ML20072B661
| ML20072B661 | |
| Person / Time | |
|---|---|
| Site: | 05000447 |
| Issue date: | 03/03/1983 |
| From: | Sherwood G GENERAL ELECTRIC CO. |
| To: | Eisenhut D, Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| JNF-012-83, JNF-12-83, MFN-046-83, MFN-46-83, NUDOCS 8303070127 | |
| Download: ML20072B661 (73) | |
Text
{{#Wiki_filter:- _ _ _ . GENER AL $ ELECTRIC NUCLEAR POWER SYSTEMS DIVISION GENERAL ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE. CAUFORNIA 95125 MFN 046-83 MC 682, (408) 925-5040 JNF 012-83 March 3, 1983 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 Attention: Mr. D.G. Eisenhut, Director Division of Licensing
SUBJECT:
IN THE MATTER OF 238 NUCLEAR ISLAND GENERAL ELECTRIC STANDARD SAFETY ANALYSIS REPORT (GESSAR II) DOCKET NO. STN 50-447 SECTION 3.11 ENVIRONMENTAL DESIGN The purpose of this letter is to request the review of GESSAR II Section 3.11 in parallel with the Staff's current review of the Licensing Topical Report (LTR) NEDE-24326-1-P, " General Electric Environmental Qualification Program." The proposed action plan, recently discussed with the Equipment Qualification Branch, is provided as Attachment No. 1. Since subsection 3.11.2 (Qualification Tests and Analyses) will " track" the LTR and the LTR review is nearing completion, the most effective use of resources is to submit a revised subsection 3.11.2 for Staff review shortly after approval of the LTR (mid-April 1983) with GE identifying any differences between the LTR and subsection 3.11.2. In the interim, GE is providing Attachment No. 2 which is a draft of revised Section 3.11.1, 3.11.4 and 3.11.5 (Environmental Ccnditions, Loss of Ventilation and Estimated Chemical and Radiation Environment, respectively) for staff review. As shown on the action plan, a supplemental safety evaluation report and the corresponding Section 3.11 amendment are anticipated by the end of June 1983. Very truly yours, Glenn G. Sherwood, Manager Nuclear Safety & Licensing Operation Attachments cc: F.J. Miraglia (Without Attachments) D.C. Scaletti P. Shemanski R.J. Wright -8g C.0. Thomas (Without Attachments) L.S. Gifford (Without Attachments) R.M. Ketchel (Without Attachments) 1 8303070127 830303 PDR ADOCK 05000447 A pop
ATTACHMENT NO. 1 PROPOSED GESSAR II SECTION 3.11 ACTION PLAN 1983
. _ March . April i May' . June.
EG&G 205 2Ci SER O APPROVED INPUT ISSUED LTR ISSUED TO EQB RESOLUTION COMPLETE GESSAR II: REV ED REV SED GE QB S SUBSECTIONS SUBSECTION MEETINGS ISSUED 3.11.1, 3.11.4 3.11.2 TO RESOLVE AND AND 3.11.5 DOCKETED DIFFERENCES AMENDMENT DOCKETED FILED NOTES o Subsections 3.11.1, 3.11.4, and 3.11.5 under review by EQB while LTR being reviewed. o GESSAR II subsection 3.11.2 to " track" LTR. GE will identify differences. o GESSAR II will utilize R. G.1.3 and 1.4 source terms (are presently reviewing GESSAR II to give credit for Pool Scrubbing - - SSER scheduled forSeptember1983).
I l l l ATTACHMENT N0. 2 ! DRAFT OF REVISED GESSAR II SUBSECTIONS 3.11.1, 3.11.4 AND 3.11.5
x l I t GESSAR II 22A7007 i 238 NUCLEAR ISLAND Rev. 5 ,
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O 2.u.2 ooaufio.uon aesu1es Q
. Applicant to supply. .
3.11.4 Loss of Ventilation
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Vsf l 0 ( 3.11.4 LOSS OF VENTILATION Environmental conditions resulting from loss of ventilation (HVAC) are presented in Tables 3.11-2 through 3.11-6, where applicable, for Nuclear Island areas except for Radwaste Building. The Radwaste Building does not contain any safety related or safe shutdown equipment. As noted in the tables, areas containing major equipment of safety related systems are provided with safety grade cooling systems and as such are not affected by loss of ventilation. The loss-of-ventilation environmental conditions shown in the tables are included in Nuclear Island Design and Equipment specifications and are to be considered for environmental qualification of equipment. The loss of ventilation calculations were based on maximum heat loads and considered operation of all operable equipment regardless of safety classification. O C
. GESSAR II 22A7007 l , 238 NUCLEAR ISLAND R;v. 5 l
[ 3.11.4.5 rbine Buil (Losso AC A plicant t upply. 3.11.4.6 Diesel Generator Buil g Loss of HVAC .
/
The Diesel Generator Bui ngs are served by fety class HVA o
/ w systems. . Thus the lo of the HVAC syste for these buildings -
f is not considered redible, and these vironmentalzone[need not be analy2.c for a loss of HVAC vent. Also, sin division-ally separ diesel generation ystems are provid d with their dedicat , divisionally sep ate HVAC systems, .e loss of one HVAC ystem will not adv sely affect the op ability of safety-r ated equipment loc ed in these buildi s. , 3.11.5 Estimated Chemical and Radiation Environment Ted s R lt T 7
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1.t 1. 6.1 E- - E y-p. $~ N JM ,-.e - AA
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6 l l 4 3.11-83/3.11-84
INSERT 2 3.11.5.1 Chemical Environment Equipment located in the containment (outside of the drywell) is potentially subject to water spray from the containment spray mode of the RHR system. In addition equipment in the lower portions of the containment are potentially subject to submergence and wetting by pool swell and weir annulus backflow. 3.11.5.1.1 Containment Spray The containment spray is to be considered activated for a period of time between 10 minutes and 100 days
- post - LOCA.
Spray characteristics are 400 micron particle size (nominal minimum); 1.1 gpm per square foot and 125 F temperature. Water quality is given in section 3.11.5.1.3. 3.11.5.1.2 Suppression Pool Wetting and Submergence The characteristics and extent and post - LOCA pool swell, and weir annulus backflow are given in Appendix 3B. Water quality is given in Section 3.11.5.1.3. 3.11.5.1.3 Post LOCA Water Quality
~
1he following water quality based oc fission prod'act "releas's of R.G.1.7:
- a. pH = 4.5 to 7.0
- h. conducti ty 121 a 5/cm C. 1 8 P9mh 2.1 1 ppm CD2
- d. 1 02 a If-5 g mole /1 dissolved salts available to deposit as dry salts upon evaporation from hot surfaces, e.1 0 9ppm undis 11ved solids
- f. 180 pet dissolved Hg arising from 1 41 volwie of M fn g containment atmcspNtre.
3.11.5.2 Radiation Environments l The radiation environments are given in Tables 3.11-2 through I 3.11-6 for the various Nuclear Island buildings except for Radwaste Building. l
- This should not be construed necessarily as establishing a continuous 100 day operating time for the Containment Spray System. Actual operating l
time guidance is established in NED0-24934 (BWR Emergency Procedure Guidelines). i l l I L C
TAE,LE. 3,i b2A C 55
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EMVIRON MENTAL CCMDITIONS FOR COMTAIRMERT(OUTSIDE DRYWELL) EQUIPMEMT INTEG INTEG I LIMITING DURATION FREQ/ TEMP ETA GMm N
@T F PRER3URE NOTE CONDITION IATION RADIATIm (Ntn/ o OF CONDITION 40 YRS (*F) (%)
(rads) (rads) an2) 4 N 7 bes) REFCAL Tb "5 Var 4 0 $$ a m == =m _m etr 1raet.t.rz 3 a s l % o q
- )
f m, tas a,3 + s a.5esa.sc.j COtTfAI?NENT - ABOVE REFUELING FICOR ct U. 84'-7" EL n WM _ I.S u Jo* NOI4ML llVAC 90*/70* 20-90% (-10.1 to ' 0 (-) l . 0 " 112 0 . ABNOINAL g , 90 -121 * (-) 0.1" to 0 l IOSS OF INAC 0 to 45 min 3 20-90% Avg Avg (+)1.0" 1120 m
*45 min - 20 hr 3 121* 50-100% * (-) 0.1" to j
(+)1.0" H2O c 3 121*-90* 50-100% * (-) 0.1" to 2
*20 hr-27.5 hr
(+)1.0" 1120 e[ IOSS OF OFFSITE Same as loss.of 11VAC n (INAC Powered Ly Non-0iv "N" Bus - Interru at. Offsite Po er) O
. POWER p -
TEST (18) *0 to 20 hr 12 *90 70-90% 8 psig ' 0 SOLATION EVENTS A' (6) g, s /O'
> (1,2,3,4,5,6,7,8, 'O to 1.75psig ) ;' EEi &) t
_.4 *0 to 30 min *90 -120* *100% 0 12,16) *30 min-10 hr *120* *100% 'l.75 psig . l *10 to 24 hr *120 -90 *20-90% *l.75 to Opsig _ . ACCIDENT (g) y8 j J LARGE IIE PIPE *0 to 6 sec *90*-120* *100% *0 to 6 psig 0 '
- BREAK IN DRYWELL *6-45 sec *120*-150* *100% '6 to 9 psig (.7,) m
*45 sec -10 mir *150 -185* *100% '9 to 15 psig ~
i
$m
*10 min -1 day *185 *100% *15 psig ,
*1 to 100 days *185*-90 *
,100%
*15 to O psig . , y, I *r'T? CTinnT TI?n FWPA N
O *s. g g f[(_. pl .
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E4VIRONMENTAL 0.O M D IT tO M S FOR COMTAlHMEMT (00T5tDE DR. Y VIELd EQOlPMEMT - INTEG INTEG I LIMITING DURATION FREQ/ TEMP PRESSURg BETA GM N NOTE
@T E IATION RADIATIm (Ntn/ o CONDITION OF CONDITION 40 YRS (*F) (%)
(rads) (rads) an2) g g} m w u m a NY m'c 00tTPADNENT - ABOVE SUPPRESSI N POOL g H-n (-)11'-2" El CT-2 NORHl$T-UP # NORI%L llVAC 100 /40 20-90% (-) 0.1" to (-) H2O O @ I!Of STANDBY *100*-120* 20-90% * (-) 0.1 to (-) l . 0"H2O O O M ABNOINAL - g i LOSS OF HVAC 0 to 45 min 3 100*-124*
- 100 */. *0-1.24 psig 0 !
Avg Avg j
*45 min-20 hr 121* *100% *l.24 psig
*20 Hr-27.5 hr 121*-100* *100% *l.24-0 psig IOSS OF OFFSITE SAME AS 10 S OF llMC O O
, POWER (IIVAC PGiE2 ED BY b 31 DIV ,"N" 1 0S - INT ERUPr. OFFSIT POWER) g ISOLATION LVENTS (1,2 ,3 ,4 ,5,6 ,7 ,8, *0 to 30 min 100*-150*
- e oa *,; *0 to 1.75 1.1x 10' 4.44IE O (3)(f,j 12,16) W psig (NCC4. 6) (Note 6)
*30 min-10 hr 150* *100% *l.75 psig
*10 to 24 hr 150 -100* *100% *l.75 to 0 Psig TEST (18) *0 to 20 hr 12 *100* 20-90% *8 psig 0 ACCIDENT (l)
SMALL llE PIPE *0 to 45 sec *100*-150* *0 to 9 psig BREAK IN DRYWELL *45 sec-10 min *150 -185* *9 to 15 psig y
*10 min-1 day *185 *15 psig m
*1 to 100 days *185 -100* *15 to O psig l GE SUPPLIED DATA g- _
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[ rA bt.E. O it- 2.A - 55 EHVIRONMENTAL CONDITIONS FOR CONTAIMMEMT[OOTslDE. DRYWELL) EQUIPMEMT RH INTEG INTEG m ok LIMITING DURATION FREQ/ TEMP ADDEN
@T FINAL PRESSURE TA GMA N NorE $ $ <:
CONDITION OF CONDITION 40 YRS (*F) (%) REF d l 5 l N$ om COMAINMENT - IICU FIDOR S 11'-0" El U-n CT-3 NOIN/ST-UP NOFNAL HV1C 90 /40 20-70% (-) 0.1 to - 7.0 x 10 0 (-)l.0" 1I20 ABNOF4ML IDSS OF IIVAC 0 to 45 min 3 90*-128 20-90% * (-) 0.1 to 0 o Avg , (+)1.0" H2O y
*45 min-20 hr 3 121 50-100%* (-) 0.1 to
(+)l.0" 1120 j
*20 hr-27.5 hr 3 121*-90* 50-100%* (-) 0.1 to >
C (+)1.0" 1120 2 IDSS OF OFFSITE SAME AS IISS OF i VAC POWER (llVAC POW 1 . RED BY NCN-DIV "N" BUS - INfERRUPT OFFSIT POWER) IP O O ISOLATION EVEtfrS . (1,2,3,4,5,6,7,8 *0 to 30 min *90 -120 *100% 80 % 17fpuy I.t x 10 4.4410 0 (G) 12,16) *30 min-10 hr *120* *100% *l'75 PM7 Usata 6) (Nate O
*10 to 24 hr *120*-90 *20-90% *s.7th Opseg TEST (18) *0 to 20 hr 12 *90* 20-90% *8 psig ACCIDENT (g)
IARGE IIE PIPE *0 to 6 sec *90* to 120* *100% *0 - 6 psig Fide. 2- Fl41 0 (7) BREAK IN DRYriELL *6-45 sec *120 -150* *100% *6 - 9 psig (Nota. 7) (Note F)
*45 sec-10 min *150 -185 *100% '9 - 15 psig y
*10 min-1 day *185 *100% *15 psig . *
*185 -90* *15 to o psig
*1 to 100 days *100% S
*GE SUPPLIED DATA -
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k q g . ENVIROM MENTAL COMDITIONS FOR COMTAlHMEMT (OOTSIDE DRYWELL)EQOtPMENT - INTEG INTEG l LIMITING DURATION FREQ/ TEMP TA Nm N
@T PRESSUR'E NCyrE CONDITION OF CONDITION 4 0 YRS (*F) (%)
RADIATION RADIATICN (Ntn/ o (rads) (rads) an2) g g} l2 o- c i COfrAINMENT -SIfS AREAS 37'-1" El CT-4 SUM /WINr /, g 95 NORMAL IIVAC 90*-70 20-90% (-) 0.1 to 0 (-)l.0" II20 ABNORMAL IDSS OF IIVAC 0 to 45 min 3 90 -121* 20-90% * (-) 0.1 to g Avg Avg (+)1.0" II20 0
*45 min-20 hr 3 121' S0-100% *(-)0.1 to '
(+)l.0" II20 $
*20 hr-27.5 hr 3 121 -100* 50-100% *(-)0.1 to ><
IDSS OF OFFSITE SAME AS I JSS OF IVAC POWER (IIVAC PG ERED BY DIV "N" BR --INTERRUPT.,OFFSITE 1 W ER) E O O ISOLATICN EVERTS g 4,4 go 2. (1,2,3,4,5,6,7,8, *0 to 30 min *90*-120 *100% *0 to 1.75 psig g,, 4) Wora 6) o (c. ) 12,16) *30 min-10 hr *120* *100% *l.75 psig
*10 to 24 hr *120*-90* *20-90% *l.75 to 0 psig TEST (18) *0 to 20 he 12 *90* *20-90% '8 psig ICCIDENT (3) A G. 2. #es, /
IARGE IIE PIPE *0 to 6 sec *90 -120* *100% *0 to 6 psig (N*Ts.7) (Norm 7) 0 (1) BREAK IN DRYWELL *6 sec-45 sec *120*-150* *100% '6-9 psig
*45 sec-10 min *150*-185 *100% '9-15 psig
*10 min-1 day *185* *100% *15 psig E
*1 to 100 days *185 -90* *100% *15-0 psig j
*GE SUPPLIED DATA -
k g - ---- - p _ . _ _ _ _ _ - - -
g P' re>tA 3.11- 2.A .
S g
ENV1ROMMENTAL COND)TiONs FOR CONTAlHMEMT (OUTSIDE DRYWELL) EQUIPMENT '. RH INTEG INTEG m ari LIMITING DUI<ATION FREQ/ TEMP ADDW
@T FINAL PRESSURE ETA GN N NOTE $ $ <:
CONDITION OF CONDITION 40 YRS (*F) (%) REF ds d 2)
$ 1
!3 i o-4 CQffAINMEtfr -RWCU ROCNS (IlOLDING PUMP & FILTER DEMIN) fe M
59'-7" El CT-5 0 976 O NORMAL IIVAC: PUMP RM 90 20-70% (-)0.1 to (S) E/D RMS 105 (-)1.0" H2O ABNORMAL IDSS OF liVAC 0 to 45 min 3 100 -109 20-90% *(-)0.1 to o O (IMCU PUMP & F/D) Avg AVG- (+)1.0" H 2O 1
*45 min-20 hr 3 109* 20-90% (-) 0.1 to a
(+)1.0" 1I20 2
*20 hr-27.5 hr 3 109 -100 20-90% (-)0.1 to $
(+)1.0 1120 2 IDSS OF OFFSITE O to 1 hr 100 -127 20-90% (-) 0.1 to y POWER , 0" 1120 g (ALL llVAC EQUIP (RWCU HVAC PCNERED I'I DIV N1 ANi lN2 BUS- -NORMAL POWER ,DG BACIG D, SHED O J IDCA 04LY; CONT O EXCL RWCU RMS) ISO L ATIDH Eve.HT
!!VAC POWEREE BY NG-DIV "N" BUSES-INTER UPT.OFFSITE P t (wo j)
C. m,, (Mote. C.) o (d , TEST *0 to 20 hr 12 100* 20-90% *8 psig ACCIDENT (I) LARGE HE PIPE *0 to 6 sec *100*-120 *100% *0 to 6 psig FICn.2. F i(n. I o (7) BREAK IN DRYWELL *6-45 sec *120*-150* *100% *6 to 9 psig (uote. 7) (Hota. 7)
*45 sec-10 min *150*-185* *100% *9 to 15 psig
*10 min-1 day *185 *100% *15 psig -
*1 to 100 days *185*-100 *100% *15 to O psig i ai' 8
t. OGE SUPPLIED DATA ',
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. s7e 12 75 C F BRAUN O CO Paga pF '
W V Crnlley -- _ General Electric ( San Jose TABLE 3.11-LA CONTAINMENT , ADDENDUM TO DATA SHEETS 1 Pressure Control is not a part of the air conditioning system. A negative pressure level within the overall containment area is maintained by separate constant-exhaust-air and variable-supply-air systems. A differential pressure controller (RR619) above the suppression pool area, throttles a damper in the supply air ductwork to maintain the containment at a negative pressure with respect to the ambient atmosphere. Isolation valves to maintain the containment integrity are installed in the supply and exhaust ducts where they penetrate the containment / shield building barriers. These valves will close in the event of high radioactivity detection within the containment, and the exhaust and supply air systems will be shut-down. In addition, a shut-off damper will be closed in the outside air intake duct to the supply air system. - 2 The systems are balanced to provide an air flow pattern from areas of low potential contamination to areas of higher potential ( contamination. 3 For the Zone CT-2 Abnormal condition of " ISOLATION EVENTS", the , suppression pool temperature was assumed to be 150.*F due to the 19 SRV's opening. k IK . _ _
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RADIATION RADIATION (Ntn/ o CONDITION OF CONDITION 40 YRS (*F) (%) (rads) (rads) on2) g g} La o navEr. To" system tn e:) oPER. STATUS" MAT 284 g [ S H E CT. e y o' < DRYWFTL - OLTPSIDE RPV SilIEID VNL - NOT AT CORE MIDPLANd O DW-1 NORMAL IIVAC 135* 20-90%
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(Note 7) (,40TM.- 7) (7) E REFUELING 70* 20-90% *12-psig ABNORMAL
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*58 min-5 hr 251*-135* *l-90% *2 to O psig a '
2 j LOSS OF OFFSI'IE NO IMPACP- SAME AS NORMAL C 2 POWER (llVAC POWI RED BY DIV N1 & N2 BUS -NCRMAL POWER, DG pp BACKED, 5HED W IDCA W LY) , ISOLATION EVENTS *0 to 75 sec
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- Steam *0 to 30 psig F14.1 FIG.1 .~
(g) y BREAK IN DRYWELL *l.5-40 sec *330
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*40-45 sec *330 -250*
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@T PRESSURg NOTE CO'NDITION OF CONDITION 4 0 YRS (*F) (%)
RADIATION RADIATION (Ntn/ REF 0 (rads) (rads) cm2) g y }
" 1 5i em DRYWELL OLTFSIDE RPV SHIEID WALL--AT CORE MIDPIANE fe U-n DW-2 NORMAL IIVAC 135* 20-90% *12 psig (Not=. 7) (Ncte7) (7)
REEUELING 70 20-90% *i2 psig ABNORMAL O IDSS OF IIVAC 0 to 16 min *3 135*-242 *1-90% *0 to 3 psig - - - 3 16 min-68 min 242*-251* *l-90% *3 to 2 psig ,
*S8 min-5 nr 251*-135* *1-90% *2 to O psig a LOSS OF OFFSITE NO IMPN T-SAME AS NORMAL C POWER (IIVAC PCWERED L Y DIV N1&1 I2 BUS - M 4AL POWER, XI 2 BACKED, SIIED C N A IOCA ONDY) ,
IP ISOLATION EVEms *0 to 75 sec- *50 *135*-150o e154o% *0 to 2 psig 1.1x 80' 4 . + x 10* - (4)
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CONDITION OF CONDITION 4 0 YRS T T " (*F) (%) ds ds REF 2)
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N.Y m < n DRYWELL - ANNUwS BE71HEEN RPV & RPV SilIEID WALL q W DW-6 NOINAL INIC 550* l-30% * (-) 0.5 to - *l.8x1010*4x1017
+1.5" HO2 ABNOINAL IOSS OF INAC *0 to 25 min 3 550 -575 1-5% *0 to 3 psig - - - ..
*25-58 min 3 575 -475* l-5% *3 to 2 psig y
*58 min-5 hr 3 475 -135* 6-90% *2 to O psig .
- n IOSS OF OFFSITE POWER NO IMP 1 CT-SAMI- AS NOINAL (INAC I OWERED BY DIV N1& N2 BUS-- -NOINAL POWER, DG
{Z BACKEL , SIIED ON ONLY) SCRAM 14'% sotArno4 - .- 1.4 x 10+ 4. + x to* - O AOCIDENT O IAI1GE IIE PIPE *0 to 1.5 sec *S50
- Steam *0 to 30 psig FIG.I FIG.t 0 (3)
BREAK IN DRYWELL *l.5-40 sec *550*
- Steam '30 psig (Note.6) (Note. 6)
*40-45 sec *550
- Steam *30-15 psig
*45 sec-1 hr *550 -250*
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*1 hr-1 day *250* *100% *15 psig *
*1 to 100 days *250 -100 *100% *15 to O psig l
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*GE SUPPLI W DATA _ _ _ _ i
s7s C F CRAUN O CO pana // 12 75 W V Cralley --.d_ General. Electric g i .
') San Jose TA&LE 3.11-2 &
DRYWELL ADDENDUM TO DATA SHEETS Pressure control is not a part of the drywell air conditioning systems, which are 100 percent recirculating. The various requirements for drywell pressure control are handled as follows. 1 During the reactor start-up mode, an increase in drywell pressure will result from the increase in air temperature. A drywell , bleed-off vent system is provided to prevent this pressure from exceeding the containment pressure by 2 psig, which would initiate a LOCA signal. 2 A steam line break in the drywell will initially cause an outflow of non-condensibles through the suppression pool to the
- containment, and a subsequent condensation of the steam within ,
the drywell, after termination of the steam flow, can result in the drywell pressure becoming negative with respect to the containment. A drywell vacuum relief system is provided to prevent this negative pressure differnential from causing the suppression pool to overflow and flood the base of the drywell. This drywell vacuum relief system also protects against an O overpressurization of the containment from an instrument line break which could also result in an overflow of the suppression - pool into the drywell. 3 A drywell purge mode shall be provided to remove any accumulation of radioactive gases from the drywell prior to re-entry of the drywell during a routine plant shutdown. This is accomplished by having the SGTS exhaust fan draw air from the drywell and in conjunction draw replacement air into the drywell , from the containment area, through valved ducting which penetrates the drywell ceiling. 4 Abnormal Isolation Events for Zones DW-1 and 2, are based on "19 t SRV's Open With Scram" and
- 5 150*F Suppression Pool temperature.
5 Normal HVAC temperature ...e DW-4 is based on a Fuel Pool temperature of 126. *F . t 6 Abnormal Loss of HVAC temperature is based on a Fuel Pool ' temperature rise to 128.5*F. i i
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CONDITION RADIATION RADIATIm (Ntn/ o OF CONDITION 4 0 YRS (*F) (%) - (rads) (rads) cm2) g g} i m e u m3 X.} AUXILIARY BUIIDING - LPCS, IIPCS, AND RIIR "C" ROCHS (ECCS AREAS) rt () 3 2.'- o EL. N. n AB-2 (Contd) FCCIDINF LARGE IIE PIPE *0 to 2 min *104*-122* *8-35% *(-)0.25 to 0" (N0ke. G)(Noted) 0 (d) BREAK IN DRYWELL 112 0 (IDCA-DBA) *2 min-100 days *122* *8-35% *0 to (-) 0.25" (12) 112 0 g flE PIPE BREAK IN *0 to 24 sec *104*-250* *100% *0-1.6 psig 2.0 m to ~ 1,3 x to 0 1 AnJACINF ZWE *24 sec-6 hr *250*-212* *100% *l.6 psig a
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u. EMVIR.ONMENTAL CONDITIONS FOR AUX,1L1 AR.Y 1501LDIMG EQOlPMENT - RH INTEG INTEG i LIMITING DURATION FREQ/ TEMP NM ADDW lm c4
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NOTE $ $ <: CONDITION OF CONDITION 40 YRS (*F) (%) ( REF d 2)
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AUXILIARY BUIIDING - RIIR PLNP ROCNS "A" AND "B" (BCCS ARFA) Q (-) 32 '-0" El $ AB-4 SLM/WINT NOIEAL IIVAC 151 104 -60* *8-90% *(-)0.25 to - 5.8 x #0 0 (-)l.0" H 2O (INCL SIftTP-DN & PEFUELING) (9,11) o ABNOfB E ' IDSS OF HVAC IMP 1 CT - ([UE 'IO REDUNDANT NA'ItRE AND IOCATIO 4 OF ! IECS E UIP NO ST-BY IU1C 1: QUIP IS REQ'D OR PROVI )ED). [' Z IOSS OF OFFSITE IIVAC E UIP POk ERED BY DIV "ESF" BU 3ES POWER , IP ISOLATION EVENTS *0 to 6.5 min 115 *104*-122* *8-35% * (-) 0.25 to - 5.8 x 10 0 (5) o (1,2,3,4,5,6,7,8,14, (-).1.0" II20 (Note 8) 27,28,29) *6.5 min-49 hr *122 *8-35% *(-)0.25 to (-)1.0" 1120 i *49-52 hr *122*-104* *20-90% * (-) 0.25 to (-)1.0" H 2O TEST *0 to 6.5 min 2241 *104*-122 *8-35% *(-)0.25 to - - 0 (1,2,3,16) (-)l.0" 11 O
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FOR AOKILi AEY T501 LDI MG EQUlPMENT - LIMITING RH INTEG INTEG ! DURATION FREQ/ TEMP ADDm m o s g ..t,SSURE BETA GN N CONDITION OF CONDITION 4 0 YRS T NorE $ $ < (*F) (%) ( REF ds ds) Ej 1
!2 7 o' c ElXILIARY BUIIDING - RNCU PWP ROWS rt N
(-) 6 '-10" El ' o as-s sW/WINP s NOINAL INAC 100*/60* 20-60% (-)0.25" to - 1.4 x 70 0 (-)l.0" H 2O ABNOINAL LOSS OF llVAC 0 to 8 min 10 100*-151 *3-60% * (-)0.25 to - - O n ( -) 1 . 0 " 112 0 1
*8-20 min 151*-100* *5-90% *(-)0.25 to a
(-)l.0" 1I20 g IDSS OF OFFSITE *0 to 27 sec 10 *100 -104 *17-60% * (-) 0.25 to - 0 E POWER (-)1.0" H 2O
*27 sec-17 min *104*-100 *17-90% * (-) 0s 25 to *
(-) 1 . 0 " 112 0 0 , (INN FOWERED BY DIV N1 &N2 BUS BS , NORMAL PO VER, DG O { BACFED, SIIFD W IOCA WLY) AOCIDENP IARGE IIE PIPE *0 to 100 days *100 -150' *5 -60% * (-)0.25 to (Nota 6) I(40ta6) o (d' s BREAK IN DRYWELL (-)l.0" 1120 IIE PIPE BREAK IN
- 0 2 0 x to p,3 x fo l IMll CWPAR'INENT e
2 i t CGE SUPPLIED DATA l l
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A TABLE All- 3 - 9 'n a= E8VIRONMENTAL DON DITiONS FOR AUKILIARY suitoi% EQUIPMEMT l RH INTEG INTEG LIMITING DURATION FREQ/ TEMP ETA GAMMA N ADDEN m Ci k
@T FINAL PRESSURE NOTE $ $ <
CONDITION OF CONDITION 40 YRS (*F) (%) REP d 2)
!3 i om AUXILIARY BUIIDING - STEAM TUNNEL h
9'-0"&l3'-0" El 3. n SIN /WINr S NORMAL IIVAC 122 -60* *10-90% *(-)0.25 to - 9,fx to 0 0" H 2O ABNOINAL O IDSS OF IIVAC 0 to 11 min 10 122*-180* *0.8-25% *(-)0.25 to - - 0 y 0" H2O
*ll min-1 hr 180 *0.8-25% * (-) 0.25 to $
0" 1120
*l-2.5 hr 180 -122* *10-90% *(-)0.25 to j 0" H 2O ,
IOSS OF OFFSITE O to 11 min, 10 (SIMIIAR 'IY i NOINAL IVAC SINCE IIVA: POERED BY DIV N1 n POWER *11 min-2.5 hr &N2 BUSEE - NOIM L POWER, DG BhZED, SIEI ON IDCA O
*2.5-4 hr N LY) .
ACCIDENT U} IARGE IIE PIPE *0 to 1 hr *122*-180* *0.8-25% *0 to 2 psig FI G. 5 FIGa. 4 0 BREAK IN DRYWELL *1 hr-100 days *180 -150* *4-42% (4)
*2-0.5 psig (Nota 4) (flote. 4)
(IDCA-DBA) IIE PIPE BREAK IN STEAM 'IUNNEL
' o to 0.5 sec_
'O.Esee - I hr 12.1'- 24 8 All Steam
*14o*-315*
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General Electric -b San .Tose TAlbLE. 3.ll-3 ' AUXILIARY BUILDING ADDENDUM TO DATA SHEETS 1 The secondary containment zone within the Auxiliary Building, consisting of the ECCS and RWCU equipment spaces, is isolated from the remainder of the building areas by leaktight physical barriers. Pres ure control is provided for these ECCS and RWCU rooms by means of redundant pressure control supply and exhaust fan systems. The differential pressure controller (RR604) at the (-)32'-0" elevation corridor, outside the ECCS rooms, throttles the damper in the supply air system which furnishes air to the corridor only. This supply air throttling, in conjunction with the constant suction from the corridor and ECCS and RWCU rooms by the exhaust fan system, maintains a negative static pressure within the area with respect to the surrounding areas and the outside atmosphere. Since the supply and exhaust fans are on normal interruptible off-site power, a loss of this off-site' power will result in the loss of the negative pressure control within the area. However, since there is an alternate valved bypass arrangement from the exhaust system to the SGTS, the SGTS can be manually actuated to ( provide a direct suction exhaust for the ECCS and RWCU rooms. 2 A slight positive static pressure is provided throughout the remainder of the auxiliary building, except for (1) the battery rooms and the CRD maintenance area which will be slightly negative due to their respective exhaust systems, and also (2) the steam tunnel area which is open to the turbine building but has only blow-out panel access to the auxiliary building RHR "A" and "B" areas. The slight positive pressure in the HVAC equipment rooms at 28'-6" elevation is provided during summer cooling only by means of the room supply air fans which furnish once-through 100 percent outside air for ventilation. These fans do not operate during winter heating and thus there is no room pressurization provided at the time. The fans however, are powered by the divisional N1 and N2 diesel generator backed buses. The slight positive pressure throughout the remaining areas is provided by the main air conditioning systems which furnish a minimum of outside air for exhaust makeup and general building pressurization. Since these air conditioning system fans are on normal interruptible off-site power, a loss of this off-site power will result in the loss of the positive preceurization for the g{ general building area.
- 3. Zone AB-7, steam tunnel . For a loss of either divisional bus one of the two A/C units will be lost and the tunnel temperature will rise to 1350F with the ESW supply at its maximum of 1000F. For LOCA the resulting environ;nental
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