasa syst en Battery chargers Yes 0 -

60 Essential lighting Yes 0 -

75 Valves (motor ogerated) Yes 0 100 85 lleat tracing No 5 min -

100 Control and diesel imilding IIVAC Yes 0 675 565

& 10

.d 11ydrogen recombiner No - -

20 C7 Diesel generator auxillaries Yes 0 50 41 i' ') Total Est imated Isud 6,445 l;g g ,

I (f1 C-E 1 of 2 Amen dnen t 20 1/2 3f16

SWEssiG-P 1 TABLE A8.3-2 . :'rf)

NUTES:

(1) Maximum time to close the breaker with zero as the time when emergency diesel I generator energizes the bus (2) Ibrsepower required at driven equipment (3) EM input to electric motor = Inad in hp r O.746 0.9 average for motor efficiency ,

(4) Dependent on site N

CD I' .)

C'-

-P--

C-E 2 of 2 Amendment 7 2/28/75

SWESSAR-P1 TABLE A15.1.13-2 PARAMETE' S USED FOR THE LOSS OF COOLANT ACCIDEh"r ANALYSIS The parameters listed in Table 15.1.13-2 are applicable to Option A except as noted below.

The following parameter (item 8, Table 15.1.13-2) is revised for Option A and is in addition to the parameters listed in Table 15.1.13-2. 12

8. One hundred percent of the containment leakage is collected in the supplementary leak collection release system (SLCRS) and filtered through the SLCRS HEPA filters / charcoal adsorbers with an overall efficiency for iodine of 95 percent before release to the environment .

670 ,LD c

Amendment 18 1 of 1 10/30/75

SWESSAR-P1 t

TABLE A15.1.23-3 FUEL HANDLING ACCIDEITP IN COlTTAIteiENT THYROID DOSE 0-2 hr Thyroid Dose (Rem)

CHI /Q (sec/m s) W-41 W-3S B T,W C-E 9.0 -04(s) 8.0 + 01 4.1 + 01 1.1 + 01 4.3 + 01 1.3 -03(2) 1.2 + O2 - -

6.2 + 01 1.4 -03(3) -

6.4 + 01 - -

(1) From Section A2.6 (2 ) From NUREG-0049, Safety Evaluation Report for ShT.SSAR-P1/

RESAR 41, May 1976 and NUREG-0096, Safety Evaluation Report for SWESSAR-P1/CESSAR, August 1976 (3) From NUREG-0096, Safety Evaluation Report for SWESSAR-P1/

RESAR 3S, August 1976 1 of 1 Amendment 33 6/30/77 670 206

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AR%'6 DENT EPGCSFi BJtfANG CCrJTA"?ENT STRUCTURE 7_ -t wB C sQ.'a Je 5'n' L<amm, 30evari f T a n Venamo a 'Jr'y- WXL m A ee m ===

enmuum AMENDMENT 7 2/28/75

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EXFILTR ATION R ATE AS A' ^

C. . ,

FUNCTION OF WIND VELOCITY j PWR REFERENCE PLANT SAFETY AN ALYSIS REPORT SW E S S A R - Pl L

AMENDMENT 23 3 / 31 /76

c _ _ _ , _ _ _ _ pq _

EN CLOSURE ) ,

INCLOSURE BLO Bull 0 LNG

_F ISOL ATlch DAWFERS r---,J

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FM 4 T 4 I T Y Y Y (TYP FOR 3; EL E C'T R I C AL (TYP FOR 2) ANNULUS ptN STEW AM) FEE 0 EATER TUNNELS EUllUIN,*

vtVE AREA (TYP. FOR 4 )

NOTES:

1) THIS SYSTEM 15 DESISNATED SAFETY CLASS 3 AND SEISMIC CATEGORY I AND IS LOCATED IN THE ANNULUS BUILDING EXCEPT IHERE OTHERflSE SH0ts.

i f f G l 'O Lo U

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L FUEL BLDG.

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I CIA (TYP)

' (SIGNAL TO OPEN) i d h l FRCW fuel BUILOING A EXHAUST SYSTEM

, , U EL FIG. 9.4.6-1 BULL 0 LNG FIG. A6. 2 3.1-1 SUPPLEMENTARY LEAK COLLECTION AND RELEASE SYSTEM OPil0N A PWR STANDARD PL ANT S AFETY AN ALYSIS REPORT SIESSAR-Pl q

c<i 6/0 AMEN MENT 21 2'20 76

040 9 - x

_ 030 -

T W

a __________ _ _

LEAKAGE 3

l M AIN STE AM C FEEDWATER VALVE ts.

O l ENCLOSURES 1,000 CFM u) O20 - l X ELECTRIC AL TUNNELS I,000 CFM W

g l

-}- FUEL BLDG 2,000 CFM l , ANNULUS BLDG 6,000 CFM Q

<1 I l A ENCLOSURE BLDG 3,500 CFM 0 :0 - l f  ;

if g l

lll l 38 SECONDS l

th o e i i i lli i i i i i i O 10 15 20 30 40 50 60 s e 70 80 90 100 t (SECONDS) l 10 SEC. FOR EMERGENCY DIESEL kGENERATOR TO START UP 5 SEC FOR SLCRS FAN TO COME O TO FULL SPEED.

~~ FIG. A6.2.3.1 -2 c;

SLCRS PULLDOWN TIME PWR REFERENCE PLANT

[ , SAFETY ANALYSIS REPORT SWESSAR-Pi N

A *> F N 'M8 F N T 14 10/33/ 7')

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F I G. A l 5.1.13 - 2 LOSS OF COOLANT ACCIDENT DOSE VS CHI /Q 2 HOUR DOSE AT EXCLUSION BOUNDARY PWR REFERENCE PLANT SAFETY AN ALYSIS REPORT ,,-

SWESSAR-PI b i/

AMENDMENT 19 12/12 / 75

5 7

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,3 yNa < . - a_

to' _

io' _

- THYROID DOSE b _

s ~

x M

8 _

GAMM A DOSE 10

N l

'_ OSE 10

O I 2 3 4 5 6 DISTANCE (KILOMETERS)

FIG. A15.1.13 -4 LOSS OF COOLANT ACCIDENT DOSE VS. DISTANCE 2 HOUR DOSE AT EXCLUSION BOUNDARY PWR REFERENCE PLANT SAFETY AN ALYSIS REPORT SWESSAR-PI 6lqu 'L] C)

AM E NOMENT 19 12 /12 /75

3 10 g

~

10* _

~

b s

w 8

a -

-THYROID DOSE i

10 3

^

- GAMMA DOSE

~

x BETA DOSE 0

10 O I 2 3 4 5 6 DISTANCE (KILOMETERS)

FIG. A15. i.13 - 5 LOSS OF COOLANT ACCIDENT DOSE VS. DISTANCE 30 DAY DOSE AT LOW POPULATION ZONE PWR REFERENCE PLANT SAFETY AN ALYSIS REPORT SWESS AR- PI O'70u '"U' cu AMENDMENT 19 12 /12 / 75

100 0 z .

o -

C 2

.J C -

U O 100 % EXFILTR ATION AT WIN D SPE EDS

[ > l 7. i M / S E C 3 -

l

$ I iC C w -

I C

W E -

Q 9

o _

5 -

c

< l W -

D l C -

l X

W I

,g 0% EX FILT R ATION AT WIN D SPEEDS 512.5 M/SEC

~

3 y _

< _ l W

W e -

W b ~

o _

b l o e

5 E

' I '  ! ' ' I I I ' '  ! '

Ci O S 60 15 WIND SPEED ( ME'T ERS / S EC)

F IG. A 15.1.13- 8 INCREASE IN IODINE RELEASE DUE TO EXFILTR ATION AFTER A LOCA PWR REFE RENCE PLANT S AF E T Y AN ALYSIS R EPORT g SW E SS AR - PI 7n cO g\

(lU AMENOMENT 23 3/31/76

100 0 _

O -

2 7 -

o U

S o 10 0 --

5  :

b o -

o O .-

o d 100 */. EX FILTR ATION AT c' WIND SPEEDS 217.1 M /S EC.

'O o 0% EXFILTRATION AT I 2 WIND SPEEDS 512.5 M/SEC.

  • _ l 0 l l

z -

i o I I

5 ExFiLTRATiON BEGiNS E _

N

' I I

m

< I w oi o

o -

i a

o -

9 -

r 5

l I I ooi i 5 'o 15 WIND SPEED (METERS /SEC)

F IG . A 15.1.13 - 9 EFFECT OF THE WIND SPEED ON THE O-2 HOUR THYROID DOSE , q PWR REFE RENCE PL ANT , ,- ,.

t.

S AF ETY AN ALYSIS RE#0RT .

SWESS AR -Pl AMENOMENT 23 3/31/ 76

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