Text

Rev B to Fc 05916, Operating Temperature Limits for DG-1 and DG-2
	ML20099H753
Person / Time
Site:	Fort Calhoun
Issue date:	08/10/1992
From:	; OMAHA PUBLIC POWER DISTRICT
To:	;
Shared Package
ML20099H730	List: ML20099H729; ML20099H753;
References
	FC-05916, FC-05916-RB, FC-5916, FC-5916-RB, NUDOCS 9208190182
	Download: ML20099H753 (58)
	v • d • e

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SUMMARY

SHEET Rev. No. OBJECiNE The objective of this calculation is to determine the Emergency Diesel Generator tepper Outdoor Air Ambient Temperature Limits for various coolant temperatures and chemical makeups. This is considered an interim calculation until EA-FC-90-062 r3 can - be t prepared, reviewed and issuedg or 5 spere.edad 1 6 4 4 4-i; N l I l si f f = gyj PED-QP-3.28 i j 'i !.' 1

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SUMMARY

SHEET Rev.No. A METHODS i To determino the Diesel Generator Upper Ambient Air Temperature Limit, the following steps are necessary. 1. Determine the KW Capacity of the diesel generator without considering the effects of elevated air temperature on jacket [ water temperature or turbo charger intake. l I

2. Predict Turbocharger intake temperature at elevated conditions i

3. Predict Jacket Water temperatures at elevated conditions:

a. Determine f an flot' rates at elevated temporarures

b. Compare fan flows to required flows to maintain jacket water at 190 F r.;"1 208 deg F

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4. Determine Deration factors from the predicted jacket water temperatures and turbocharger intake temperatures 5.

Plot Derated Power vs Time and Required Load fur each doisel i i L l' l i i PDj l PED-QP-3.29 ip ?J

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SUMMARY

SHEET Rev.NO. E ASSUMPTIONS 1. Ambient air pressures are considered constant

2. The diesels are in a cold shutdown condition with the jacket I

water at a temperature of 125 F prior to the start of the accident.

3. Turbocharger inlet air temperature delta T with outside ambient air does not change dre-ctically with outside air temperature increases, ie the optsit

.r temperature to turbocharger intake delta T from 90 deg F a,

Jnt can be used to predict turbocharger intake temperatures at 110 deg F ambient conditions.

4. The radictor fan intake is equivalent to outdoor temperature +

1 deg F. This is validated by test da'a gathered during the last test performed on DG-2. 6 For DG-1, the test data requires some interpretation. During the hot weather testing performed in 1991, the outdoor ambient temperature recorded was 95 deg F with f an inlet temperatures of 96 dog F on the north side of the radiator and 100 F on the south cida. The majority of air flow in DG-1 entering the fan comes from the north side of the engine (ref EA-90-091 rev 0 attachment 8.8 fig 6A and & 7a). The configuration of the r equipment in the room is such that a natural plenum is formed between the north wall and the engine skid through which the e fresh air travels. The air on the south side is mostly eddies formed from fan blade tip recirculation containing heat rejected from the radiator. The 1 deg F assumption is justifiable based on the following factors: a. The fan Enroud/ fan blade tip clearance was reduced substantially when the new fan blades were installed. This t. resulted in reduced tip recirculation. b. The majority of the makeup air comes from the north side of the engine down the natural plenum Any preheating ce the air supplying the radiator is done by c. heat rejected by the radiator or the diesel engine itself. Heat removal from the engine by this air reduces the thermal loading on the jacket water cooling system. Air that backwashes from the blade tip / fan shroud gap removes heat from the radiator but is not measured as fan flow during testing, which indicates that more air cooling is supplied to f' the radiator than can be meausured in a test configuration. jh4

5. Only the minimum ainount of emergency safeguards equipment f

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SUMMARY

SHEET Rev.No. b ASSUMPTIONS required to respond to a large break LOCA is considered to be the required load for the diesels. Additional optional loads that may be desired to assist operations in accident response, such as station air compressors, are not included in the required electrical load calculations.

6. Although the new fans draw more air, the air flow in the room

) is such that the turbocharger inlet air temperature is assumed to be unaffected. 11 y \\;

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SUMMARY

SHEET Rev No. A INPtfTS / REFERENCES REF. NO. 1.-- Letter From Ted Fryar to Randy Mueller, Dated 2/10/80 contained in EA-FC-90-062 r 2 Attachment 8.2-b

2. MWo 913677 Replace Fan with Substitute Replacement Item per EC) 91-306 i

3. MWO 913676 Replace Fan with substitute Replacement Item per EC) 91-306-j_

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4. Diesel Generator Deration curves from EA-FC-90-062 r-2

/ Attachment d.2-a -j

5. Fax Transmission from Young Radiator Company to Dan Borcyk datec 4/8/91

6. Fax Transmission from Young Radiator Company to Dan Borcyk dateo 4/15/91 found in EA-FC-90-062 r 2 Attachment 8.9a

'7. FCO3382 r Diesel Generator LOCA Loads f

8. Mechanical Engineering' Review Manual Seventh Edition r

9.- EA-FC-90-062 r 2 Diesel Generator Upper Temperature operating Limits lo. MWo 92 23% %vios Aa.w rwe.c_ s s eeocr

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SUMMARY

SHEET Rev.No. 3 CONCLUSIONS DG-1 Upper Ambient Air Temperature Limits: DG-1 will satisfactorily supply the minimun required power to support Emergency Safeguard equipment in a post LOCA scenario with f a 50 % ethylene glycol coolant solution in the Jacket Water. system up to an outdoor ambient condition of 104 deg F DG-1 will satisfactorily supply the minimum r" p, sd rower to support Emergency Safeguard equipment in a post 1 SCA % vp'io Mith a treated yater coolant solution in the Jacket W, t*u;' f@.~ it n

o an outdoor ambient condition of 110 deg F DG-2 Upper Ambient Air Temperature Limits:

) h DG-2 will satisfactorily supply the minimum requirec' power to O support Emergency Safeguard equipment in a post LOCA scenario with a 50 %. ethylene glycol coolant solution in the Jacket Water system up to an outdoor ambient condition of 110 deg F- .DG-2 will satisfactorily supply the minimum required power to support Emergency Safeguard equipment in a post LOCA scenario with a_ treated water coolant solution in the Jacket Water system up to r an outdoor ambient-_ condition of 110 deg F with a wide degree of margin that could be used for optional loads. 5 NOTE: Generator Limitations: The generator portion of the Emergency. Diesel Generators is limited to a-maximum power output of 2718 kW 0 for DG-1 and 2656 KW for DG-2 based on power factor as discussed in y Calculation FC-03382. This calculation (FC-5916) only considers the C 'derated power capabilities of the Engine. b i Evj, PED-OP-3.32 i i / i!

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y 1 ramt m M CALCULATION PREPARATION, REVIEW AND APPROVAL CALCULATION NO* FORM PED-QP-3.4 Form Page NO.1 Of 1 F C - 0 5 "1 i b PRODUCTION ENGINEERING DMS10N CALCULATION SHEET Rev.NO. A REF. DG-1 Derated Power NO* ggg n o o e_4., A s s e.rr T e. 4 9 10 deg F Fan Inlet, Ethylene Glycol Coolant Time Turbo inlet JW temp KW Derate Derate min Temp F F init k KW 0 118 125 2627 100 2627 10 118 174 2627 .99 2601 20 120 200-208 2627 .915 2404 30 122 200-200 2627 .91 2391 40 123 200-208 2627 .907 2383 50 '122 200-208 2627 .91 2391 f 60 123 200-208 2627 .907 2383 70 124 200-208 2627 .905 2377 90 124 200-208 2627 .905 2377 120 125 200-208 2627 .903 2372 I o L DG-1 Derated Power 1o4 D66 F AMB IG~rr Aia l 105 deg F Fan Inlet, Ethylene Glycol Coolant Time Turbo inlet JW temp KW Derate Derate i min Temp F F init KW 0-t19 II L 125 2627 -140 l** 2627 i 10 -144 ilt 174 2627 r99 i.o +601 242 */ 20 _144 t14 190 2627 v4SS 1.o -ases ut*8 l 30 t2+ i t b 190 2627 .-999 99'S G641 2/ot3 40 i+9 t t 'l 190 2627 ,4 M.99 &&5-3 26" 50 ist til, 190 2627 .4M. 'I95'- 2561 ~M*l'a 60 144 i tl -190 2627 .4M. 'l9 255-3 IW 70 H+ ii B 190 2627 .4M.9 87 25&-3 W3 I 90 1-24 it 8 190 2627 .4M. 9 0~1 2999 23 120 its oci 190 2627 .49e M6 tSts - 15M f ~ .g T

o carn ha 15 CALCULATION PREPARATION, REVIEW AND APPROVAL FORM PED-OP-3.4 Form Page No.1 of 1 CALCULATION NO. wc.- o sn t L. PRODUCTION ENGINEERING DMSION CALCULATION SHEET Rev.No.- A REF. DG-1 Derated Power i d e " A4 BIEE. A I A. 5 109 108 -19& dog F Fan Inlet, Water Coolant Time Turbo inlet JW temp KW Derate Derate j min Temp F F init KW l i 0 4-14 til, 125 2757 +00. cpiy -s757 270 10 1-19 114 174 2757 v99. %5 E-7tt 2.W3 20 190 6 6 190 2757 r4G&.9F7 @+1t 4731 30 ist Ito 190 2757 cG7-5.965 N 2715 40 444. T 2.1 190 2757 <G42.963 2680 2150 50 144 12o 190 2757 .495.985 4 6 9 6 2.1 15 60 3 82.5 190 2757 .9tP.493 34 4 & tilo 70 -1 3 4 6 2 2 190 2757 .47s.'lB -4680 7-7e( f 90 434 t2,7-190 2757 .443.98 2 6 80 V/c1 120 445 12.3 190 2757 ,KLQ- .9~77 2 69+ 76*3 4 DG-1 Derated Power

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t io,15 F NetCW A4 } 1+0 deg F Fan Inlet, Water Coolant ll Time Turbo inlet JW temp KW Derate Derate min Temp F F init KW { 0 118 125 2757 +00 Si 94672727 10 118 174 2757 .99 2727 l! 20 120 200-208 2757 .915 2522 30 122 200-208 2757 .91 2509 40 123 200-208 2757 .907 2500 L( 50 122 200-208 2757 .91 2509 60 123 200-208 2757 .907 2500 70 124 200-208 2757 .905 2495 90 124 200-208 2757 .905 2495 o 120 125 200-208 2757 .903 2489 f-c i i U.1 L .i

cur.netn % CALCULATION PREPARATION, REVIEW AND APPROVAL. FORM - PED-QP-3.4 Form Page NO.1 Of 1 CALCULATION NO* vt -os% PRODUCTION ENGINEERING DMSION CALCULATION SHEET Rev.NO. A REF. DG-2 Derated Power it; tto Jes P M8w A LA -iit deg F Fan Inlet, Ethylene Glycol Coolant \\ Time Turbo inlet JW temp KW Derate Derate min Temp F F init KW k 0 121 125 2627 4 0 0, H i" a+3-7 25B7 10 124 174 2627 .973 2556 20 127 200-208 2627 .895 2351 30 129 200-208 2627 .89 2338 40 129 200-208 2627 .89 2338 50 132 200-208 2627 .88 2312 I 60 133 200-208 2627 .88 2312 3 -70 132 200-208 2627 .88 2312 90 133 200-208 2627 .88 2312 120 136 200-208 2627 .875 2299 DG-2 Derated Power i go, 10(,

C 66 t(# ALA

-99 deg F Fan Inlet, Ethylene Glycol Coolant Time Turbo inlet JW temp KW Derate Derate i min-Temp F F init KW O itt i10 - 125 2627 1 0 0 A 9 5' -Efr2 9 2t,lti i 10 4-24 524 174 2627 .r99t AB S' -asss M67 20 14-7 it'4 190 2627 v960.ct 13 2522 2m 30 1-29 t 21, 190 2627 rG6~J. cirn GG441eo ( 40 449tE. 190 2627 .45-7. ' EG-14 *S+P 50 4+2-t 19 190 2627 r944 4 - ? .s400 **8 5D4 '60 109- (So 190 2627 r945,9ST Met M .70 132 t19 190 2627 r94 9 .9 5'7 9498 W SfW 90 1-34 130 190 2627 .-949."E e492 "l-@8 120 afr-i % > 190 2627 r+417

' W G+69 1*f l

+ l i ) j (I!E 'W

rara m n CALCULATION PREPARATION, REVIEW AND APPROVAL CALCULATION NO* FORM PED-OP-3.4 Form Page NO.1 of 1 nc.-o sat i t, PRODUCTION ENGINEERING DMSION CALCULATION SHEET Rev NO. A REF. DG-2 Derated Power NO. l(O \\o%

G M 66 W

-143 deg F Fan Inlet, Water Coolant Time Turbo inlet JW temp KW Derate Derate min Temp F F init FW 0 -iti-W 125 2757 100 AST 751 2H 6 10 +24-l'L3 174 2757 M2. 9 4 E600 Meo 20 29 Itk 190 2757 <96&. % 7 M46 %64 30 4 itB 190 2757 e457. W 3600 2.6% 40 2 9 t'z.e 190 2757 cG&7 2430- % ^ 50 442sti 190 2757 . 9 4 7. *'5~5 M10- %33 60 14 l 3L 190 2757 .-S tS'. 9 7 2(r05 w'l [ 70 142 ist 190 2757 rt47 956 24-14 M 3' R 90 443-t31 190 2757 .446. i f 260S24M .lO 4591 '26* 120 446 s 3 F 190 2757 S40 DG-2 Derated Power ig llo

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I t-14 deg F Fan Inlet, Water Coolant Title Turbo inlet JW temp KW Derate Derate min Temp F F init KW i-0 121 125 2757 -tOO.987 G-7-5-7 2718 10 124 174 2757 .973 2682 20 127 200-208 7757 .895 2467 i 30 129 200-208 2757 .89 2454 l 40 129 200-208 2757 .89 2454 50 132 200-208 2757 .88 2426 60 133 200-208 2757 .88 2426 70 132 200-208 2757 .88 2426 90 133 200-208 2757 .88 2426 120 136 200-208 2757 .875 2412 L i i REV1 1 iI

4 rac ru no.- IB . CALCULATION PREPARATION, REVIEW AND APPROVAL CALCULATION NO* FORM PED-QP-3.4 Form Page No.1 ofI src.-os9 Iw PRODUCTION ENGINEERING DMSiON J 3 CALCULATION SHEET Rev.No. REF. NO Pl.or T4 DWkso ?> Ju. Ms T.n no n e. aecs,tso Pos Vs Ti% to de u+ i w_. ce a o r, o s s 7 ec. o,es e u $ P %~t~1 oa /~T G& b'%D 4 s L., rs.sP W W L< 5 c 1 s ) Y L ) Y.

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m... O e. e e O DG-2 ENGINE DERATED POWER : AND POST-LOCA POWER DEMAND vs. 1 TIME 2800 2700 A ' = 111 degt ran InM.112 degF Amb.bt Air. EC ^ 2m 0 \\ 107&gFTen hM.1C6 dqF Ambia8 Air.EC C e 2400

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7l Calc Preparation, Review and Approval PED-0P-3.5 Page 1 of 2 CALCULATION NUMBER Reviewer's Checklist-Calculations FG- 0010 eA JJ.S. M N/A 1. Is Calculation Cover Sheet attached and / completed, as required,*.o the calculation? V ~ 2. Is the calculation objective stated 7-Was this achieved? / 3. Are' inputs correctly seiected and incor- -porated into the analysis? / 4. Have inputs and/or assureptions which requir confirmation at a later data,=been identi ed on the Calculation Coter Sheet and in t calculation body? V -5. Are the applicable codes, standard. regulatory requirewnts, and oth references including issue ant, addenda idgittified such that they are trace 4.ble to-sovrce document? / 6. Was an appropriate calcul i n method used? Was the basic. theory ap opriate? 7 '7. - Have-' assumptions bee noted and, justified? / 8. Are the calculat ns free of' arithmetic errors? [ -9. Is the calcy ation consistent with the design ba is requirements?

10. _.

Is the onclusion stated? 11. Is e calculation legible and suitable for m' refilming? / Y 1 ~ i I PE0-0P-3.34 i d Rev. 2 g -i

'Ab Cale Preparation, Review and Approval PED-QP-3.5 Pace 2 of 2 CALCULATION NUMBER Reviewer's Checklist-Calculations f C- 05 M V rb YES N/A 12. Are all blocks on the Calculation Cover Sheet addressed correctly? / / 13. Have Forms PED-0P-3.2, 3, 4 and 5 been used and correctly completed? / / 14. If the calculation has been prepared to / supersede another calculation, has all the valid information been transferred in the new calculation? k F / i REVIEWER COMMENTS: / I l /Y,2d-9,2 Reviewer F Oate t k t [ A PED-0P-3.35 i Rev. 2 or N

I-l Calc Preparation, Review and Approval i PE0-0P-3.5 Page 1 of 2 CALCULATION NUMBER Reviewer's Checklist-Calculations FCOS9/G cb e u YES NQ W,A, 1. Is Calculation Cover Sheet attached and completed, as required,to the calculation? 2. Is the calculation objective stated? Was f i this achieved? 3. Are inputs correctly selected and incor- / porated into the analysis? I 4. Have inputs and/or assumptions which require confirmation at a later data, been identified on the Calculation Cover Sheet and in the f I calculation body? 5. Are the applicable codes, standards, regulatory requirements, and other references including issue and addenda identified such that they are traceable to source document? k -- 6. Was an appropriate calculation method used? Was the basic theory appropriate? 7. Have assumptions been noted and justified? 8. Are the calculations free of arithmetic / errors? I 9. Is the calculation consistent with the / design basis requirements? 10. Is the conclusion stated? 11. Is the calculation legible and suitable for / I microfilming? .g. i i PED-0P-3.34 4 ha. 2 N

l Calc Preparation, Review and A;- aval i PED-0P-3.5 Page 2 c: 2 CALCULATION NUMBER Reviewer's Checklist-Calculations F C - 59 t h r 6 rzt j YES EQ N/A 12. Are til blocks on the Calculation Cover / Shee. addressed correctly? d 13. Have 'orms PED QP-3.2, 3, 4 and 5 been used / and c.rrectly completed? l 14. If the calculation has been prepared to superwide another calculation, has all the / valid information been transferred in the f ) new c4'culation? -c k s REVIEWER COMMENTS: 't a i C W / Sf7ff2- ~ Reviewer Dats ' f PED-0P-3.35 f Pev. 2 \\

4 e <

Calc Preparation, Review and Approval PEDeQP-3.7 Page 1 of 1 CALCULATION NUMBER independent Reviewer's Checklist - Calculations i

FC' 05% Ch .Yf_$, M N/A 1. Are the calculation methods accurate and appropriate? / 2. Are input data sufficiently detailed? ,[ l 3. Are the calculation assumptions reasonable? /! l Hasthebasisforengineerin! ion,whenjudgement/ 4. b includcd in the calcula p 5. Is the celculation documented sufficiently .such that the analysis is understandable t someone competent in the discipline without recourse to the Preparer? / 6. Have the desi n interface requirement I been satisfie ? / / 7. Are the resui s reasonable and do they resolve the calculation object ie? / 8. If an alternate calculation as used to verif the adequacy of thefanalysis, is it I attac ed to the calculation? y 9. If qualification testi was used to verify the adequacy of the apa ysis, has-it been documented using a rAtrievable source, or attached to the ca tulation? y 10. Are calculation involving Technical Specification falues and associated margins of safety ideAtified? y i / / / INDEPENDENT REV1 EWER COMMENTS: 1 l. 'bh l % 20-92 [ Independent @ eviewer Date bi PEC-QP-3.38 Rev. 2 l ; W

Calc Preparation, Review and Approval PED-0P-3.7 Page 1 of 1 CALCULATION NUMBER independent Reviewer's Checklist - Calculations \\ R-o.59/d 8. 3

J_E_,

N/A E 1. Are the calculation methods accurate and appropriate? X 2. Are input data sufficiently detailed? 3. Are the calculation assumptions reasonable? 4. Has the basis for engineering judgement been included in the calculation, when f used? gf A 5. Is the calculation documented sufficiently such that the analysis is understandable to someone competent in the discipline without recourse to the Preparer? 6. Have the design interface requirements N been satisfied? j A p 7, Are the results reasonable and do they resolve the calculation objective? Y 8. If an citernate calculation was used to verify the adequacy of the analysis, is it attached to the calculation? ,X 9. If qualification testing was used to verify the adequacy of the analysis, has it been documented using a retrievable source, or ~ attached to the calculation? 10. Ara :alculations involving Technical Specification values and associated margins 2 N/ of safety identified? ,/\\ s INDEPENDENT REVIEWER COMMENTS: _0 le9 o 9W Independent Revifwer / Datb PEO-QP-3.38 Rev. 2 i ,s g

. c: g gggy 7p ] i' Y. - :.' pjESEL. GEldeKATo A IXERA TIo M 'Ui"I 74-l CURVES.2a-2 ENOW 4 TilmIFSRATURE S#fTCH NOAsINAL sonen l ps mw, 8N#8 ~ ET3 I I 208'F l l ETS or 215' F. 203' F' l IT5 2 i 373 i b Het sagtas alare 8C. HC. 3.- IT3 - Het espas aarum MD. LD. IT3 2 - Het anpas shutdown 5C. HC 3..

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am strass femeenatums L f Rating at Ejersted Temstrature ('F)- PorEMD84884 tI( i -s ..>:s .m:. .: :wcu st :

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pauwpm,x:. i18 - y, 21 ...y 31 nt 'g . 41 4-51 u 4nw cvei.= tecosvet.= 243e vet... 23603 vet.=. 2soo.gvet.= tszegvet.= 2620@ vet.= -235eMvet.e. 2440 ivet.=1 .26se y g- -61 g. 71 Q 81 c,g

m:

.g: ' 156jj} vem.= - 153yreap.= 54y re.p.= 15 re.p.= 15 - t em. = .eap = .155{.re.ps iss i te p.=.

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vei.=

26togver.= 6z - 27teg; vet.=. g. 72

n 82 te 9z.

g z27o gvei.= z32ojyves.=' 935 dvet.= le p,s " f56[j renp.=- 231am vet.= 2623:qves.= - 2770[ vet.=." 246eb' 150g temp.=

153.g fesp. =

155fTmp.= 157j' Temp.= 157{'jtemp.=. 151%yt f enp.m. L 147[;, Temp.m. ~ 145% ' y y ..a + 4 v s, b $[' h Yt MI$ $iikN. bb. b5b hh!Nhb h.hNh3 .h.5f5k$',h .s, .+0 qn 15 Z., 1 23

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-y - 73 hhkk.$ '.M5$Nhih 2 Vet.= 2800Rvet,= ! 3020{ vet.= - 2490$ vet.=' 2491)(vet.=' 960livel.= '2370dv.et.= 2400Vvet.s D 2700Myet.= ' 2580EdJ . 41 .;g L 93 - '4 Trap.= ' t46[iene.= 1476 iesp.= 153E.Iempt= 154[3 cap.= 155%q emp.= T T i 1513 esp.= - 147'.]1 esp.= 145;gre p.=. '.14 a i '. j r u .g; -.gn.T .i1 ;m ?r ptygyn. tar;gh,j.m; fen gea:tb JMrM"Mi@;tyu t 'tht t w..itt. L'N... =o '.,?t.h..g gm.. N jp y = v.e m , m,. p u. T - .c,.. a v ah. 14 24'

u. n t.e.a < A.. ',.p)y '?f...~:W~W. J,MMa*-91 g tu d

253c y$ g - m,= 86c (t:: vet.= .p, s s g 34 ' i

44 -

3 A mpa. any wm 54 - 64 -. Q ' vet.. 26303 vet.=- . 28053 vet.= 2600 n vet.= 74 E4-14 94 Q:, vet.=. teap.= 146';, tcap.= 144 g reep. = 143J Tenp = - 147lyicap= 149 y resp.= 2t90})flem = vet.= 20so3 vet.. 241c3tvet...- 2260 tit : 146i 143'/j icap.= 141@e n II.0 f;- ' it 3 .a r-Temp.= w -yJ n.gp %$PWHn.up*qF pig pu. ;f c:?n. tgNagem..a:heuhm.g.. s u ,.. 15 . s. s y, w + 35 w:,. qu a a n n uw w.$1p.q. w; p..x,[:w..y.&s.q;gt,:d;hw%a...aw& q gka

w. ~

m 2380@... ') 2 mw k g .45 g 55 ~ 5 2t100'd .s p..ae c 65 i 75 g 85-vet.s , Vet,= 2440,& vet.= l 2050 9.. Vel.a 2100 K. vet.= 890 4. Wet.= .g 95 g l esp.= 143p imp.= 140g teep.=. 142} Temp.= 144,, steep.= 144 g-temp.* ' 139p fenp.= 141.y rcep.= 138p; re p.= 139"3 g avet.= 1960.T. vet.= 2180 A vet.= . 20 M P., m p Qnt

p ?

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3 >.a J M W S. M ru t m Equipment used= Ist Modet 8350 vetacicalc, MT-00077;Digitat teep. NT-10104rM.C,.. a.r 3. p+*d 2.%, L $, pm,. . 'c '4; r a.giWsv mFre ~n.@em-c@.. h,,.; ev '.h.3,p'di@t/a %'M1M.,r@q% t;."%e* 4 .ri 4 U J ~m t m .w%.,. n = m.wm M vet. = 'tetocity in it./ Min. (standardized to 70 T. and 14.7 Psta) Tmp. = Temperature in degrees F Tiele cosatant = 15 seconds Intet femperatures ' - (18. = 77.7F)," (E. = 79 F), (v. = 77.2 f ), (s. = 77.2f) MWo 922344 xN , f';i7f f G ~%' Y $ ' lb Y 'D ~n n. . ce z O. ' si r.,e a ' 1 m

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wa a

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t unmm. as --- n ,e-w ..,.3 -rj. w m.,, j'i 11 .E 21 31 41 51 61

2 71 T

Si - _ a.-- y au mu uw.u r a -p-- 2-_ - - =w,= j 91 ill sCf Ms - 2521.11 2 sctM= 2485. I scfM= 2254.44**Estfm. 2545.67 sct> 2456.67 stFa= 2611.1t hsCPN= 2543.33 lI scr> 2556.67 scFm 2677.78 ll t '%gl temp.= 132.7ETemp.= 130.4 yleep.= 132.3Niemp.= 131.2 2 y 8 ep.= 130) Temp.= 128l fop.= UI te 117.3 [ Temp.= 118.1 fesp.= 126.3 E -4 I nr E'* ::;t#O9; qh:mue.m.nw. w".L.mf =':::Utti mutilm10.%. ";p:::.'c:dSM.p..;,, w2w - g; .we r - m"- u .o m.... .w. .,w.!!* u '= 'n ns:::n:1 3r,

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12 'dj 22 32 42 52 g 62 72 u. ~ rt 3.stins. 2571.11dj scf M= 2567.78*.!$CFM= ThistfM= 2316.67 q 82 - 92 4 L 2061.11),- g SCfn= 2135.56::tscen= 2445.56 sctw= 2622.221 l scrM= 2797.73 scr> $3 teg.* 133.2!!: temp.= .126.7!iiteg.= 129hfeso.=, 128.2hiesp.= a 129 fesp.= 123.4 Teg.= ' 115.5Miemp.= 111.9 thiemp.= E ,L,..,:.u....,35q, m n it; !ll - -- --118.2d)f C:":::. :.:nnn:n............. -* !:"...........,.j. .n. y,, ?- Gr C**. g;.u v3EI m f*f

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1. =E' M

15. lji 23 id 33 Ul 43N 5"3 5MU'- 'dM"G I hicep.= 2851'.1t hiscin= 2912.22!i} stfM=2475.56EsctM= 24 33 scfM= 1564.44dscr> 2347.7s]Iztr> 23es.894t'scim. 2674.44!, !*** ***'9"3 j'iscip 43

R 73 f*j a3 g

' str> 2422.22 y-120.a ttj iew.= 122.4 hj resp.= 126.6E reep.= ' 121. 't fesp.=

123 temp.=

121.5@reep.= 109.3MTemp.= g I:t 199.6 Temp.= 106.6 i.n.c...u;.x. int.:!i.N.~l:.t.r*miwis:tinIEeW...:"m.it.i.!.:.!a"d'~4._".n*:x t.W..o."ttaa m 3

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_ M.ff!F. ' E ~.. - mm 7. N. , =

G 14 -

fy 24 ["t: 34 44 .g .bstfM= 2490'.*M.. scfMa 2722.22 scF> g-64 74 ,y a'. } O ig lscr>96 D 2462.22':'"fCFNs 2326.67 sctM. 1 .33.scFs= 2153.56 scrM= 2180ll 'scrus 2133.33 l D gleap.= 112.7E..j fesp.= ' 115.9E.3lleep.= 121:Xjtemp.= 112.6,,, Teep.= 11h41lltiemp.= 111.4, Teep.= 105.1.gifesp.= 102.6l reup.= 101.4!{ 2227. .d.' p a N. Tim.sponeN1'k: p:wtim rsaw$jhi;:miim:7. in;;sN!mnmiems li 3 ~ issmL J 7tT::" I, .4 m

n

W..unta n1%

a:1t'.3C? aN:l"*.',M Mi.3~!t'S'li'=N2*'*3...m..- as...

jh ..m:n:1*unnsc:'t;;;;**12:1m'mminminra".= E.,

M 15

f..t 25

$.Q 35 T.,; 45

- E 55 4

Immmm-~ ..eI ?! e. 75 - 85

OstfM=

2200 T.:gl.lscf M=2415.89:dsCFMs 2144.64'.C.stfM= 1955.56' scfm ' 1068.89 5C7m= 95.

~

.67 scio. 2833.33tsasc7M= 2227.78 i'scin= 2133.13 I.!;. 'O p ieg. = 107.4 le Temp.s 101.9g f eep.= 111 yJTeap.= 107.4d6iesp.= 109.2)yu f erp.= 9 fesp.= 100.6,. ggt. Temp.= 96.5 resp.= 98.4g.- .a i ix .19

n._g._,.6. - n.a..._.~.,. w... - _.

3m::r..A. hr

a_;m:.w:n_nm.

3:: e um;n:; xem:n:d. ilhmaugrm::ur..:J, n+.u,.annummam c+)

m...

a._... n:::;r. = ea..,. nn;:c: men;cx:m;:en:= m; total cattutated flow Rate = l*05451.1lsctM Average Temperature in Duct = l 116.94]Degrecesr M odM Mm >m (- s P.T E Page 2 m

.-v qqr, u ik y a>

12 sisde, 22I Degree Pitch,.'DC-2, 6-10 92-

Calculated Flew mates

- WMt,i*(aj;t@MQi t.4t,pWW@t"e?pMPQgf'm.%a?$U3$.Q*gjt;'sTW!gitm**4gT4WpP R t*f. y s. v d 1I 3 .%p. -- 31 m m.e ~ 41 p y..st m m.g.a.a m m,. 21-4Nif. m,m,m . %p% u. :Ef 4jrp*O.tgg-EMy,q~ t: ;MnnM:=e,m=rn;p. y 51 2622.22p :cfM= 2777J8gscfMz ; " g 61-pSCFM=. i 2888.89, {yscrits g ~ 71 ; .st: ' pun 2700MSCfM=- s 2022.22,pscrM=' 2911.lfpSCFM3 ' ' 2611.11(, sCffts ~ 27tl.1 thy - 93 y, t ese. = 156 Temp.= 153k temp.'r ' 154'q temp.= ~ 1.5K reep.=, ~ 157 Qv eg.= 155$leep.= - 153Mlerp.= sCins ~ 2977.73h' a 1n 9 yr:m,g %n &y p

g t

W 6' +M ISS7 dig.= 150 [ m&nis%ch lqi.,... u.a;;p:Q,. yMQ:wsQytrGuesytwry@$: ^ nq w u. h: A w ? ,p gyn.Q nm.,; -m w:sf.: w, y Awa q 12 M 22 uwgygA w wn;y y.up.q % g d'{ Q+,g,g dhm T 'd, n g;j 32 42 pscrM= 2900;p sCFM= 3et 1.11Qsc5M3 2522.22 -qp 52 _ m wmg j 62- . -Q 82 ,R 92 ~ p 72 j SCFMs. 2577.73;'f scrMs - 3038.89 Qstin= 2566.47E;scta= 29 t.11yscrny

reep.e.

156Mtemp.= 150 gtem.= 153 Q-- teap.= 155pt reep.= 157Eirm.= 07$tw.= 151,pf te.g.= - n c4 Jp> gx. p;.c g.n@g.;n -.p y:p;a -3 r.' t s74 :e,.= . v.5 ^ .f r J: M 3.)d g w[gM %g:%m pM;7pnjy;p$g;q.o am 4t; g syggt;J"n '?Wy m.) wp s 'gq.pn @t n 13 .. A 23 33 w. vf cQ ya,w g %g&;,%,,u,4'y.%,y, f:q y g Q-gg a lsCfM= 3111.11{sCfM= 3355.56 YSCFM ' 2766.67d' j5Crn= 2166.67%sCfM= ' 1066.67.O SCfM=. 2633.33hstfMe 2M6.67$p 3000k{sCFM3 - 286

43 53 71 61 15 73 83

? 93-4:T ev.= .246 $ teep.* f1473.yfem.* 153 y Temp.=. 154 g Tesap.= ' 155i% Temp.* scfM= .r V; S 1511t tem.= 147:4 7ey.= ~ 145}hTemp.. .141L n t S. ea.... y,.. g1 n n- -5q n; M g 9 :n . 4@wo;7%g; 34 Mg13Mm 4,dpytea htm.4 hr agptw mnm(M;p;y e.e >._ p n;.,g.5/ws. 1. Jp,.:m..psw,qqty,c._p;gg:ggg,,%c g yg#. v e p.s ,s. i 14 s~ a .,4w. de ty.m w 24 .e qf* p o e g 44 54 .istin. 2922.22 i scrne 3116.67 4scrM= - s en 2888.89 hstfM= ap 64 ' 3 74 146 jleep.= 144)[ Tem.s - 148M ienp.= " 2811.11h stfM= 955.556ilistin= 2433.33 W(stfM= g . 44 6 94 t em. = e 2311.11Fscrte= 2677.785[stin* ' 2511.ttb 147 Eicy.= 149 h icm.s - 1r.6 'fewp.= 143{ teep = 341 D 7,9.= 34o y 2. dl. , k <*y

h f&Q&&hft 3'

2 * &GilQ& l;g.% i & !QQi;Q 2-QQ'f)]{ YfRQQfy '3 ' ~yf* pt 4 .- i 15 25 h 35 ' n v. h l1: 45 istfM: 2644.44.jsCfN: 2713. II,'fstf M= 25t t.lijsCf Hr 2333.33[sctM= 988.889h SCFM= - 2222.22hr 55 sh 65 e 75 s. 85 - k 95 fleep.= I43 ; temp.* 140gleap.=' 542 ;1cep.= f(4pleep.s 144preep. 3397 t e,.. ' 141 g re.p.s g3sg ge.p,. - g 39,- 2177.78[f5CfW 2422.22ii'SCTMs,2322.22h 5CfMe .e ^** -.N.. W 3.(W Q M* e s '? t c, MQ4% }*!Q.. ?.(g. } 't.t. -? w 4t.$,.$idf,as q. 3 e 4- ~ 4 w e ?.l. $. ',.,, 3 g g,[, fg;t=.u'P g ;, g.**$b.f w 4rt**,c. 7 3...- m

WuM*

-r 3.g g g gy,, e m. total Cal (clated flow Rates [114$$5.6lSCfM Average Treperattse in (9tt = .l 148.16l0egrece$F t 4 j - t' N '_l - v1 f ._D Page 2 t4 -N g -. y- -e

r-- W W-

~ Am.M ~"' 4

pc.ogs ep 'M i j'.% -4 n oz u sans w : h w ah g?swam 4>4 ~8 :v l8 a,.R, $ a,; ~e ?$ n Q 48 a2 o% ~ m-y. it 7,y n c. y n WL 6' ' '... a.. >a . - #.e p n'w,"ALs.. mL 58 m '@ _ p. w : g n~e,. s .g fg _:g ~d4 a Ms,. _ iQame g ro m sPEMta m pt ,. _ Tt +.,. _ , - - < ry 4. r.5E D P m [8 9 j8 ? ~Es $ ga qL a D ~ w, m: - s ,a ,r n w.-. 2.. m,a.. p s.. 9 m i, _t ?,a. t a. a i i i, _t : m, i _t m e,n s s y m, _t A o i_ w i L a a po-- - ~gj p( x n n-3 Es a is ne r =g 1' Hg g a ( F a 3 Q G en.,. n.,. mc.. s c s i4 y t% i,.t - a,u..i>.t T i, _t .v i.t. Mem,v*.t. M. x,.. a Mi r. >a .x s 4* s f;"*yt ym% y ;.;*mM.m'rfi e & JVW;:--* j -- w wssw.

- P. n N

h3 RS ]a xO hd k 8 - E ij h s afj R s 4 ~ a~ xy a 9 d

d..

.M Y q JA 59 w ~4 a w$5. t.- Ma m klam, _aMmmu,r_t ed,n_ @ha,.. Sa.. (W 1 i, _t E .a s.. 9 1-4 y g a Ni 9 i _t s.i i f 4 a eka c%_yM w EE 44 nSE O.[E D $8. pl H 8 9 L a-3 by 3 N' iM M a a .i. ,... rL ~tw.. ~.. a . i g x,. i. e v.. w.,mm.i u s,_i m~ ~ p a 3 s,_ . _t 9 s_ u _n-ws 4 s= _m n_n_mn~ _w n m: am,ws e. m a _s a w g s n m m - at e e er: sa m,& x ' 'e h" }a;, g - &~ N kN a y N N gy w~.. n=m._t' s- . e a 5 m a n . a as.,., ,a n e ~ p_.-. ~ n.- e. w : _g u _ _g gg _:: p g,- _:. p a.o : _g L=u ~ u g.- -m 4 ~ m z iw=mammerramammme.l a w =a w sa a %n e R n-p ~ge a s~ p S b4e ps-a nnu A u 4 un, e r. _ n.2 u.w m 4 a ~O e pr y....-. .. gwm hy .m AM pf e p*m ^ n.. e, m m 7G_R?fD QM;$ _*MfC*TTU?a"3"*}[WM M 7 %lu i,_t u n.i_t y i,_t n i .. -_u'~ 4 s n e Wi u _t: W a x s. QM_@Z%m,. M g r m uJ. ~ s s., _.e. w a se r s.a e s+2 p; , s - aA s,a e.>so_- a dg w.. ~ w~ a~ w e~ x= e 2 ~ 4:> m~ ~~ e ,a. e n: 4. n~.t s:,,y;e +m ~ ~ ~. g~.. n g? .t = w.i w~z,.. -A - _.. z, _i .t' r .m N'dfMTMTNTM.wgy *g/M?-W? < WMJ:MF '.f UDUTd N h6UY bN , 3, pwp y .g.- um, .o.,. a^ ,.y .~. ~. ~. F. N n-N N L 4 g, t,_ c' z _ g _l-d I. h %= s~.. .. m m. 1;..,, n-i t :.-.., _ i, _t i,_t R_ i _t._H_ l l ._.:.s?**'+__t

i t e i

e. , ~ w'<. w., -M7""*P'W*T'"*T W"**9f%**M**tM em5 **wn+7*M A; f m g. w a n. f.' a u; an

=* s D ' Cateutered Flow setes 12 stede, 22 Degree Pitch GQQ[?QQ}fQQR}@hQ:f[f fj$ [ Q [ Q QQff j~Q QGf g g g - h. 21 - 9 11 31 ' Efscin= 2711.11 h pgggy.ggg - 6 I 41 51 Q scrn= 2661.11 jstrn= ' 2527.78pjscrn= '2243.33%gstrn= 2166.67gscrm= 61 T1 81 i 91 jife.p.= 122:LTe.p.= 2355.56 sctm 2677.78 ?scrm 2755.56 scrne 2343.33 117 pre.p.= 120pjfe.p = 117 T e.p.= -

119 ate p =

' 118 ~ Temp.= 123l!T.sp.= 117 Temp = (N 3 jft W.d f b' w: t. Y > q. 7l%?.9.M.n, W f; m M"W%WTWWT%y._m.ng. Tg_a*%m ")dT*?7*,"73.m ,19 V 7BT i c h

s

.x akn Lw%.na 5 [3 n 12 22 7 32 42-mm,. Am d QVM tWTN w 2876.67(f scrM= _3000 scrn= ' 2622.22,j$- -g 52 62 g.p 72 sy [uscfM= '3366.67h 92 .1 s2 scrn. 2600 jstrM= 2588.89 scrum 2722.22 a sctn= 3014.44 scrn. te.p.= 111(ve.p.= tio te.p.= J 115gire.p.= 114 9 te.p.= 9 sctm 2644.44k 119 ]re,.= L

a 115 117 r p.=

1024 1 p.= tosh p w w,e re p.= M t mmy w w w& n m m e%p m~ y m s-Q ..,M w 1 m m 3 p: pd I h h sm pdscrM= 2eco[1xc u.n h n w ; aiy&mm.pg.,m;xz9y) apaa pwww afjmten.2,mu dwLh,i w.up 13 g 23 33 Q 43 m

agm.me p

53 i 63 p 73 y 4scrn= 2711.11gscrn-2533.35pscrn. as jscina. 2311.11hscrn= 3077.78g,scrn= 2777.78s scrm 3177.7s scr> 2744.44k 93 p 2442.22 ylem.= 96 p i p.= 99ptem.= - 112qre.p.= 104 qrem.= 110 g re.p.= - tongre.p.= - to5gre.p.= k k , n, au.:y;g m.- m& W m p%.Q m y gk,p[3 90 re.p.= 94 m.asa pmzwa u%mwm&z.pwytw-gyyym.w.&)4 mmkywy mm g j! g( 14- ,m e a-en u.c+- m 24 n 34 m L 2411.11{dscrM= Uscrn= 54 n wun g 64 r 74 R4 84 2500$sctn= w .2731.11 (; scrM= iew.=' 2622.22M diem.= 91yie.p.= g pM 94 2033.33 Vscrne 3144.44 : scrn= hscin. 2600p?Ie 102%g 95 iesp.= scr> 2988.89gscrn. 2374.44 93 re.p.= 96 re.p.= 95 is ,g. gg begg.,Q,.= 86[ tesp.= 90h ~

(

O. i 96 c g p.= t d o ,, g g w g g g g y 2 9 9.7 m g y p. r p; .. W c: 9,m i;yd Jos ganl}a&Gdbg ? C m heeantWsw.4 $p.ympg p q*d4 aa f, . h,. m L 2 f 24 p ~. -. s 3 15 dj 25 ami mhew.d W 4 - pg .- 35 EQ 2155.56hscrn=45 [Niewp.= 1783.33M scrus 2738.89[0 IscfM= 55-65 f 75 ( 85 95 if 2377.78"' scrne 1977.78gstrn. 3341.11 dsctn= 2222.22y)sctn= fij scrn= 87 M ie.p.= 89 Te.p.= 91 Q Tenp.= 87 Te.p.= 90 Vffe.p.= 2311.11Qscin= 1816.67% ih !4 L 859 T e.p.= 90 : Te.p.= Bo b ie.p.= 82hj d-Y v3 A > y,p mzb gmc.g pm-QQp,ggy, nspyggMgmygg p Q w qqwyy mmyy

a n z%;s t m;

- w wwweflub% gens c, w m.cagae-w.e m;saanb wse.;n c wg.p.yg.yp j total calculated rtow Rate = { 116583.3]Scr4 Average Temperature in Dutt = l 102.49]Degreces r Y. c 4ggW gp staJ T 84 1 b M 3.- a C ^% '3P y7_ _ ~. _ _ y.

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FG- 0 @ th ') ( d. ALTI NDE.BEI.ATIVE Dmb!TY TABLE FOR AIR Al titudes in Feat.--Standard Air a t 0 Alt. (29.92 In. Bar.) = 1. Al t. Den. Bar. Alt. Den. Bar. Alt. Den. Be r. Alt. Den. Ber. ~ 0 1.00 29.92 1500 .944 28.26 3000 .891 26.68 6000 .195 23.79 100 .996 29.81 1600 941 28.15 3200 .885 26.48 6200 .789 23.61 200 .992 29.70 1700 .937 28.04 3400 .878 26.28 6400 .784 23.43 300 .989 29.58 1800 .933

27. 93 3600

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WET " J DRY
wrT "

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1. 0i 74

.992 .981 135 I .832 30 1.082 1.076 76 . 98 9 .977 140 .883 .817 !7 .891 2 + w 35 1.071 1.067 78 .985 .972 145 .876 . 602 ? 40 1.060 1.056 80 .982 .968 150 .869 .76o 42 1.056 1.051 82 .978 .963 155 .862 .769 44 1.052 1.047 84 .914 .959 160 .855 .751 4 46 . 047 1.042 Bf \\y .954 165 .848 .731 48 1.043 1.038 8f .9' .9 170 .841 713 50 1.039 1.033 90 .9 175 .835 .692 {1 52 . 035 1.029 92 .941 180 .828 .671 54 1.031 1.025 94 .i' .936 185 i .022 .647 I h 56 1.027

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TRANSMISSION FROM:

r NAME ON l.- l C'- TITLE E, WI C LEXINGTON, TN b CENTERVfLLE. lA 414 839-1013 901 968 3617 515 856 8634 /) DATEM / b /.h. FOEM NO. 3613 REY. 6/es TIME [ I I I'd w er,r. ra.es / 'i

WoT% p % .u/Wemorandum ..b_b_ M l' DATE:; July 1, 1991 PED-FC-91-472 FROM: P. F. Vovk TO: R. P. Clemens

SUBJECT:

Maximum Generator / Exciter KW Ratings for TUB Figure III.26.A The subject TOB figures (attached) were submitted for PRC approval on June 28, ~1991. The initial (horizontal line on the first part of each curve) KW rating shown for each diesel generator,is limited by the generator and exciter base i load ratings as shown on the attached data sheet on the generating unit c (Attachment 8.4-1 of EA-FC-90-062 Rev. 2). The base load KW rating of the L generator / exciter is 2500 KW (3125 kVA x 0.8 pf). Per calculation FC03382 Rev. 3, the actual power factor for the load on DG-1 is 0.87 and for DG-2 is O.85. This yields the following gererator/e.. citer base load KW limits: DG-1 = 3125 kVA x 0.87 pf = 2718 KW at 0.87 pf 2 DG-2 = 3125 kVA x 0.85 pf = 2656 KW at 0.85 pf A* The above KW ratings represent the continuous KW loading which can be . supported by the generator / exciter. Since the engine KW limit is greater than -.the generator / exciter KW limit, the KW is limited to the generator / exciter KW limit for both diesel generators. This applies only during the horizontal section of the TOB figures. The sections following the initial horizontal section are limited due to the engine derating with increased temperature. & /) 11-91 -P. F. Vovk Engineer - Electrical p Production Engineering Division PFV/sf "e; b Attachments -c: K. A. Miller D. G. Flegle l

0. G. Borcyk PED Library l

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TRANSMISSION FROM: t m l u NAME lbM TlLL. R TITLs ~ .a I ( h RACINE. WI O tExisoTon. Tn O CENTERVILLE. IA i l 414-639 1013 901-968-3817 515-856-E634 FCRM NO. 3013 "EV.8/89 DATE~ d/ /$ TIME .su. PM 3 L m q es:se is, si e ~<

.u. u... %,y agg,c g,g; f0R T ALHOUN STATION CENERA'.. FORM PRC Reviewed FC-154 PRC Mtg. Minutu R13 NOCLEAR SAFETY EVALUATION g Q g ;302 Reference N00-QP-3 !) 41. ID No.L10-92-207R SECTIO _N A Page I of 4 (from 9.1) 10-CFR 50.59 Applicability Screening 9.1 Activity identification Procedure Change No. affecting Procedure _ 4 Modification Request No. Design [ ] Installation [ ] Testing ( ] Temporary Modification No.- Engineering Change Notice No. Othor.Licensino Recue_st for Safe _ty Evaluation For C_ hance in OG Coolant Philosophy Occument

Title:

e k Nuclear Safety Evaluation Conclusion M -This activity is not a 10 CFR 50.59 activity, because it: Mt Does not change the-facility as described in the USAR. ..n g. Does not chanoe procedures as described in the USAR. -Does not involve conducting-tests or experiments not described in the USAR. g.2 u.

Does not affect Nuclear Safety in a way not previously evaluated in USAR.

+ .f (>d _ This activity is being done pursuant to 10 CFR 50.59. b This safety evaluation must be reviewed by SARC; ref Tech. Spec. 5.5.2.7. This activity must be reported in the annual report; ref 10 CFR 50.59. i Item b, Paragraph 2. - [] This activity involves an Unreviewed Safety Question. The activity must be canceled, or revised and re-evaluated, or NRC authorization is required prior to implementation; ref 10 CFR 50.59, Item c. 9' '- We hereby certify that this Nuclear Safety Evaluation is complete and accurate to 1. the best of our knowledge.

1 L

Prepared by Donald.G. Flecle Date d-30-92 Time 0 95 d Print Name 7 h l-Sd Extension loS79 n Signatore p Reviewed by b e n.to b dewas,vG f Date 4-to-9 L Time c

4 '9 Print Name M/s M d- '--

Extension 5??7 i Sianature # i A-1 lC/ FORMS T ~

+ ~ w.:nstro van c FORTICALHOUN STATION. l GENERAL FORM FC-154 R13 NUCLEAR SAFETY EVALUATIQg Reference N00-QP-3

1

-4D . ID' No.LIC-92-207R (from 9.1). SECTION A_ Page _2 _ of dr 10 CFR 50.59 Applicability Screening 9.2 What (specifically) is being done? Previously, there had been a commitment t: the NRC to operate the mergency diesel generator (OG) jacket water system with a solution consisting of deionized water with corrosion inhibitor additive during the sumer months. This )lan for DG operation was presented to the NRC in EA-90-62. OPPD has determined that tais coolant change will no longer be necessary. This safety evaluation will ensure that the change to maintain the 50/50 glycol / water solution year around does not constitute a safety hazard, k% 9.3 Why is this being ou y (briefly)? Engineering Calculation FC00916 has determined that the diesel generators may be safely -operated at high' temperatures even with the use of a glycol / water mixture in the jacket water system. I i .i. ? I 9.4-Does the activity involve a change to the. Technical Specifications? [X)NO- . This activity meets the requirements of current Technical p Specifications. The following sections were reviewed: 12.7 & 3.7 . Continue with 9.5- [_]YE5 Technical: Specification Section must be revised prior to performing this activity. . Exit this procedure and continue with N00-QP-7. f Lr ) l @/ FORMS

hFORTCALHOUNSTATf0N GENERAL FORM FC-154 R13 NUCLEAR SAFETY EVALUATION Reference N00-QP-3 '3 +t 10 No.LIC-92-207R SECTION A Page 3 of - (from 9.1) 10 CFR 50.59 Applicability Screening 9.5 Does the activity involve a change in the facility? [ ] NO Go to 9.6 i [X]YES Is this aspect of the facility described in the USAR? List USAR Sections reviewed: 6.1.2.2. 7.3. 8.1.2, 8.2, 8.4 [ ] NO Go to 9.6 [X] YES - list USAR Sections 8.4.1.1 Does the USAR description require any changes or revisions due to this activity? 7 k --{*} NO continue with 9.6 AM g.yo. g g. M YES 10 CFR 50.59 applies to this activity D" Section B of the Nuclear Safety K#-U Evaluation must also be completed. Continue with 9.6 't 9.6 Does the activity involve changes to procedures? E [X] NO Go ?o 9.7

1 7

[] YES Are related procedures (including definitions or descriptions i of activities or controls over functions) outlined summarized. completely described, or implied in the USAR? List USAR Sections reviewed: []NO Go to 9.7 l [ ] YES - list USAR Sections

Does the USAR description require any changes or revisions due to this activity?

[]NO - Continue with 9.7 [ ] YES -. 10 CFR 50.59 applies to this activity 1{ Section B of the Nuclear Safety Evaluation l 4 I must also be completed . C_ontinue with 9.7 A-3 i C/ FORMS jj

m ,v

i. ruyram e

\\ FORT CALHOUN STATION GENERAL FORM FC-154 R13 NUCLEAR SAFETY EVALVATION Reference N00.QP-3 ID No.LIC-92-207R SECTION A Page 1 of 0 (from 9.1) 10 CFR 50.59 Applicability Scresning ~ ) 9.7 Does tha activity involve tests or experiments? it l [X)NO Go to a.8 i, i. [ ] YES - Is the test / experiment one which has been previously anticipated in the USAR? [ ] YES list USAR Sections j f Go to 9.8 j []NO - (i.e., it is not described in the USAR; including one-of-a-kind tests or new system configurations) i Could this test / experiment degrade the margins of safety during normal operations or anticipated transients, or could it degrade the adequacy of structures, systems or components to prevent accidents or mitigate accident conditions 7 I f [ ] NO h 4 - Continue with 9.8 [-] YES - - 10 CFR 50.59 applies to this activity Section B cf the Nuclear Safety Evaluation I must also be completed. L Continue with 9.8 i i A-A ~ /FORfiS i i l l'

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ram FORT CALHOUN-STAT!ON FC-154 EfENERAL FORM R13 NUCLEAR SAFETY EVALUATION Reference N00-QP-3 10 No. LLC-92-207R SECTION A Page 6 of (from 9.1) ~ 10 CFR 50.59 Applicability Screening 9.8 Could the activity adversely. affect nuclear safety?- [X)NO Explain The activity concerned calls for retainino the_JW 4 solution of a 50/50 01ven1 water mix year around. The hich I temperature operability limit for DG-1 with a 50/50 civco1/ water mix is reduced _to___1_04*F. The hiah__ temperature operability limit for OG-2 with a 50/50 alveol / water mix is y 110'F and is the same as usino water as a coolant. These k operability lin,tj are substantiated by short (continued) Go to Nuclear Safety Evaluation Conclusion or continue with .Section B of the Nuclear Safety Evaluation, if required. ,i -[]-YES-How L

)

I i[ ip -Has this effect been previously evaluated in the USAR? [ ] YES - discussed in USAR Section Continue with Nuclear Safety Evaluation Cone'usion i []NO 10 CFR 50.59 applies to this activity 1-Continue with Section B of the Nuclear Safety 3 Evaluation i A-5 1 FC/ FORMS-L 6 d

' FORT-CALHOUN STATION GENERAL FORM FC-154 R13 NUCLEAR SAFETY EVALUATION Reference N00-QP-3 I FORM E

3 ATTACHMENT l_

Reference Sections 9_<B (Continued) i t?rm calculation FC05916 -The advantaces to usino the 50/50 olveol/ water mix durino the summer months are:

1. Reduce _s the 0_iesel Generator down time required for sorino and fall coolant __

chances.

2. Provides_ cons _ tant o_p_erabi_lity limits and reduces confusion over which coolant is used and what diesel operability 1Jmits are used.

3. Offert more orotection aaains_t__ unseasonable cold oeriods. A 50150 I

Olyco'/wa_ter mix offers freeze protection aoainst___co_ld ambient air k temoeratures_flowino throuch the radiatar with little or no.iacket water flow circula_tjno_throuch the radiator. -3t shou _id be neted that the OG operability limits are based on the enoine 2000 hour ratino and not the maximum load that could safelv be___ carried __bv that OG for a_ shorter _Derio_d of time. Since-temo_eratures in excess of 104*F are very rare in Nebraska and since these hich temoeratures tvoically occur for a short f Deriod of time in the afternoon, it is not anticipated _that hich temperatures ] will cause any olant shutdown. In the worst case scenario. if ambient 4 -temperatures exceed 104*F then OG-1 would be declared inocerabie_bec_au_se of f . Tech. Spec. 3.7 (1) c.iii and the olant would enter a 7 dav LCO. However__the 1 D_G would_still be__ capable of Derformir.o its safety function even at the hicher i temperatures un_.to (ano bevond)-Il0'F. Therefore this not considereo to be an [ activity which adverselv affec_ts_ nuclear safety. I d: I I + FC/ FORMS k

--mn wm u sa iro iu u wcac F.cs FORT CALHOUN STATION FC-154 GENr.RAL FORM R13 NUCLEAR SAFETY _ EVALUATION Reference NOD-QP-3 .y f3 ID No.LIC_-92-2_07R Page_/I of 3 (from 9.1) SECTIO _N_-B Unroviewed Safety Question Determination 10.1.1 Identify Plant Specific Design, Ooerating and Technical Docurnents Document Title ID__ Number Revi_sion Operatino Temp. Limits .F_CQ$_916 ._A For DG-1 and DG-2 Diesel Generator Uoper= EA-FC-90-062 2 Temo. Operatino Limits 10.1.2 Identify Applicable NRC Documents / Industry Standards E Title ID_ Number Revision EDG Max. Temp. Limits 92-095 (NRC) N/A ELAIC Techni_ cal Eval. TAC No.M77596 N/A c,' 10.1.3 Identify Related Drawings k Title ID Number Revision _N/A V; Y 10.2 List safety functions the affected structures or i components perform:The emercency dLe_sel cenerato_r provides a source of AC power in cas_e ottsite__ power _is lost. l List applicable accidenta for which these safety functions are required: Loss of_offsite oower or loss of voltace on a_ vital 4160 v Ac bus. 1{ i i ._A l B-1 I FC/ FORMS .1 ___-____________-_a

, c.evs., m w FORT CALHOUN STATION FC-lS4 GENERAL FORM. R13 NUCLEAR SAFETY EVALUATION -Reference-NOD-QP-3 9 iS

IOL: No, LIC-92-207R-Page d of 4 (from 9.1)

SECTION B Unreviewed Safety Question Determination 10.3 System Interactions Analy,ses Criteria ADolicable Critoria Ann 11 cable Firs-Protection ( ] Structural Impact ( ) Electrical Equipmene. Separation Criteria ( ) Qualifications ( ) Single Failure Criteria [ ] High Enargy Line Break -: Review. [ ] Possibility of Operator Error Saismic Interaction and ( ) ( Qualification [ ] Heavy Ocads [ ] Electrical-Systems Analysis-[X) Impact on HVAC ( ) Human Factors. Review. ( ) System / Component -Performance (X) LStcurity Review [ ] 1 -Environmental-h RadiologicaliRelease [ ] Installation of Temporary j Modifications ( ] ' Materials Compatibility ( ] Testing of Temporary . Containment Integrity ( ) Modifications ( ) Control-Room-Habitability ( ) Other ( } / Missile Protection ( ) I Discussion of Applicable Systems Interactions Analyses 1 I(Include Attachment Sheet as needed) See Attachment- )!.- B-? FC/ FORMS t

~ ,. _.. ~ c.~ [? 0 FORT CALHOUN STATION FC-IS4 GENERAL FORM R13 NGCLEAR SAFETI_ EVALUATION Reference NOD-QP-3 9 ,3 ~ ID No.LIC-92-207R Page I of D (from 9.1) ATTACHMENT SHEET \\ 10.3 System Interaction Analvsqp ,Electr.1 ca1 S_vstems_ Analysis i The__emercency diesel cenerators orovide__A_C__e.l_octrical cower to the alant vital buses in case of f site AC oower__Ls lost. The amount of-cowe_r availab,l_e from ea_ch__ encine needs to be creater than the minimum encineered safecuards___lo_ ads for that encine. In addition to this i oractical consideration there is a_T_echnical Specification that the .emercency load _s not__excoed_the 2000 hour _r_atine of the encine. (The 2000 hour ratino of the encine is__the_ amount of oower that_th_e encine can routinelv Droduce before a maintenance __ inspection should be B_ecause hiaher__amhient temoeratures can oroduce creater__ j -performed) encine wear, the encine vendor derAtes the encine at air __ temperatures creater than 90*F. This deratinc causes an " intersection" of the nmercency load and.the-2000___ hour ratino of the encine. While the_enninn is cacable of eroducine moro power than recuired. plant Technica1 Soecifications recu:8re tha_t_emercency loads be less than the ennine 2000. hour ratina. System / Component Performance

9 The-diesel-encines may be cooled _u'sino either a c1veol/ water mixture or water alone (with a rust inhibitori. Because civcol is hearinr and

' more viscous than' water it takea more power to cumo the alveol / water mixture throuch the cooline system. The oower recuired to cump the coolant is subtracted from the enaine oower available for dri_v_ine the cenerator when determinine the KW ratine of the systan. Durina orevious summers the alveol / mixture was_ replaced with water in order to_avoi_d _this "civcol oumoine cenalty". _ Now beca11sAof sionifi_ cant improvements V in overill-coolina performance __due to radiator cleanino, hiaher [ capacity radiator fans, improved fan tin _ clearance,etc.f it is no loncer considered to be necessary to chance to water durina the summer months. The 2000 hour ratina_will be above the maximum _emercency loAdina rec _uired_bv Tech. Soec. 3.7 up to 104*F for DG-1 and 110*F for QG-2. Sho_uld_ tempera _tures exceed 110*F_bo_th DG's would b_e_ considered inoperable and__a_nlant shutdown wou_ld_be-recuired. I A FC/ FORMS { Wl f

_,m._,., FORT CALHOUN STATION FC-lS4 GENERAL FORM R13 LQCLEAR__ SAFETY EVALUATION l Reference NOD-QP-3 fo ID No.LI_C-92-207R Page Y of 4 ) (from 9.1) SECTION B Unreviewed Safety Question Determination 10.4 Could the proposed activity increase the probability YES ( ) of occurrence of an accident previously evaluated in the USAR? NO (X) Explain: The activity only affects eculpment which operates to miticate [ an accident.___ The_ a ct_i_v_ity cannot increase the erobabili_tv of anvi accid _ent_. 10.5 could the proposed activity increase the consequences YES [ ] s of an accident previously evaluated in the USAR? NO [X) [ Explain: Accident consecuences will no_t__be__ chanced by the continuation of a clveol/ water mixture because_DG__ocoration___rema,iins unchanced. USAR 5%ble 6.4-1 shows how DG ratines chance with temperature. It must be noted that the USAR has not___ vet __boen updated to reflect (Contin _ued ) 10.6 Could the proposed activity increase the probability YES [ ] l of occurrence of a malfunction of equipment important to safoty previously evaluated in the USAR't NO (X) Explain: Ecuipment__ malfunction orobabiliti;ps are not increas_ed since this activity involves only a temperatur; ratina which af fects Techni_ cal Soecification 3.7 (1) c. i ii_. This recuires FCS to maintain emern_ency i . leads below the 2000__hr. encine ratinq-L 5 10.7 Could the proposed activity increase the consequences YES ( ] of a malfunction of equipment important to safety previously evaluated in the USAR? NO [X] Explain : As_ s_ta_t_ed_in 10. 6, this ac_tivity does not affect malfunctions l l of ecuipment. EA-FC-90-062 and Calculation __FC05915 document the abili_ty of the DG to operate nroperly with a gly _c_o_1/wa_ter_ mixt _ urn even at ( =-.temreratures uo to 110*F l I 5-3 ll FC/ FORMS J

., _..- m _ vx rw u a e FORT CALHOUN STATION FC-154 GENERAL FORM R13 NUCLEAR SAFETY EVALUATION Reference NOD-QP-3 o 4.) ID No. _LIC_ 2_0_7_ R Page + of * (from 9.1) ATTACHMENT SHEET 10.5 (Continued) Encinserina Analvaia_EA-EC-90_062_._.This analysis differentiates between DG enaine capacity based on whether_the encine coolant is water or a alveol / water mixture. Either coolant,is acceptab_1_o, ho_ wever the alveol /wa._ter_ mixture _ causes__a_nrea ar encine S,aoacity deratina. This_ _i_s__true whether the temperature is ho.t o.r_ cold, Because emercency,loadir on DG-1 is higher ___than___on DG_- 2, the temoerat_ure_gt which the emornoncv leadina exceeds the 2000 ho_ur_ ratino of__the encine is__ reduced to 104*F. This does not mean that the enaine will not carry the emere.ency loads, it - simolv means_tha_t_the f maintenance insoection interval should__be shortened to somethina less than 2000 hours.For more details refer to_EA-FC-.90 _062__Rev. 2). Eurthermore as shown on once 19 of Short T_orm__Calculati_on_F_C-05916 h Rev.A, the emercency loadine decreases af_ter_ _6_.0__ minu_tes_ _to__a level well belov the 2000 hour ratino of the encine. Thus from a safety standpoint th^ ras _is_no doubt _that the DG would be able__t_o__ carry the required load. The problem is simolv that Tech. Snec._3.7 (1) c.iii does not consider the effects of temoerature on encine ratina. It is concluded that_leavina the_clycol/ water mixture in__the.DG's is safe and does not increase the probabilities or the_consecuences of any accident. / b se 9 kq l L i lFC/ FORMS w

g, v;vv=s7snvngrr:Tlemti TO-LICB85ING P.'13 ~ ].* L . FORT CALHOUN STATION FC-154 GENERAL FORM R13 NUCL%R SAFETY _ EVALUATIOl{ Reference NOD-QP-3 et 43 ID No.LIC-92-207R Page O of * (from-9.1) SECTION B_ Unreviewod Safoty Question Determination -10.8 Could the proposed activity create the possibility of YES ( ) an accident of a different type than any previously evaluated in the USAR? NO (X) i Explain No different ace _ident__tvres are created by this activity. Instead a situation may oc_ cur where a Technical Snecification for loadino__of the diesel cenera_t_ ors _ is exceeded fo,r DG-1 at emeroency 104*F rather than_at_110*F. Technical spe_ci.fications allow the di_esels 8 to_.._be inocerable for un to 7 days (total both diesols) cer month. 10.9 Could the proposed activity create the possibility of YES ( ) a malfunction of equipment important to safety of a different: type than any previously evaluated in the NO (X) USAR? Explain:The oossibility that_the DG would malfunction _is__ dependent on l J leadinrt__and temoeraturo,.._Thta_ pos_aibility exists whethenthe k emercency DG coolant used-is water or civcol/ water mixture. T h i_s___e v a l u a t i o n i s succortqd_bv EA-F_C-90-062 and Calculati_on__?C05916. No new malfunction tvoes__are created. 10.10 Does the proposed activity reduce the margin of safety YES ( ) as defined in the basis for any Technical Specification? [ NO [X] Explain:No Technical Specification Basis discusses the tvne of coolant _ used in'the diesel c_enerators, nor is___there_any discussion of hich trmeerature operation of the_di_esel cenerators. Usino th_e 2000 ho_ur x2t_inc of the encine bul_1da_c_o_nservatism into the Tech._Snec. withou_t [ havino to censider temeeratu.rg.nf_fects. At some temoera_ turn, no_ matter L (Continued) _ _ _] B-4 i .FC/ FORMS L r

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, y g g,,g g, g d 3 ~ o FORT CALHOUN STATION GENERAL FORM FC-134 R13 ELCLEAR SAFETY EVALUAMON Reference NOD-QP-3 ID No.LIC-92-_207R (from 9.1) Page of ATTACHMENT SHElQ w 1_Q,LO (continuedi what coolant is_used, encine derating would cause a violation of Tech. Spec. 3.7 (1) c. ii_i. However the marAin of safety defined in the Tech. Spec. does not a_ddress temoeratttre ef fects. f ~ f. k 1. 5 I l ? \\ [ e r i l FC/ FORMS I a

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