ML17187A802

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Rev 1 to Minimum Available Ccsw Flow to Maintain 20 Psi Differential Between LPCI & Ccsw Hx
ML17187A802
Person / Time
Site: Dresden  
Issue date: 11/06/1996
From: Hawley J
COMMONWEALTH EDISON CO.
To:
Shared Package
ML17187A798 List:
References
DRE96-0214, DRE96-0214-R01, DRE96-214, DRE96-214-R1, NUDOCS 9702240127
Download: ML17187A802 (49)
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Text

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  • . DRE96-0214. MininilllJl Available *ccsw Flow to

. Maintain a 2o:psi.Differential Between LPCI and CCSW . Heat Ex~hanger? Rev l. '/ 9702240127 970217 D ~--P_o_R_A_o_o_c_K_o~so_o-'o-'2'-'-3'--7---' P PDR I

COMMONWEALTH EDISON COMPANY CALCULATION TITLE PAGE CALCULATION NO. DRE96-0214 PAGE NO.: 1 _x_ SAFETY RELATED REGULATORY RELATED NON-SAFETY RELATED CALCULATION TITLE: Minimum Available CCSW Flow to Maintain a 20 psi Differential Between LPCI and CCSW* in CCSW Heat Exchanger STATION/UNIT: Dresden.Unit 2&3 SYSTEM ABBREVIATION: 1500 EQUIPMENT NO.: (IF APPL.) PROJECT NO.: (IF APPL.) N I A 1501 REV: 0 STATUS: APPR QA SERIAL NO. OR CHRON NO. NI A PREPARED BY:~~/ JO.~es I. H~ll\\Jt~1 REVISION

SUMMARY

,Original Issue. ELECTRONIC CALCULATION DATA FILES REVISED: (Name ext/size/date/hour: min/verification method/remarks) l:\\transfer\\transfer. isi\\DR960214. wpf l:\\transfer\\transfer.isi\\DR960214.xls WordPerfect 5.1/5.2 Excel DATE: DATE:. 1_1/b /9fo

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DO ANY ASSUMPTIONS IN THIS CALCULATION REQUIRE LATER VERIFICATION? YES _2L_ NO REVIEWED BY: / __ _.. o ~ //vo //. G9 r'.:C-7 DATE: // (6/'7~ REVIEW METHOD: ~~~*led /l!<ev/e/A./ COMMENTS (C, NC OR Cl):N c. APPROVED BY: \\.;/;/!,;{ {.( (/;/~ DATE: it Ii 2. )Cf {J 'c._ * . ~, '.. - -... ' t ** ~ ..,:_~ ; -./

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COMMONWEALTH EDISON COMPANY CALCULATION REVISION PAGE CALCULATION NO. DRE96-0214 PAGE NO.: 2 REV: 1 STATUS: QA SERIAL NO. OR CHRON NO. DATE: I PREPARED BY: &?/C..,, ( ~ ~) \\. /Christonher M. Kinstler DA TE: 2/5/97 REVISION

SUMMARY

1.
2.
3.
4.
5.
6.
7.
8.
9.
10.
11..
12.
13.
14.
15.
16.
17.

Pg. 8, Eliminated unverified assumption #1 by incoi-poration of Ref. to GE calculation GE-NE-T2300740-1. Pg. 9, Design Input #2, Revised LPCI pump discharge pressure to 164 psid in accordance with maximum IST reference value. This is conservative in that It reduces CCSW flow. Pg. 9, Design Input #8, Revised elevation of ~ter surface in intake bay to 500 ft per R.ef. 6. Pg. 9, Design Input #11, Added note. Pg. 11, Revised Reference #6. Pg. 11, Revised Reference #8. Pg. 12, Revised calculation table to incorporate revised discharge pressure (164 psid), and elevation of water surface in intake bay (500 ft): "Pg. 13, Revised calculation table to incorporate revised discharge pressure (164 psid), and elevation of water surface in intake bay (500 ft). Pg. 13, Revised calculation table to incorporate analysis at ~000 gpm CCSW flow.

  • Pg. 13, Added expliination regarding the sooo* gpm flow calculation under table on.

Pg. 14, Revised' calculation table to incorporate revised discharge pressure (164 psid),.and elevation of water surface in intake bay (500 ft). Pg. 15, Revised calculation table to incorporate revised discharge pressure (164 psid), and elevation of water surface in intake bay (500 ft): ' Pg. 16, summary point # 1. Added text to. Pg. 16, Summary point #2, Revised Torus Overpressure table.. to incorporate revised calculation results and added note. Pg. 16, Conclusion #1, Revised flow.rate. Pp. 2-17 to revision 1, no other changes. Pg. 3, Table of Contents revised to include page 17. ELECTRONIC CALCULATION DATA FILES REVISED:* (Name exVsize/date/hour: min/verification method/remarks) l:\\transfer\\transfer.isi\\DR960214.doc MS-Word 6.0c l:\\transfer\\transfer.isi\\DR960214.xls.* .Excel DO ANY ASSUMPTIONS IN THIS CALCULATION REQUIRE LATER VERIFICATION?.YES_ NOX. REVIEWED BY: DATE: ~l** s*. '.17 COMMENTS (C, NC OR Cl):,.*./ G APPROVED BY: DATE: -Z.u-r)

  • ExhibitC

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COMMONWEALTH EDISON COMPANY CALCULATION TABLE OF CONTENTS PROJECT NO. NIA CALCULATION NO. DRE96-0214 REV. NO. 1 DESCRIPTION PAGE NO. TITLE PAGE 1 REVISION

SUMMARY

2 TABLE OF CONTENTS 3 PURPOSE/OBJECTIVE

4.

METHODOLOGY AND ACCEPTANCE CRITERIA 4-7 ASSUMPTIONS 8 DESIGN INPUTS 9-10 REFERENCES 11 CALCULATIONS 12-15

SUMMARY

AND CONCLUSIONS ATTACHMENTS -4& 17 A. Background Information A1-A32 c ~ ' ~... - ~ PAGE NO. 3 SUB-PAGE NO.

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COMMONWEALTH EDISON COMPANY CALCULATION NO. DRE96-0214 PROJECT NO. PAGE NO. 4 REVISION NO. I 1 I PURPOSE/OBJECTIVE: Calculation Type: M03 Initiating Document: Affected System/Structure: Operability Screening 96-38 ccsw Safety*Classification: Safety-Related T.he purpose of this calculation is to determine the minimum available CCSW flow while maintaining a 20 psi differential pressure between the LPCI and CCSW sides of the CCSW heat exchanger:. METHODOLOGY AND ACCEPTANCE CRITERIA: Methodology The minimum CCSW flow that is capable of maintaining a 20 psi differential pressure above LPCI

  • pressure within the CCSW heat exchanger is determined by the following steps.
1. Determine the pressure at the exit of the LPCI side of the CCSW heat exchanger. The governing
  • . equat.ion*is:
  • _PLPC1.Hx = Poev.LPC1 -.APFR1C.LPCI
  • pg(H~HroRus) +Pop
2.

Determi.ne the pressure at the exit of the CCSW side of the CCSW heat exchanger. *The governing equation is: ~ Pccsw.HX = Poev.cc5w - APFR1c.ccsw - pg(H~H1NTAKE~BAv)

3..Determine the pressure difference at the exit of the CCSW heat exchanger by subtracting Eq. 1 from Eq. 2, to obtain:

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~ COMMONWEAL TH EDISON COMPANY CALCULATION NO. DRE96-0214 PROJECT NO. PAGE NO. 5 REVISION NO

  • I 1

I Pccsw.HX - PLPC1.HX = (Poev.ccsw - Poev.LPC1) - (t.PFR1c.ccsw - t.PFRIC,LPC1) + pg(H1NTAKE_BAv - HroRus) - Pop The input values required to evaluate*Eq. 3 are obtained as follows. The head-flow characteristics of the LPCI and CCSW pumps are available from Ref. 1. The total LPCI friction pressure loss to reach the CCSW heat exchanger exit is the sum of the friction losses for the individual piping segments and the heat exchanger, as shown in Eq. 4:

4.

~ProTAL =.I:t.Ppipe + t.PHX. The LPCI piping segment frictional losses are available from Ref. 2 for specific assumed flow rates. Values are provided for a LPCI pump's suction and discharge piping segments, as well as the common * <;1ischarge piping to the CCSW heat exchanger. These losses are then scaled to the value corresponding to the desired flow rate of 5000 gpm by the square of the ratio of the flows, -as shown - -below: T_he LPCI frictional loss through the CCSW heat exchanger is available from Ref. 3 for specific assumed.flow rates. This loss is also scaled to the value corresponding to the desired flow rate of 5000 gpm by using Eq: 5.

  • The CCSW system pressure at the CCSW heat exchanger exit was obtained from a recent test that is documented in Ref. 4. This data, in conjunction with the CCSW pump head-flow characteristics from Ref. 1 allows the total CCSW frictional pressure loss to reach_ the CCSW heat exchanger exit at the tested flow rate to be determined from Eq. 2, above.

_Since the left-hand side of Eq. 3 is defined as the 20 psid requirement for the *ccsw heat exchanger, the preceding develo-pment leaves Eq. *3 with two unknowns, Poev.ccsw. and t.PFR1c.ccsw. which both .depend on the assumed CCSW pump flow rate, and the parameter Po~. which depends on the assumed sequence (e.g., DB~ LOCA). De-noting Pccsw.Hx - PLPC1.Hx as t.PHX, Eq. 3 may be rearranged as follows:*

6.

Poev.ccsw = t.P~ + Poev.LPC1 + t.PFR1c:ccsw - t.PFR1c.LPc1*- pQH1NTAKE_BAv +.pgHroRus +Pop _-

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  • I 1

I The first case addressed by the calculation is solving Eq. 6 for the OBA LOCA. For this case, the torus overpressure is specified and the CCSW pump flow rate required to maintain a 20 psi differential between the CCSW and LPCI sides of the CCSW heat exchanger is found by iterating as follows:

7.

In Eq. 6, insert.the elevations for the intake bay and torus water levels, assign a value of 20 to aPHX, assume Pop has the value for the OBA LOCA, assign ttie value of aPFRic.LPCi determined for 5000 gpm, and assign the value of 6Poev.LPCi correspondi.ng to 5000 gpm from the LPCI pump curve.

8.

Guess a value for CCSW pump flow;

9.

Scale the CCSW frictional pressure loss determined from the system test and Eq. 2 to the value corr,espo.nding to the guessed flow rate by using Eq. 5;

10. Determine the CCSW pump developed head predicted by Eq. *3;
11. Look-up the CCSW developed head from the pump curve;
12. *Compare the results obtained i~ Steps *~ O and 11;

~...

13. Repeat steps 7-through 12 until the resuJts show reasonable *agreement.

The second case addressed by the calculation is for a varying torus overpressure, to assure that any concerns related to Small and Intermediate sized breaks are covered. In this ~ase, although the torus ov.erpressure could be specified, the iteration above is avoided by assuming a value for throttled CCSW pump flow and determining the value of torus overpressure which maintains the 20 psi differential between the CCSW and LPCI sides of the CCSW heat exchanger, as follows:

14. In Eq. 6, insert the elevations for the intake bay and torus water levels, assign a value of 20 to

... aPHX. a throttled flow rate for the CCSW pump, assign the value of 6PFR1c.LPC1 determined for 5000 gpm; and assign the value 0L::~Poev.LPC1 corresponding.to 5000 gpm from the LPCI pump curve; '.~ ~--:~r:-:- *: ;! ;": _........ *: 1J..,i

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COMMONWEALTH EDISON COMPANY CALCULATION NO. DRE96-0214 PROJECT NO. PAGE NO. 7 REVISION NO

  • I 1

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15. Scale the CCSW frictional pressure loss determined from the system test and Eq. 2 to the value corresponding to the guessed flow rate by using Eq. 5;
16. Look-up the CCSW developed head from the pump curve;
17. Determine the torus overpressure predicted by Eq. 3.

"Exhibit E NEP-12-02 . _ Revisiori 3

COMMONWEALTH EDISON COMPANY CALCULATION NO. DRE96-P214 PROJECT NO. PAGE NO.' 8 REVISION NO

  • I 1

I ASSUMPTIONS:

1.

QesigR IRput #11 requires verif:isatieR eRse the DRAFT eele1:1letieA is #iAelized and sular;iiUea te Gem Ea. Assumption verified in Rev. 1, see Design Input #11.

2.

OBA is the worst case.because of the need to initiate CCSW cooling mode in 1 O minutes to . maintain suppression pool temperature limits.

3.

Maximum containment overpressure (at greater than 1 O minutes after accident initiation) is 17 psig (based on current GE OBA analysis).

4.
  • At 1 O minutes operators will throttle LPCI to 5000 gpm. (one pump) and throttle CCSW to
maintain specified differential pressure (20 psid) per procedure. The suppression pool cooling limiting case is loss of offsite power and one diesel generator. Diesel capacity limits require one LPCI pump in each train to be stopped before starting CCSW.
5.

One LPCI pump is operating. This is the limiting case for LPCI pressure in the.heat exchanger since the pumps will be throttled to 5000 gpm each in a two pump case. Si.nee the throttle va.lve is downstream of the heat exchanger and the pressure drop will increase in the common downstream piping with two pumps operating, the LPCI pressure in the heat exchanger will be . less with two pumps operating. . 6. The appropriate location to impose the required pressure differential between LPCI and CCSW in the CCSW heat exchanger is assumed to be at the CCSW flow exit point. Jn other words, . the heat exchanger*is assumed to be arranged such that the lowest LPCI: pressure occurs at - the same spot Detailed scrutiny of the CCSW heat exchanger.internal arrangement was not performed for this calculation. However, the 20 psid requirement assures.that the worst-case. situation (i.e., highest LP.Cl pressure near lowest CCSW pressure) will still cause leakage flow. into the LPCI system. ~ * .. ~::::-~_~; < ~ ::*~~ -~. ~.~ ._;...,:..1: ~ : -

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COMMONWEALTH EDISON COMPANY CALCULATION NO. DRE96-0214 PROJECT NO. PAGE NO. 9 REVISION NO

  • I 1

I DESIGN INPUTS: ~*.... > *..,

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1. Throttled LPCI pump target flow of 5000 gpm, Ref. 9.
2.

bPCI J:nn.llp !:lea~ 1lgw G1uve, Ref, 1. At a tai:got flgw gf 5000 gpm,.tl:lis m.irve sl:lgws a bPCI ' pu1+1p de"eloped l:lead of 156 piid, Revision 1 of the calculation utilizes 164 psid from the IST program reference value to provide a conservative result, Ref. 13. . 3.. LPCI pump suction piping pressure drop of 3.44 feet at 5000 gpm, Ref. 2.

4.

LPCI pump discharge piping (upstream of common piping) pressure drop of 2. 7 psid at 4320 . gpm, Ref. 2. . 5. LPCI pump common discharge piping pressure drop of 0.13 psid at 5000 gpm based on resistance due to through-flow tee eler:nent (17.124" ID for both sides of tee so UD =.20) and .gate valve (UD = 13); Ref. 10.

  • :6. LPCl-side pressure prop.across heat exchanger of 15 psid at 10700 gpm, Ref. 3.
7.

Target pressure difference between LPCI and CCSW in the CCSW heat exchang*er of 20 psid, Ref. 9.

8.

El~vation of ~~ter s~rface in intake bay was taken at the operating low water level of 501 ft 500 ft, Ref. 6.. ,9. Elevation of water surface. in torus taken at high water level limit of 494'.-1 OYz", Ref. 7. . 10. Estimate of el~vation of cc.sw outlet of heat exchanger as 507.333', Refs. 11, 12.

11. Containment overpressure.of 17 psig is rounded-up value at 600 sec. after initiation of OBA for second Case 1a in. Table 2, Ref. 8.. (Note 16:5 was used in the actual calculation) r...
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  • PROJECT NO.

PAGE NO. 10 REVISION NO

  • I 1

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  • 12. CCSW system pressure of 140 psig measured at heat exchanger exit for a CCSW system flow of 7000 gpm obtained during CCSW system flow test, Ref. 4.
13. CCSW pump developed head at various flow rates obtained by reducing nominal developed head values froro pump curve in Ref. 1 by 15 psig based on lowest surveillance test result for developed head at 7000 gpm (i.e., assume constant pump degradation of about 15 psid):

Flow (gpm) Nominal Dev. head (psig) Degraded Dev. Head (psig) 7000 gpm 205 190 6000 gpm 225 210 5600 gpm 230 215 .5500 gpm 231 216 5400gpm. 232 217 5200 gpm 235 220 5000 gpm* 238 223 4000 gpm

    • 250 235
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\\ COMMONWEALTH EDISON COMPANY CALCULATION NO. DRE96-0214 PROJECT NO. PAGE NO. 11 REVISION NO. I 1 I

REFERENCES:

1. ComEd Calculation No. DRE96-0211, Rev. 0, Dated 1996.
2.

UFSAR Paragraph 9.2-4.

3.

Berlin-Chapman, Inc., Heat Exchanger Data Specification Sheet for Containment Exchanger, Dated 3/29/67.

4.

Datasheets from DOS 1500-12 conducted 8/15/96 to obtain a CCSW flow of 7000 gpm through the CCSW heat exchanger; 140 psig is a lower bound of measured heat exchanger 'exit pressure. 5: ComEd Calculation No. NED-M-MSD-54.

  • 6.

Di:awiRQ M 10

  • Dresden TSUP section 3/4.8:C.1.
7. *Drawing M-7
  • 8.. Draft Meme fFem S. MiRit (GE 5aR Jose) to ' ~lasll (GE-D~esden), Dated 11i4t96, re* Review ef NRG IAfeFFRBtieA Netiee 96 55, Jel:lle 2 freFR AtteohFReAt. GE calculation GE-NE-T230074-1, dated Dec. 1996.
9.

DOP 1500-2..

10. Drawing M-29, sheet 1.
11. Perfex Corp. Drawing K-5009-1&2, sheet 1, Rev. 4.
12. Sargent and Lundy Inc. Drawing 8-282.

,. ~,.~.. * .. :.:13. *auarterly LPCI Pump>>Test Data Ranges & Required Actions, Table 48, Unit 3 dated 12-22-95..

COMMONWEALTH EDISON COMPANY CALCULATION NO. DRE96-0214 REVISION NO

  • I 1

CALCULATIONS: PoeV.LPCI 6PHx 6Psuction 6Pind_ disch 6Peommon_ disch ~ 1- :'. ...... ~._: 6Phx,LPCI 6Ptnc.LPCI HNTAKE_BAY HroRus

  • HHx PoP Pccsw.HX Poev.ccsw 6Ptnc.ccsw Exhibit E

. NEP-12-02 RIMsion 3 .. ~.-* ~ -.

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Raw Value

...+66-164 20 3.44 2.7 0.13 15 NIA

-594-500 494.875 507.333 17 140 190

  • ~46.8

-~- Units psid psid feet psid psid psid psid

  • feet feet feet psi.

. psig psig psid PROJECT NO. PAGE NO. 12 I DRE96;..0214 - Case 1 Design Input Corresponding Flow Value Scaled Value Input

  1. or Equation Value for Raw fo 5000 gpm to Eq. 6 Value (psi)

Solution 2 5000 -+56-164 -4"'-164 7 NIA NIA 20 3 5000 1.5 NIA 4 4320 3.6 NIA 5 5000 0.1 NIA 6 10700 . 3.3. NIA Eq.4 NIA 8.5 8 NIA NIA .ff1:+216.6 9 NIA NIA 214.4 10 NIA NIA NIA 11 ---NIA NIA 16.5 12 7000

  • NIA
  • NIA 13 7000 NIA NIA Eq.2 7000 NIA NIA
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COMMONWEAL TH EDISON COMPANY CALCULATION NO. DRE96-0214 PROJECT NO. PAGE NO. 13 REVISION NO

  • I 1

I CALCULATIONS: DRE96-0214 - Case 1 Raw Value Units Design Input Corresponding Flow Value Scaled Value Input

  1. or Equation Value for Raw to 5000 gpm to Eq. 6 Value (psi)

Solution Iteration Occsw 6000 gpm Guess 1 APmc.ccsw.:: - 34.4 psid Eq. 5

  • Poev.ccsw -

224.2 psid Eq.6 Poev.ccsw 210 psid 13 A~14.2 psid Occsw

:400 gpm Guess 2 ANSWER APmc.ccsw

~27.9 psid

  • Eq.5 Poev.ccsw

~217.6 psid Eq.6 Poev.ccsw

~~.~ 217.0 psid

. '13 A =4:8--0.6 psid,-eK-Occsw 5000 gpm Guess 2 ANSWER APlric.CCSW -23.9

  • psid Eq.5 Poev.ccsw 213.7 psid Eq.6 Poev.ccsw

.223.0. psid 13

  • A= 9.3 psid A flow rate of 5000 gpm for CCSW ~ill maintain *a AP 20_ psig with an allowance of 4% degradation of pump performance fromthe:current minimum IST reference values:

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COMMONWEALTH EDISON COMPANY ~ =** *:::*-: CALCULATION NO. DRE96-0214 REVISION NO

  • I 1

CALCULATIONS: Design Input or Calculated Quantity Poev.LPCr 6PHX 6Psuction APind_ disch 6Pcommon_ disch 6Phx.LPCI 6Plric.LPCI HrNTAKE_BAY HroRus HHX Pccsw.HX Poev.ccsW 6Pmc.CCSW -

  • Elchibit E NEP-12-02 Revision 3 Raw Value

-466-164 20 3.44 2.7 0.13 15 NIA -59+500 494.875 507.333 140' 190 ~46.8 PROJECT NO. I DRE96-0214 - Case 2 Units Design Input# or Equation #

  • psid 2

psid 7 feet 3 psid 4 psid 5 psid 6 psid Eq.4 feet 8 feet 9 feet 10 psig 12 psig 13 psid Eq.2 PAGE NO. 14 Corresponding Value Scaled Value Input Flow Value for to 5000 gpm to Eq. 6 Raw Value

  • (psi)

Solution 5000 -'t-56-164 -+&&-164 NIA NIA 20 5000 1.5 NIA 4320 3.6 NIA 5000 0.1 NIA 10700 3.3 NIA NIA 8.5 NIA NIA =* :-. : 216.6 NIA NIA 214.4 NIA NIA NIA 7000 NIA NIA 7000 NIA NIA 7000 NIA NIA

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COMMONWEALTH EDISON COMPANY CALCULATION NO. DRE96-0214 PROJECT NO. PAGE NO. 15 REVISION NO. I 1 I CALCULATIONS: DRE96-0214 - Case 2 Design Input or Raw Value Units Design Input # Corresponding Value Scaled Value Input Calculated or Equation # Flow Value for

  • to 5000 gpm to Eq. 6 Quantity Raw Value (psi)

Solution SENSITIVITY Occsw 4000 gpm Case 1 APlric.CCSW 15.l psid Eq.5 Poev.ccsw 235 psig 13 POP ~ psig. Eq. 6. ANSWER 46.4 Occsw 5000 gpm Case 2 APlric.CCSW 23.9 psid . Eq. 5 Poev.ccsw 223 psig 13 PoP -34:4-psig Eq.6 ANSWER 25.8 Occsw .5200 gpm Case 3 APlric.CCSW 25.8 psid Eq.5 Poev.ccsw 220 psig 13 PoP -e9:+ psig Eq.6 ANSWER 20.9 I Qccsw

  • 5400 gpm Case 4 APlric*.ccsw

-27.9. psid Eq.*5 Poev.ccsw

217 psig 13 PoP

-.-z.4-psig Eq. 6

  • ANSWER l

15.9. Occsw 5600 gpm Case 5 APlric.CCSW 30.0 psid Eq.5 Poev.ccsw 215 psig 13 PoP ~9.9 psig Eq.6 ANSWER 11.8 I '*~.* ' ',**~~~ -~~... =:::: .'t-".... -:.'r. ~ :.- : :* .. *(. -- '~

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COMMONWEALTH EDISON COMPANY CALCULATION NO. DRE96-0214 PROJECT NO. PAGE NO. 16 REVISION NO. I 1 I

SUMMARY

AND CONCLUSIONS: Summary

1. For the OBA case (i.e., torus overpressure set equal to 17 psig), using a CCSW pump curve degraded by 15 psid (based on surveillance test data) results in a CCSW pump flow of 5800 5400 gpm required to maintain 20 psid between the LPCI and CCSW in the CCSW heat exchanger.

A CCSW pump flow of 5000 gpm provides an additional 4% rnargin for future IST surveillance.

2.
  • The throttled flow rate required to mairitain 20 psid between the LPCI and CCSW in the CCSW heat exchanger varies depending on the torus overpressure, as follows:

Torus Overpressure (psig) ~46.4 ...a4.4-25.8 ~20.9 ~15.9 ~11.8 Throttled CCSW Flow to Maintain 20 psid (gpm) 4000 5000 5200 5400 5600 (Note: These numbers are based on current degraded pump values shown in design input 13. The allowan~e for.an additional 4% degradation would reduce the torus pressures shown above by 9.4 psig {235 x.04)) Conclusions

1. An evaluation should be performed to determine the CCSW water temperatu_re required to maintain sup*pression pool temperature below design requirements with an assumed CCSW flow

. rate of.Seee-5000 gpm:

2. A sensitivity evaluation should be performed to determine the CCSW water temperature required
  • to maintain suppression pool temperature below design requirements with an assumed CCSW flow rate of 5600 gpm.
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3.

Due to Assumption 6, this calculation should not be used to justify reducing the 20 psid requirement between the LPCI and CCSW systems within the CCSW heat exchanger. .\\**

f ~ *~--: . \\ -* CATEGORY 1 REQUIREMENTS: f<4, q / s1.~ k.}...,.+ 11611 f 1>LJ

  • 1~,. # J TORUS WATER COOLING MODE OF LOW PRESSURE COOLANT INJECTION SYSTEM UNIT 2(3)

DOP 1500-02 REVISION 26 NONE. Dllt ~' - O?... I '-1 Al () i:: _A~L TECHNICAL REVIEW AND CONTROL Disciplines Required: NPPT RO [X) [X) Unit 1 Review Required: Special Reviews: DEOP. ( x] RE/QNE CH RS ( J (. J ( ] ( YES (X] NO ON-SITE REVIEW.AND INVESTIGATIVE FUNCTION (OnSR&IF): .OnSR&IF REQUIRED [ ]**YES (X] NO .Required Review

Participants:

NONE. I&C [ J M&ES (X) APP~OVAL AUTHORITY:,' .. Shift Operations *Supervisor (SOS), or deaiqnee POST PERl'ORHANCE REVIEWS: ....... -=.

~ ' ""

NONB. ..~ - I l of 22 ~l~:: u ~~~'.~:.. ~ EFFECTIVE DATE -i I. I:

~ - ~-*:,r* _*" *-5. ~-. CATEGORY 1 UNIT 2(3) OOP 1500-02 REVISION.26 D12.E 'it -c 1-- I ii-* Al-of A@;3v l!.Qll I I 2(3)A AHJ2 D CCSW Pumps are preferred for two pump operation to minimize ccsw Pump Vault Cooler run time. I I I I

c.
2.
a.

start 2(3)A QB B ecsw Pump~ verify MO 2(3)-l50l-3A, HX DISCH VLV, opens (dual indication). I I.J

b.

Adjust DPIC 2(3)-1540-JA, 2(3)A LPCI HX DP COHTLR, to obtain desired ccsw flow (approximately 3500 gpm).

c.

Start 2(3)D QB.C CCSW Pump Alm. verify HO 2(3)-1501-38, BX DISCH VLV, opens (dual indication).

d.

Adjust DPIC 2(3)-1540-38, 2(3)8 LPCI HX DP COHTLR, to obtain desired CCSW flow (approximately 3500 gpm).

e.

Verify 2(3)-i50l-l3A, MIN P'LOW VLV is open.

f.

Verify 2(3)-l50l-38A, TORUS CLG/TEST is closed 9* Open MO 2(3)-l50l-20A, TORUS CLG/TEST.

h.

Start 2 (3 ) A OR B LPCI Pump; 1

  • I
  • I fil2n I

I I I The flow rate *through each LPCI Pump should be maintained below 5000 I I I gpm to prevent a pump runout condition. I I .1 I "'---~------~------;.._----------------------------------------*----------------.J Throttle open KO 2(3)-150l-38A, TORUS CI,.G/TEST, as necessary .ImI.Ut LPCI flow rate is approximately 5000 gpm as indicated on FI 2(3)-l561A, 2(3)A LPCI FLOW.

j.

Verify 2(3);..1501-i3A, KIN P'LOW VLV, clos~s~ . k. Close KO 2(3)-1501-llA,* BX BYPASS VLV.

  • Du. I""f'. '7

_.-:---------~---------------------~--=---- Adjust DPIC 2(3)-1540-3A, 2(3)A LPCI HX DP COHTLR, as necessary to maintain the differential pressure at or 20 paid * . m.

  • Ver.ify 2(3)-1501-*138, KIN FLOW VLV, is open.
n.

Verify 2(3)-1501-388, TORUS CLG/TEST, is closed.

o.

Open KO 2(3)-l50l-20B, TORUS CLG/TEST.

p. **

Sta~.. 2 (3) C OR D LPCI Pump. 8 of 22 ~.***.'."\\ -~*-.

  • .'.*r

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    • "l,

. ~ ~- *. :. ',

  • .,,.. :if.

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ATIACHMENT H, FIGURE 1 Unit 2, Composite of LPCI P!.!mps 2A, 28, 2C, 20 Pump Curves, One, Two, and Three Pump Operation c::::> = '350 ~ t F.',. I '/)Cf.' I,.:, P.. tt L ~ -

  • -* *--* -- ~ - -

250 200 150 100 50 0 0 2000 4000 6000 8000 10000 Flow(GPM) 12000 n ___,._,,. 14000 16000 18000 E

~

t:

MOV Test Data -1 Pump Operation -2 Pump Operation 3 ~~f!IP Ope~~!~~. ~ C7 vJ ~ 0 ...u 1' ti'- 20000

i:..

0 t -C. vl I"

' QE*Sl.D..

  • *.... EXHIBITB.

',:.*.:: REV:.3 -... COMMONWEALTH EDI SON COMP ANY .D f2.E c:u, -o 1..1 'f TITLE PAGE A-~ o~ AtfJf13'l-P._ e. ** l.. p~ '... f" " fl: ~ CALCULATION NO. NED-M-MSD-S* PAGE 1 OF 17 _2L SAFETY RELATED NON-SAFETY RELATED CALCYLATION TITLE Dresden Post-LOCA LPCZ/Core Spray Pumps NPSH Eva1uation 'EQUIP NUMBER ( S} STATION/UNIT SYSTEM 2 (3} - 1502A/B/C/D Dresden 2 & 3 LPCI/Core Spray 2(3) - 1401A/B REV. CHRON # PREPARER DATE REVIEWER DATE APPROVER 0 ~

  • o/~,43

'4- ~ DATE ,,... ~ .. ~ I I )

COMMONWEALTH EDISON COMPANY TABLE OF CONTENTS CALCULATION NO: NED-H-MSD-54 I REV 0 SECTIONS DESCRIPTION 1 TITLE PAGE 2 TABLE OF CONTENTS 3 REVISION

SUMMARY

4 CALCULATION SHEET(S) s REVIEW CHECKLIST Atta_chments APPENDIX A ~

  • -* ~-

.. -~...:.. / . '. ~........ ":'

  • ~**
- w. -

-~* D itE'l~ -o~l 'f A~ or Afi1"3'2-I PAGE 2 OF 17 PAGES 1 2 3 4-l.6 17 A.1-A..

CALCULATION PAGES REV.* N/A 0 NO: COMMONWEALTH EDISON COMPANY .REVISION

SUMMARY

NED-M-MSD-54 I REV 0 DESCRIPTION OF REVISIONS/REASON FOR Original calculation AFFECTED PAGES DESCRIPTION. . original calculation I PAGE CHANGE D12£9G -ot.t~ A-~ ~F ~3Z.... 3 OF 17 ..,,.. *, ~**... I - 1

Calculation No. HED-M-MSD-54 Rev. o Dresden Post-LOCA LPCI/Core Spray PUmps HPSH Evaluation 012£ '\\~ -o 1-1'-f Purpose/Objective: A-1 uF" AJ83L-Calculate the Net Positive Suction Head Available (NPSHA) for the LPCI and Core Spray pwnps at Dresden Station under post-accident conditions as outlined in Reference 2, and compare with NPSH required (NPSHR) to ensure pump protection. Also, develop a system resistance to deterJU.ne the maximum attainable LPCI flow for one and two operation in the drywall spray mode. These flows will also be analyzed for adequate NPSH marqin. Assmnpticns/Xnputs: The NPSHA is calculated for each of the cases analyzed in

  • Reference 2.

Inputs were taken from Table 5 of Reference 2 and are summarized in Table 1 below: LPCI/ Total Total Maximum Pressure ccsw LPCI Flow CCSW Flow Pool at Max Case Pumps . (gpm) (gpm) Temp (F) Temp (psia)* R0-1 2/2 10000 5600 169 19.5 R0-2 2/2 11620 4795 170 19.8 R0-3 2/2 '10370 4795 170 19.8 'R0~4* 1/1 5000 3500 180 20.6 . R0-5 1/1 , 5300 3071 182 21.1 R0-6 1/1 5920 3071 181 21.0 R0-7 2/1 11620 3071 178

  • 21.1
  • R0-8 1/1 6020 3071 181 21.0 Table 1 In addition to the assumptions made in Reference 2, the following assumptions are also made in this calculation:

':

  • l) *Assumed even flow split between pumps operating in*

parallel and frictional.losses to each pump similar. '~ : i

  • f.) Suction piping losses determined at 90 deg F, 5000 gpm

.(one pump) and 10000 gpm (two pumps).

    • 3.) *unplugged strainer loss is l ft @ 10000 gpm (Ref. 14).

Assumed all four ( 4) strainers

  • 50% plugged and flow out of torus evenly distributed through all four strainers.
4) Entrance and strainer (unplugged) losses assumed to be 0.8 ft @ 5750 gpm,.2.47.ft @ 11620 gpm per Reference 11 *.
5) NPSHR values (Table 2) are developed based on the NPSHR curves *for the LPCI and Core Spray pumps (References 5 and 6) *. NPSHR not corrected for.higher temperatures.
6) Minimum torus.level elevation with maximum drawdown of
.2.1 ft. is 491 1 5" or 491 *. 42' (Reference 3).

Assumed .., ~.. recovery of l. 'l ft. for a drawdown of l* ft. (torus level !~~~:'.*~k;y.>

~~;~:I~~ ~ ~;ts~~) at time~;; ~;~;~~;G;;ljp~;~~;;ed and

'.:Itr~~~~}j;~f L~~*::.,,~,*: ..,, - ** *' * ~ J

':- -~.,_ >*~:*."':. *-.. Calculation No. NED-M-MSD-5~ Rev. O Dresden Post-LOCA LPC~/Core Spray PWnps NPSH Evaluation 01U-~'10U'/- At °F A93'-

7) Assumed roughness factor, e, for clean commercial steel pipe (e =

0.00015)~

8) Assumed turbulent flow through fittings.
9) Core Spray and LPCI pump suction losses similar.
Also, Unit 3 LPCI/Core Spray suction losses assumed similar.
10) Core Spray case bounded by LPCI case due to similar suction losses, NPSHR curves and pump centerline elevations; Core Spray runs at a lower flow than LPCI, therefore operating at a lower NPSHR condition than LPCI.

11). Assumed all gate valves to be fully open.

12) Strainers on lines 2-l502A(B)-14" and 2-l507A(B)-14" (Reference 16) upstream of each LPCI pump were installed for initial*plant start-up and have been removed per telephone conversation with s. Eldridge, ENC Dresden *

. 13) Dischar9e into containment will occur through the lower spray ring header located at elevation 527.l'. References*: l) "Flow of Fluids Through*valves, Fittin9s, and* Pipe",* Crane Technical Paper No. 410, 24th Printing, 1988.

2) "Sensitivity Analysis of Post-LOCA Containment Heatup at Dresden Station," Nuclear Fuel Services Document Number RSA-D-93-03, dated April 30, 1993.
3) S. Eldrid9e letter to c *. Schroeder titled '~Submergence of LPCI Discharge Line Post LOCA Dresden Units 2 and 3" dated September *29,.1992, chron# 0115532.

.4).nD:i:esden LPCI/Containment Cooling System~" GE Nuclear

  • . Energy letter from S. Mintz to T. L. Chapman dated

.~January* 25,.1993 *.

5). Bingham Pwnp curve No. 25355 for 12Xl4Xl4.5 CVDS, Dresden Station LPCI _Pwnp.
6) Bingham *Pump curve No.* 25231 for 12Xl6Xl4:.5 CVDS, Dresden Statio:p Core Spray Pump.
7). Sargent & *Lundy drawing M-547, LPCI pump suction *
8) Sargent & Lundy drawing M-549, Core spray pump suction.
9) "Cameron Hydraulic Data," Ingersoll-Rand co., 16th Edition, 2nd Printing, 1984 *

. 10) *"Dresden LPCI/Containment Cooling System, " GE Nuclear. Energy letter from s. Mintz to T. L. Chapma:p dated . _.January 27,

  • 1993.

~-.... 1_:_... ". . -~.. \\ . -...,..-: '. '.-: *:..,. <~-~ --.

. *-.~ - .. *... ~-.£ ~ "',_- ~. :. -*-... ~ ~. t"// l calculation No. NED-M-MSD-54. Rev. o Dresden Post-LOCA LPCI/Core Spray Pumps NPSB Evaluation D!Leqf,-ci..-t'f Aq of> All1 3-i.

11) "Dresden Station Units 2 and 3, Quad-Cities Station Units7'""

land 2, NRC Docket Nos. 50-237, 50-249, 50-254, and so-265," letter from G. J. Pliml*to D. L. Ziemann dated September 27, 1976.

12) "Centrifugal Pump Clinic,".Karassik, Igor J., second edition, Marcel Dekker, Inc., New York, 1989.*

. 13) ASME Steam Tables, 1967.

14) Dresden Unit 2 CB&:I Drawing No. 224, Rev. 8, "24 in.

Diameter Header for Suppression Chamber"

15) '"Dresden LPCI/Core Spra¥ Pwnps NPSHA Evaluation Post DBA-LOCA," Nuclear Engineering Deparbnent calculation number NED-M~MSD-43, Rev. 1, dated February 11, 1993.
16) Dresden Station.Unit 2 P&:ID M-29, Sheet l.
  • 11). Sargent and Lund¥ Calculation No. MAD 76-198, Rev. o, "Long Term Containment Cooling -

4 Pwnps," June 30, 1976.

18) Sargent and Lund¥ Calculation No. MAD 76-234, Rev. o, "Long Term Containment Cooling -

3 Pwnps," July 14, 1~76.

19) Ferfex Corp. Specification Sheet for Containment cooling
  • Heat Exchanger dated 3/29/67
  • Equations:

suction Losses* Straight piping and fitting losses are determined using the following equation (Reference l, page 3-4): 0.00259 *.K

  • Q2 hL =.

d4 where: hL. = frictional losses (ft) K = resistance coefficient Q = flow (gpm) d = inner diameter of pipe (in) . ( l) The resistance coefficient, K, is the sum of the resistance coefficient for.the fittings, Kf, and the resistance coefficient for the straight pipe, Kp. Kf can be obtained directly from applicable tables '(Reference 9). For straight pipe, Kp is defined.as:

  • :-:* f

Calculation No *. HED-M-MSD-54 Rev. o

  • Dresden Post-LOCA LPCI/Core Spray PUmps NPSE Evaluation

..... 1/ / D J2..fCH - 0 7-1 'f A-cc af A'8'3i... .*****~".*.. ~= " ~... L Kp = f ( 2) D where: f = friction factor L c: length of pipe (ft) D = inner diameter of pipe (ft) The* friction factor, f, is dependent upon the pipe diameter, Reynold's number., and pipe roughness, arid can be determined using the Moody dia~ram (Reference l). Rernold's number, Re, *is determined using the following eguatiop (Reference l, page 3-2)! where: p µ S0.6*Q*j' Re = d * µ = density, lb/ft3 = d.ynamic viscosity (centipoise) Net Positive Suction Head (3) Net Positive Suction Head Available (NPSHA) is determined using.the following e911ation.: (pt - Pv) NPSHA = 144 x. .Y + hL. where: pt = Torus Pressure given in Table l (psia) Pv = VC!por.Pressure from Reference iJ (psia)

z
=~*static He~d, the minimum water: elevation expected above the LPCI/Core Spray pump suction as calculated below:

(4) Minimum Torus water level elevation

  • 492.52'

'LPCI/CS pump suction elevation

  • 478.13
  • Static Head.

14. 3 9

  • hL = suction losses in feet

. *- - ~-,.. ' -.. " .. ~-.. .. *_,*,:-_*'.-:*.*.-.-*-~~.. -.-./.*,*_.. -~_ ~ - '~-- '. :;'"; -. -*~-:.:: ---~- _:..::..- .. ~.-... *.. -.... _ -::.. ..:::*~--:.- -~ ':.*.*-*. ~.. -*--~~71_--.;_*r:*** *.:.. * ;.. -~l~~- -* *_*;!... :._.~;:-. ":-:.. ~-_, *. .:./..,~ .. *_.: ;.. ~~ .:... :.~--. ':****

Ca1culation No. NED-H-MSD-5~ Rev. o Dresden Post-LOCA LPC~/Core Spray Pumps NPSE Evaluation 0f2£'Cf b-o'l-.t'-{ Calculations: A-1 I c:. f A.3 'l. Suction Losses - One Pump The suction piping for LPCI pump 2A is shown in Reference 7* and is made up of the following components: Line Component No. Kf a L/D Loss(ft) 2-1502-24 11 Entrance/strainer loss o.12b 90 deg elbow (LR)c l' 0.19 ID= 23.25" 45 deg elbow 1 0.19 gate valve 1 0.10 reducing tee (thru) 1 0.24 16' straight pipe8 8.26 -Total* 0.72 8.26 0.72 2-1502A-14" reducer, 24x14 1 o.01d 90 deg elbow 2 0.78 ID= 13.25" 45 deg elbow 1 0.21 gate valve l 0.10 4' straight pipe8 3.62

  • Total 1.16 3.62
d. from Reference 15 a from Reference 9.

b see Appendix A c.from Reference 11 e sum of all straight pipe lengths minus the length of all fittings

  • The Reynold's number for each piping. run is determined using

. Equation 3.(@ 90 deg F):. 50.6 x (5000) x (62.116) - . ( 2 3

  • 2.5) x ( 0 ~ 7 5)

~ri.6 x (5000) ~ (6i~l16i . (13.25).x (0.75) = 9. o x lo5* = 1.6 x 106 The friction factor for each piping run. is determined using the Moody.diagram for clean commercial steel pipe (Ref. l: A-25): f24 = o. 0132.. f14 = 0.0134 The*resistance coefficient, K, can be determined for each piping run utili~ing Equation 2 for the straight pipe portion: = Kf + Kp = 0.7~ + (0.0132) x = *O. 83 (8.26) ~. .K14 = 1.16 + (0.. 0134) x (3.62) = 1.21 --~ *~

l, ~. -, '

l>n. 1'y.. T-~ 3 c*alcu1ation No.; NED-H-MSD-54' Rev. 0 Dresden Post-LOCA LPCI/Ccre spray Pumps NPSR Evaluation

/) /J,£&f h - 0 J-I 'f-A-1 Z..- oF A~3 Using Equation l, the friction loss for each piping run and total suction friction losses can be determined as follows: h~4 0.00259 x o.* 83 x (5000) 2 = 0.72 ft + (23.25) 4 = 0.90 feet 0.00259 x 1.21 x (5000) 2 = {13. 25) 4 hL14 = 2.54 feet hLtot = 0.90 + 2.54 = 3.44 feet @ 5000 gpm To. determine frictional losses at any flow, the quadratic relationship between.hL and Q establishes the following: hL2 = hL1 x (Q2/Ql)2 (5) Suction Losses - TwO Pumps For two pump operation, most of the 24" line (assume all) sees full flow {10000 gpm), while each of the 14" lines that branch off of it see.one-half full flow (5000 gpm). *Since the .14" line was previously analyzed at 5000 gpm, only* the 24 11 line at 10000 gpm needs to be analyzed. The Reynold's number and. friction factor for the 24 11

  • l*ine at 10000 gpm are:

50.6 x 10000 x 62.116 23.25 x 0.* 75 f 24 = *o.012s 0 The resistance coefficient and frictional losses.for.the 24" pipe at 10000 gpm are then calculated as: K24 = Kf + Kp = o.72 + co.0125).x ca.26) = 0.82 h~4 = 2.05 ft1 + = 2.78 feet 0.00259 x 0.82 x (1Q000)2 (23.25) 4 The suction.friction losses for each pump with two pumps running. is:. 'hLt t = 2. 78 *+ 2.54

  • 0
  • = s. 32 feet @ 10000 gpm total *flow

lo Calculation No. NED-M-MSD-54 Rev. D Dresden Post-LOCA LPC~/Core Spray Pumps NPSH Evaluation .J) tl'1 lc-C>1-If System Resistance - One Pump ,,4-1;, oF AJ!I# 3" The LPCI system resistance in the drywell spray mode is determined using the suction losses calculated above.and the discharge piping configuration outlined in References 17 (pp. 49, 54-55 up to first tee) and lS (pp. 22-34). The discharge piping for pump 2C is shown in Reference 16 and is made up of the following components: Line Component No

  • Kb L/ob Loss(ft)b 2-l508A-l.2". 90 deg elbow (SR) 1 30 check valve
  • 1 l.35 IO=.12 gate valve 1

13 90 deg elbow (LR) 1 20 enlargement 12xl.8 1 0.15

  • 3
  • 5 ' straight pipe ( 18")

2.3 Total 0.15 199.J 2-l509-l8"c 90 deg elbow (LR) 5 100 90 deg elbow (SR) 2 60 ID=l.7.124" 45 deg elbow (LR)

l.

12 gate valve 1

l.3 tee (thru) 1 20 tee (branch) 2 l.20 63' straight pipe 42
  • heat exchangera 1

34.6 at 60F 10700 gpm Total 367 2~1509-16" 90 deg elbow (LR) 4 80 gate valve ** 2 26 'ID= 15.2s~* *45 deg elbow l 12 .reducers (18Xl6, l6Xl.O) 2 0.1 108 1 straight pipe 81 Total 0.1 199 2-1509-10" 97.S thru spray at ring header 12000 gpm a 15 psi pressure drop (Reference 19).* b from Reference 17 & 18 c The flow path evaluated in Reference 17 was for LPCI operation in the injection mode and therefore bypassed the component Co.cling heat exchanger - assume piping/fitti?lg losses* on line thr9ugh heat e;xchanger to be similar to piping/fitting . losses on.l_ine _bypassing *heat exchanger *

    • ~.:....
~.

'~... :*_~~.

y I '; Calculation No. HED-M-MSD-54 Rev. o Dresden Post-LOCA LPCI/Core Spray PUmps NPSR Evaluation /)(2.£9 b -O"l.I ~ A-ti.for The losses through each of the above segments at sooo gpm can now be determined as follows: Line 2-l.SOBA-l.211 Line 2-l:S09-18" Kl2 = f x (L/D)tot + Ktot = D.013 x 200.S + 0.15 = 2.76 (0.00259) x Kl2 x Q2 hl2 = ~------------------- d' co.00259) x 2.76 x sooo2 = ~----------------------- ( 12) 4 = 8.6 feet @ 5000 gpm KlB = 0.012 x 367 = 4.40 . (0.00259) x 4.40 x 50002 hlB = (17.124) 4 = 3.3 feet @ 5000 gpm

**.'.*1 Line 2-1509-16"

.j..:.. Kl6 =

  • =

'hl6 = 0.012 x 199 + 0.-1 2.49 (0.00259) x 2.49 x 50002 . - (15. 25)'4 = 3.0 feet @ 5000 gpm .. ->:*~-.. -. _'*._.

.,hHX = 34.6 ft. x (. )2 5000 *

. 10700 ~ - ~ :*

  • =.1.-6.feet.
  • @ *sooo gpm

. -~. --:~ ~ --:-,: <... :~ :*"'*>. *: ~:;. -~- .. '-'J .. * ~-

*: '.. ~.

~. --~-...... ":..:if _'.J . ;'\\ 1 - ** ~ 4rl

. ~. '** ll/ .Calculation No. NED-M-HSD-5-4 Rev. o Dresden Post-LOCA LPC~/Core Spray PUmps NPSR Evaluation 1Ja.F9 6 -o 2 t l Air or A~ Line 2-l.509-l.0" through rinq header hlO = 97.S ft. x ( ::::~ 2 = 17.0 feet @ 5000 gpm Elevation (static head) losses helev = ring header min torus level elevation elevation = 527.1 1 492.52 1 = 34.6 feet The total system resistance at 5000 qpm is the sum of the losses of each segment from the torus (suction) to containment (discharge) :. hsys = hsuCt + hl2.+ hlS +.hl6 + hlO + hHX + helev 5000 = *3

  • 44* 1 + 8
  • 6 I + 3 *JI. + 3
  • 0 I + 17
  • 0 I + 7
  • 6 I + 34
  • 6 I

= 77. S.feet

  • @ 50.00 gpm Maximum LPCJ; Flow - one Pump

. At 5000 qpm, the LPCI pump can develop 360 feet of head (Reference 5), and would therefore not be challenged or limited by.the 77.2 feet.of system resistance at this flow. To determine the system resistance at any flow, the dynamic losses (all losses

  • exce~t elevation) are adjusted usin9 Equation 5 and added* to the static.loss.(elevation), which remains constant at* all flows.

At 6000 gpm, the system resis~ance is.found to be:

  • bsys =

6000 = = .(*6000)* 2 hsys -.belev x + *helev 5000 5000. 42.9. x (:::~) 2 + 34.6' 96.4 feet @ 6000 gpm ....... ". *. ~

.*. ~.;' ~- *,:. -..... :~"-.. 13 I I Calculation No. NED-M-MSD-54 Rev. o Dresden Post-LOCA LPC~/Core spray PUmps NPSH Evaluation b!2£'l~-ou A-1 \\D t-F A§f At. 6000 ~m, the LPCI pump can develop about 105 feet of head and is still not limited by the 96.4 feet of system resistance~ At 6020 gpm, the system resistance is found to be: hsys 6020 ( 6020D 2 42.9' x + 5000 = = 96.8 feet @ 6020 gpm 34.6' Through linear interpolation between data points ~rovided in Reference 5, the LPCI pump developed head at 6020 ~mis about.96 feet. It.is at this flow that *the system would limit the pump and is therefore the maximum LP~ pump flow attainable in the given system configuration.

  • systelTI Resistance - Two Pumps The.system resistance for the two pump case is very similar to the one pump case with the following *differences: (-1) must use suction *1osses calculated 'earlier for two pump.operation, and (2)

.lines 2-l508A(B)-12" will only see 50% of the total LPCI flow dul:'ing two pump operation. At a combined flow of 10000 gpm (5000 gpm per pump), the individual segment resistances are as follows:* hsuct = 5.32 feet helev. = 34.6 feet hl2 = 8.6 feet (same as l-pump case) hl8 = 3.3 *feet x (iooop2 hl6 *= 3.0 feet x ~0 00v 2 hlO ,.~ j 500,0

  • 5000

-*= 13.2 feet = 12.0 feet =.97.8 feet x &0000)~ hHX = 34.6:feet X (:oooJ 2 12000 . 10700 = 67.9 feet = 30.2.feet The total system resistance for the two pump case is:

  • hsys = hsuct + h12 + hlS + hl6 + h10 + hHX + helev 10000 = 5.32' + 8~6' + 13.2' + 12.0* + 67.9' + 30.2' + 34.6'.

= 171.8 feet @ 10000 gpm ...... _,~:""" -;* -*~~ l*

  • }~.'~ ~---. -~
    ~ ~* ~. ~ i!.
    • ~ :. ~

,; '"I -~*

Calculation No. NED-M-MSD-5~ Rev. o Dresden Post-LOCA LPC~/Core spray PUmps NPSE Evaluation Maximum LPCI Flow - TwO Pumps /) llE '1' - ~'Ll A.' '1 o *~ A{jli At 10000 ~m, two LPCI pumps can develop 3*60 feet of head and are not limited by the system resistance of 171.B feet. si:r:ice 11620 gpm.tota+ two pump ;1ow re~resents c:me of the cases being anal¥zed in this calculation, this flow will be used to determine if it is a bounding flow for this configuration. At 11620 gpm, the system resistance is found to be: X 0 1620~ 2 hsys = (171.8 1-34.6 1 ) + 11620 0000 3.4

  • 6 I a

219.9 feet @ 11620 gpm At 11620 ~m, two LPCI pumps can only develop about iso*feet of head, insufficient to overcome the system resistance. Therefore, *case R0-2 bounds two LPCI pump drywell spray mode operation for both flow and, as a result, NPSH. NPSHA Calculations:

  • .*using Equation 4 and* the inputs provided in 'Table l and Equation-5, the NPSHA is calculated for each of the cases given (Table 3).

The required NPSH is also provided and the difference between the two is calculated. The NPSHR provided.is for cold water and is not corrected for the increased temperatures expected in the torus. This adj ustlnent would have reduc.ed the NPSHR and resulted in a greater margin for NPSHA over NPSHR. From Figure l (Reference 12), the reduction at 170F would be a~proximately 0.3 fee~, and at lSOF approximately 0.4 feet. Summary/Conclusions: Post-LOCA torus conditions were determined in Reference 2 and were used to calculate the available NPSH for the LPCI and Core Spray pumps at Dresden Station. The results in *Table 3 indicate that the available NPSH is greater than the required NPSH for all cases, and therefore adequate to protect the pumps under these conditions. The results bound all of the LPCI ~umps as well as the.Core Spray pumps for both units based on similar suction losses, required NPSH and pump elevations. Also developed was a LPCI system resistance for one and two pump o~eration.in the drywell spray mode. This was used to determine the maximum one and two pump LPCI flows in this mode of operation. The maximum one*pl.Ullp flow case (R0-8) was evaluated

  • and the.NPSHA was found to be adequate to protect the pump.

The maximum two pump flow case was* found to have a lower flow than case R0-2 and is therefore bounded for NPSH by case R0-2 * ..... : ~.. ':. ~ _... .,. \\ '":.

    • . -~-...

~- ~. _.:.....

,j.* v

. j:..... **,.;.. ***... *
      • q.

(**./.*.. :,**.;.:.: . * '*. ~;. ~~. '. ~ -~ t ~.... ... *!II . I*,.,,., ~-~~ .... ii.;.>> .*~* ~*-*~,, ~. .-~*~. )

  • - :* l

-~ ... I ~t *. :;

  • ~

.* :i ,*J, ** !l'I . :... ~ Calculation No. NED-M-MSD-54 Rev. 0.

  • Dresden Post-LOCA LPCl/Core Spray Pumps NPSH.Evaluatlon Tabla 2

LPCI ccsw Torus Torus Stelle Specmc Vapor suction Flow Flow Temp Press Head Volume Pressure Losses NP SHA NPSHR Margin Case (gpm) (gpm) (Fl {psla) (fl) (ft3/lb) (psi a)- (fl) (ft) (ft) (fl) R0-1 10000 5600 169 19.5 14.39 .01645 5.856 5.32 41.38 30.0 11.38 R0-2 11820 *4795 170 19.8 14.39 .01845 5.993 7.18 39.92 38.5 1.42 R0-3 10370 4795 170 19.8 14.39 .01645 5.993 5.72 41.38 31.9 9.48 R0-4 5000 3500 180 20.6 14.39 .01651 7.511 3.44 42.07 30.0 12.07 R0-5 5300 3071 182 21.1 14.39 .01652 7.850 3.87 42.05 33.0 9.05 R0-6 5920 3071 181 21.0 14.39. .01652 7.679 4.82 41.25 '39.7 1.55 R0-7 11820 3071 178 21.1 14.39 .01650 7.184 7.18 40.27 3e:5 1.77 RO-B 6020 3071 181 21.0 14.39 .01652 7.679 4.99 41.08 40.9 0.18 Tabl* 3

I~ .......... -... *;;or,.*:,1 _:*.. 1-; -'.~*. ~ T ~ 100 -- ~ r - c - ~ L-......... f - SD ~ ~ ~ ~ I, .)'

..... ': 1 I

~ ~ ~ }'I* ~* ' ~-- ~ ~* .. ~ I

  • L.ol-~..-"'........

10

8.

6 5 4 3 2 1.5 ~ o.s I J-1-rT I ~ l~::rt--t---t--t--T-+-"'i~,.-t-+-+-+-+.,._ .-+--+-+-H-+-+-~-+-""'""..i...1~.JJ..U-1-++"-.U.U i.o~~--"-..._...... ~1--i._.._.._._.~ 1'.-i......i..-'-.._.~_,_......u~J..J..J..l-UJLI.1.L.L.l..UJ.U . 50. .100 1SD 200 TEMP£RAlURE. ('"F) 0 250 300 400. _*.--:-_:*_*.. _*-~:..--_.:' ___ ---:~:_* ** Figure 1..29

  • NPSH rcduc:rions for pumps handling hydrocarbon liquids and high-remPerature water (Collnosy Hydralilic Institute Standards of 1975.) *

.... -;.. ~: ~ ~-~!~*:_ t~ ~ ~-.: ~'~.-.:... **.*,.* -:*.*. -:. : ,.";:i~$'*;~!;{,,* 7:: : '> <' \\ _;~~::0:~~.u RE. t .*. l Reker@AJ<~ J;!, f

  • S G)

.. ~ -. - ~ I

-~ Calculation No. HEI>-H-MSD-54 Rev. o {'. ~. "' J {..... \\ Dresden Post-LOCA LPCX/Core spray Pumps NPSB EValuation APPE5DXX.A ~ncreased Bead Loss Through Plugged Strainers D/2.fq £ -c t.l ~ >rw o-F-AcJa In Reference 11, combined entrance and strainer losses were determined to be o.s ft. @ 5750 gpm for a single LPCI pump and

2. 4 ft. @ 11620 gpm for two LPCI pump operation. _ These values were ~ene~ated assuming no strainer plugging *. Since the strainer loss is given as 1 ft. @ 10,000 gpm, the strainer and entrance losses can be separated as follows:

Strainer loss @ 5750 Strainer loss X @ 10000 = 0.33 ft. Entrance

  • Total

_strainer loss = loss loss @ 57.50 @ 5750 @ 5750 -= o.s ft. 0.33 ft. .= o_.47 ft. Similarly, the entrance loss for the two pump case is:* Entrance.

  • loss

= 2.4.ft *. -.@ 11620

  • =
1. 05 ft *

(1 ft.) x ~~:::) 2 . For the purposes* of* this analysis*, all four torus strainers are assumed 50% plugged and all flow leaving the torus is assumed to be evenl~ distributed through the four strainers. From Equation 1 it can be -seen that by reducing the flow area (and therefore d ) by 1/2, the losses_ are increased by a factor of four. For a strainer flow of 1250 gpm (5000 gpm total), the loss through all four straineJ:;"s is:

  • 1 _.

X '(1250 ) 2

  • /*

. ~.,. ~ --.--~ *'.*.c Total'.

  • strainer

-LOSS_ -J ~:.. ~ -~:*;.-!...:~* *. . ---~.;:.;.-:_......... _.... _. = 4 x 4 x (1 ft:.) .* = 0.25 ft. . ' ~. ,. l. .. '- ; :_ -~-*..:*;~:-:-- ---~.~ _:~*~-.,.. '. :::.*:-~... :-;";:':'.'"::>~:~.,,*~:~:-.:*** _* \\* ~. ~* '.-l-~: *_ *..,~~'.:P~-=:._* *,.. >

    • -.:~~- =~~~t:.. ~ -~-~

10_000

. *~-*. ~ '* '* r .... _ '.. :.~ :..:.:..- *.. . -"'*-~-- calculation Ho. HED-H-MSD-54 Rev. o Dresden Post-LOCA LPCI/Core Spray Pumps HPSB Evaluation 1)1.F 'tb -o 1.1~ A'-I o-F A~5 Conservatively using the entrance loss at 5750 gpm, the combined entrance and strainer loss at 5000 gpm for a single LPCI pump is: Total loss @.5000 = 0.47 ft. + 0.25 ft. = 0.72 ft. Similarly for the two pump case, for a strainer flow of 2500 gpm (10000 gpm total), the loss through all four strainers is: Total Strainer Loss 4 x 4 1 ft. ( ) 2 2500 x (1.ft.) x 10000

  • Again using the entrance loss at 11620 gpm, the combined entrance and strainer loss at 10000 gpm for two LPCI pumps is:
  • -*Total loss

=. 1 *. os *ft. + 1 ft. @ 10000 =* 2.os ft. J, . ~. .l~. ,: \\.... :. -. -._:~~ -: ~ -* ~: *--.*. -. --~. r ' *J.-.:-. --/":-:-

.. ~
*.:\\:.. Lr. :*~-

-'.~.~~:: *. ~-<.> - _~_;"; i .. -\\ -

-~-. c:::::>,;: J) CJ, I AJ /'. 'jf l/- COMMONWEALTH EDISON COMPANY~ * ~r1. '~r. 'f!r CALCULATION NO. REVISION NO. I 0 llh = f.!:... Q: co.00259) . D d PROJECT NO. NIA I This equation was converted.from ft to psid in the following way: !lP = [ LQ 2

  • ]

I D-d7-C*0.00259> - 2.3 07 PAGE NO. 16 b ll..f'H~ -o L. I 'f A--2 1.. <tF A 11113 2-(5.ol (6.0) A pressure drop calculation was done for the case where four pumps were in operation. This was done since test data for four pump operation was available (Reference ); with this data, the flow model could be validated from actual test data. The calculation was done as follows

  • with the sections of pipe referenced to Figure 1.

Section 1: Section 2: .... ****r

  • Qr

.J

  • .(O~O 12)(J.17.2). d4L"'. (0.00259)
  • *. *c11.124r flPco~montocro11*tic '.'":

. ( 2.307) ~5pSI~ Section 3:.. [ (1779) 2 l (o.012xJs6.2) 4 co.00259) (17.1-4) . /l.P0;01~.,;. 1~ 21 ~al*~.= ( ) = 18.09 ps td 2.307 Section 3 Flow.Orifice: *

  • [ * *
  • c11219) 2 *i *

(554). -(20000) 2

  • !lP. = *

= l4.94psid orifiu .*.<2*301xr2) .. ~dP1 =.2.70 -+:. 018.09+3.75+ 14.94 = 39.48 psid ~.. ~ *~ :"-~ ."'-"'R ~ (6.0) .(6.0) (6.0)

1:~1 :.* 1

,;:. *.*i

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    • *-* --------*-s'"..... J..... s""o...... o;,;c~o::...-.. _____ _.., ____ 3, 500.poo __.

I STEAM CONOfP4S£0 I'. I GAAVl'tY~IQUIC VI \\COSIT"l'-1.JCUI O*-*-

0._.... 4.J ___

c:,....P_S.;...~ __....._ ___ -'----.=...:.~-=*...:....~..;:_..;_ __ "ll!COSliY.UOUID CPS.. .WO\\.ECULAA 1tl!l::tiT-l/Af'ORS I I* IS 16 .17 II 19 20 21 ne~ ~-N-_-C_O_H_O_E_NS~BLf-S ______...;..._. ____ _:. __. __________.,_ ______________ _ 1 ,Lu*o...,.P"C,-~*.-uo ~--~oe.. sE"o* ! SPEC:FIC HE.t. ~-1... IO!JIDS I ~TfNT HEAT.V.t.POi°s_____ -~.

1---.--.._ ___

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    • ---- 10s ooo.aop liLT.o. ccoHecT!o~-- 42~z~---~---

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  • l6. [Des~~~-TEMP£:t" Tu!!...

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  • !.s~~lL Steel.------*

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  • 9

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~!.1.11H~~:!.T~!~~~~A_v~onc.J Clad Steel (..11411 overtay) FLa.ATrtiio

  • :_!A:_=:L_E_s:-~'"E.~s *. _... ~.Lc:cl.--:

TYP!.zcn. cut,.Aguble u:immtil 22-:1*12*.... ~.~.azi*rl!j~~~ 0 . BAf"LE.;,..ONC. TYP! . TrJee :;uPPOl:!n

  • I

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  • -*---***C::~"~.E'l..~*~-* -~-' ---

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  • ---ill'!. ____ _

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T!MA CL.A.SS -~~

,._c_1;;_1;1_;~:.E~~.l'!EL,y'... : 64.~...

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. *(j) 57

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.-~-~ '~.. :.,:,; ~;~:** ::.~ "_; _l.l6i+*:~u~!f°1;,,.P._,._var -~:i~:~-L.iri~. L*-~i ~'!.._.._?..!tl...~!.<<!! ~~.£3.. ~Y.. Kvn~!_* ____. __ *--~

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  • 1

REF. 2.. DRESDEN - UFSAR D IZ-E 'i' -O"l.-1 '( A1-'-l ~ A')ll32- ~ ~ ~t:.s. !NP. 7 diagrams of the CCSW systems for Units 2 and 3 are shown in Figures 9.2-1 (Drawing M-29, Sheet 2) and 9.2-2 (Drawing M-360, Sheet 2), respectively.

  • The CCSW system provides cooling water for the containment cooling heat exchangers during both accident and nonaccident conditions, as described in Section 6.2.2. System piping is an-anged to form two separate~ two pump, flow networks (loops). Each pair of CCSW pumps takes a suction from the crib house
  • via separate supply piping. Two CCSW pumps discharge into a common header which routes the cooling water to that loop's associated heat exchanger. At the heat exchanger, heat is tnm.sfe?Ted from the low pressure coolant injection (LPCI) subsystem to the CCSW system, and subsequently to the river.
  • 9.2-3 During normal plant operation, the CCSW system is not operating. Following 8n accident or other plant evolution which requires containment heat removal, the CCSW system is manually started. Each CCSW pump is rated at 500. hp with a service factor of 1.15. The CCSW pumps are powered by normal ac or diesel generator ac power. Additional CCSW pump information is provided in Table 9.2-1.

9.2-4 The CCSW pumps develop Sufficient head to maintain the cooling water heat exchanger tube side outlet pressure 20 psi greater than the LPCI.subsystem 9.2-6 9.2*8 ressure o shell side while maintainin rated heat exchan er flow. e AP is maintained by a differential pressure control valve.. Maintaining this pressure differential prevents reactor water leakage into the service water.and thereby into *

  • the river..

The 'four CCSW pumps are located in the turbine building. Two of the four CCSW pumps (pumps B and C) are located in a Single, eommon watertight vault for flood.

  • protection. To prevent the CCSW pump motors from overheating, the vault has *
  • two vault coolers. *The cooling water for each cooler is provided from its respective CCSW pump discharge line throligh a four-way valve. This valve also permits flow reversal of the cooling water through these coolers to help clean the tubes. Refer to.
  • Section 3.4 for a discussion of the flood protection features.at Dresden.

A continuous fill of the CCSW system is provided by the service water system or, in the c.ase of a loss of pow~ to the service water pumps, the diesel generator cooling. water system may be aligned to provide.the continuous fill. This eliminates the potential for water hammer upon CCSW systel:n startup. The diesel generator. . cooling water system is discussed. in Section 9.5.. 5. * * * *...

  • The Unit 2 CCSW loops also provi~ a.safety-related source of.service water to the control room air conditionmg condEµl!lers. Refer to Sections 6.4 and 9.4.1 for a description of the control room ventilation system.

9.2.1.3. *saretv Evaluation* ContaiDm~t cooling is not immediately re~d following a design basis loss-of-coolant accident (LOCA). The required timjng of the initiation of containment -. cooling functions *by CCSW _is described in.Section 6.2.2. One of the two heat exchangers, two CCSW pumps, and one LPCI pump all in the same loop are the - ~- *- ~minimum* requirements for_ containllient cooling. ~ '

i I i* .Y t1..e q(o 1 y.. AlS o: AJl!J1.. GE Nuclear Energ;t (JU 1AJ4.f I'). f P.!. IN I'. 7/-1/) G~ru:nzt Elur.-i: Compm~~ 17.S Oumu A11e1tuc. SOii Jost. Ci 9511.S November 4, 1996 To: 'J. Nash From: S. Mintz I I I I cc: T. H. Chuang N. C. Shirley G. B. St.ramback DRF TI3-00740 Sl,lbj ect:. Review.::,f NRC Infonnation Notice 96-55

  • Reference 1).
2)

I NRC lntormation Notice 96-55: Iiiadequate Net Positive S~tion .Head o~ Emergency Core Cooling and Contaimne:it Heat Removal Pumps 11ndcr Design Basis Accident Conditions. I I . GE-NEf!2300740-l, Dresden Nuclear Power Station t'Dits 2 and 3, Contaimnent Analyses oftbe DBA-LOCA Based on Long-term . 'LPCI/Cbntainment Cooling System Configuration of One LPCI/Cbnmimn~t Cooling Pump and 2.CCS"\\V Pumps, "Nov. 1996 ($AFT)

  • i
  • Per your request NRC Inforindtion Notice 96-55 (Reference 1) and Branch Technical
  • .Position CSB 6-1 have been r~viewed to deteimine wbat impact they might have on the
  • *containment analyses perfon:ied by GE to evaluate NPSH for Dresden (Reference 2);

I . Reference.l and CSB.6-1 cac~ include desaiprions of models acceptable to the ~C to .. be used in determining contairiment pressme for use in calculating available Net Positive Suction Head (NPSH) for prc+mizc:d water reactor (PWR) plams.. The assumptions used . in Reference 1 and CSB.6-1 a:i:~ stated as conservative! y minimizing containment* pressure and tbcrcfo::-e conset'-Jatively evaluate available NPSH in_PWR plants. They arc thBerWR.ef ore not directly. applied + any containment pressure or NP SH assessment related to a I I

  • * * **. *.. Containment anal!scs perf~riticd by GE tO evaluate :a~*ciilablc NP~H.for ~WR

~l~t.s with

  • *pressure suppression contaJnmcnts also use conservanve asswnpuons which ID.!lll.IIllZC
  • . *..,... *.. calculated containment pressJe. These assumptions provide an equivalent degree of

. conservatism ro the CSB 6-1 ihodel assumptions for PWR plants. 'I I

/
      • ::-~~:. : -~,.. :The assumptions *used in the:qE arui.lysc:s are disc~se~ in the folloWing:
    • ... ~

-._*1,. --.. ;--.. -~ ' :*:._:::::::-;/*:'.."'>:~*;< :::,~: *; :>.-.:... : :.. :-.*.....

  • .:. **:.* / -~..,l *_.*.. :. *-..

.. ~::.. -, ~. : *:' ~~-. i,,";;'~~-~~it~~;gc<.J-) *.. < ~ ':, -' *.* *' *..* * *.**** *., *,.*.

  • ;.I. 7 '*,

~ ~ ~..

'... -~ ~.... :... ~*;... ". 1 *** *

L* i::~ :.'.:;:\\;:.: :.::*. ;:**.
~ \\,*:

.. t:.

  • C CASE Thcnnal. Mi.x.inc Efficiency
  • 0 -

J'.' TABLE 2.~ Summury<<>f Dresden Containment Analysis Results ])e.s.' t"' ~..,;... t :JI: II 1 la la l la la lal lal. J la Ja Jal Jal 100 100

20.

100 100 20 JOO 20 JOO 100 20 JOO 20 (%) :.

  • ... **}

.:\\. - ~ I . *( I**, ,*. "'. *.'".. 1.*.. '> 'i>t::<.. t;' !'.~..

  • f.. ' :.-:*-:.

c*.* :.:'('.;:.. *.* .t... ... *".'.;. '(; '. .* I

    • ~.;

r~ :* 1* j ~.: *.*l,4

  • J j ;* *,

i*

    • '¥'1 '

'1.':,,J . *.'..  ::;CJ '... f:.:.:..;*.. ~. <~i'.[l t~;*~. J

*~.
.~J
r:~ :~~.

.* : ~.. : :

  • J
'*'. *~
.,.. *~'.,

' *'.s 1::: \\::*-.:..... Heat Sinks

rio no no*

no no no yes yes no DO no yes yes ~-------"'-----"'--1----------1--------t--'---~--'-----t-----~------1---~-t---~~-.....,..---+------1----1----.f.---- Suppressioil Pool ISO ljO i49 148 ISO* ISO ISO 141 Temperature 1"*s. 14,. af6UD5ccT'FJ-*-:'-*-- -.~~ -.-. - --... -'-*--*--- -- __.;... -*-*---4---------___,__ ____ -*- -- -------< (Al initiation of 149 148 operator actions). Suppression Chamber Airspace Pressure at 600 sec (psig) (At initiation of opcreror actions) Minimum SUpprcsslon Chamber Pressure Following Initiation of Conllsinmcnt Spray (psig) Pc3k Long-renn SuppreMion Pool Tcmpcralurc* (DF) Suppression C.bomher Airspace Pressure at time of Peak Supprc.ssion Pool Tcmpcniluic (pslg) 11.3 8.S'.* 6.9 4.S 173 173 7.2 4.9 8.7 12.S s.s. 2.7 6.3 4.0 2.2 l.6 171 171 J7l 173 172 3.0.. 7.3 4.9 3.0 4.8 I0.9 8.8 6.2 12.3 S..5 11.0 1.9 b.2 3.9 l.O l.S 1.7 173 171 171 I'll . 171 171 '1-- 0 I"' ~ Ei' 2.9 7.2. 4.7 3.1 4.7 3.1 -S> Q, CJ' \\' I 0 ~ t.. tN

300 2SO a 200 ~ GI 1SO .. = *.. 100 e .Q. so

0 0

'~.* *. 300 250 I

  • =.200

.. :s: 150 CD

  • =..
  • 100, I!!

A. so .:. -,1 RrP. 1 1000 I I I I I I I I ... 1000. Unit 2, CCSW Pump Curve 2000 Flow (GPM) I' I I 3000 Unit 3, CCSW Pump Curve I I I I I f I I I 2000 . 3000 ,* *FJow (GPM) 4000 4000 o;2.:E"q<:o -c "2-t'f A 1.. '7 r. P-A,P3 "},_ 1ro~/*

  • 1 I* Surveillance Data j I I ! i I

I

  • .*. *Dresden operating Surveillance DOS lS00-12.tests eacli loop(2p~ps) ofCCSW. The *
  • acceptance criteria arid the latest surveillance results are as follows:
. A~ceptance Criteria*

Unit.2

  • unit2

.Unit3 Unit3 gpm

  • Loop A**.. *

. ~- ~.

  • -Loop B Loop A Loop B
  • Unit 2-7102 *

.~*7200 . 7200 xx xx

  • unit. 3-7000 *.. :. *,:.~.:.

.*xx

  • xx

.6975- -7100 ..,._.'.:::-*~>>:* ~. :~: D~~:~:~: Io\\.\\> fl~~ con~iti~~in U.nit 3 Loop A, a Problem Ide~tification Form was -. :* '_:*::tx~... -.:}.>. 'generated:ari~ an operability.evaluatio~ is in place which establishes an upper limit on }~it:il~;~i:!1~t'I~~:;}f ~~;1~;f I~~~*J~~i*~~, <;~:~*'.-, : ** '. :.

v

~

])5.. I #JP. # J l- !.:::uest *Task: 960076622 01 L-iurr.ber

00.

I lll!ll lllll lllll lllll ll/11 111111~/l ll~l lllll lllll 1111111111111 P~ge: 3 Date: 08/14/96 PART 1 of 2 i Type M MASTER Work Date:

t (RX) 2A CONTAINMENT COOLING BEAT EXCHANGER
.cie:

2A LPCI/CONTAINMENT CLG RX TOBE SIDE DP VERIFICATION JESCRIPTION: (~J FABRICATE COPPER TUBING FOR HIGH SIDE CONNECTION AND CONNECT.FROM HIGH SIDE OF TEST TRANSMITTER TO INPUT OF HEAT EXCHANGER VALVE 2-1501-77A. (-4' REQUEST OPS TO VALVE OUT VALVE 2-1501-78A AND REMOVE PI 2-1502-61B. c0**. FABRICATE COPPER TUBING FOR LOW SIDE CONNECTION AND CONNECT FROM LOW SIDE OF TEST TRANSMITTER

  • .TO *OUTPUT. OF BEAT EXCHANGER VAL VE 2 -15 01-7 SA *

. ( v( : CONNECT BETA CAL TO LOW SIDE TEE OF TEST TRANS * .,_~*sJ~l.REQuEST OPERATIONS TO START. CONTllNMENT COOLING \\/la ?SJ . ~,. '~SERVICE WATER PUMPS. I I ('i. t'.6 *I.- 14' -.01.~ fv"'f c~~nu'). ~ol.. < 1n \\t:'.il ~... t.:ff... ~ ~ccr.cl 1::>r ~*~- D;fJ --:LJ.'j7_.. )_2!..?F~ ....' >.c~-WITlI,.TWC,.PuMPS RUNNING AND. SYSTEM STABL~~ ~.r:r.~....,~~(l~.t-~i;--**-.:J.)61 _ .: :_.. TES~~ FIXTURE ... AND *REC:ORD D/P READING ~ELOW.. -~.. 0 ~.P *--~- _*_. ~'Z_._.S _P-5I..-.:C~~ 7Dv)

  • SJ' sJ'fc,

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BETA.CAL. AND DOCUMENT READING BELOW *

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. ****cYr.. ~~~ ~OVE ~Di-Gs* WITH SYSTEM ENG~ AND

  • *' * * *AND.*PER* SYSTEM ENG. : 'PERFORM ANY OTHER TESTING*

.. _µ V°T'! * ~,_;~ rlvi'l!.~'1 .* * :**... *,::.FOR.-D/P READINGS.-. **.. ' . t\\~C:.

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Cl~ 9/t'>J'l&! . ~:.'.(/)*.*WHEN. ~STING I~f CO~LE~: REQUEST OPS TO VALVE . * > OUT 2-1501"-77A *re 2-1501-78A, AND REMOVE TEST "FIXTuRE...

  • .:~c-J;.INs~Ar.~ -~r:2-1~01-6~~ ANDREOUEST *oPERATioNs.

. :**:* _ TO.POSITION *vALVE AS DEEMED NECESSARY.. . : _* y: *.***.. ~ '... **.::* *z -~ "ft6 <i/N/ib - ** .,:C ). INST~L PI.Z-1501-61B, AND.REQUEST OPERATIONS . :.. - *:_TP POSITION VALVE AS DEEMED NECESSARY. ~ !' ' * ... <TJ :ENSURE ALL CONNECTIONS ARE.SNUG TIGHT AND VERIFY . :.. " *->~~>./'.:<~~.-*.,tEAK.:* ... -~.-~.:-.. ~---.. '.:*.. .,. -~.

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960076624 01 00 Date: 08/14/96. ~ber Type PART 1 of 2 le: M MASTER 2B LPCI CNMT CLG me 2B LPCI/CONTAINMENT Work Date: TUBE SIDE INLET CLG me TUBE SIDE DP VERIFICATION SCRIPTION: ( *ti-FABRICATE COPPER TUBING FOR HIGH SIDE CONNECTION AND CONNECT FROM HIGH SIDE OF TEST TRANSMITTER TO INPUT OF HEAT EXCHANGER VALVE 2-1501-77B * . (,/ REQUEST OPS TO VALVE OUT VALVE 2-1501-78BJ

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  • AND REMOVE PI 2-1502-94B.

FABRICATE COPPER TUBING FOR LOW SIDE CONNECTION AND CONNECT FROM LOW SIDE OF TEST TRANSMITTER ., 1_ TO OUTPUT OF HEAT EXCHANGER VAL VE 2-1501-7 SB. ~ CONNECT BETA CAL TO* LOW SIDE TEE OF TEST TRANS. . A 'REQUEST OPERATIONS TO START CONTAINMENT COOLING . *./ SERVICE WATER PUMPS. -:, - f-1"1'/. J?/IC./v/1'/) /V////;y,,. /'"'4#.:t * //J /J'./ /;/ /i-;r:.. /c-"".l'Y.I ~~ ~1r1~1 - - . /fc':u,._,.._I pt/' /cd6l!.?.

  • J) WITH TWO PUMPS RUNNING AND SYSTEM STABLE, VALVE IN
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TEST* FIXTURE AND RECORD D/P READING BELOW. . D/P =_ -~-- ~- 'f_'!_ 11~1_e/_ *- ..;{ WITH. TWO PuMPS RuNNING AND SYSTEM STABLE', VALVE IN BETA.CAL. AND DOCUMENT READING BELOW. PSI =-~---*

  • 1 REVI~ ABOVE READ~NGS WITH SYSTEM ENG.* AND.

..., '~. '** :_AND 'PER SYSTEM ENG.* -.:PERFORM.ANY OTHER TESTING -- -. FOR D/P READINGS.* * *,

.,/ ~

~ST~G. IS_* C.OMPLETE REQUEST OPS TO VALVE OUT 2-1501-77B & **2-1501-78B,* 'AND REMOVE TEST ., FIXTtlRE... * -. : . :.. :-~:<~STALL ~I '.~--1so1-:~4A', --.AND~ ~QUES~- O.PERATIONS ... ';'O POS.. ITIO~ VA:L~ AS DEEMED NECESSARY. -~ - '.....'1.. &. "'6 8/rl{t{, .... _-./INSTALL PI...i:...1so1-94B, AND REQUEST OPERATIONS -. ~p *poS.ITION VALVE AS DEEMED *NECESSARY. .. :.~: ~~SURE ALL. CONNECTIONS. ARE SNUG TIGHT AND VERIFY _, __ :: *:~ "... :t-{O_ LEAKS.,' 1~<>~. / :. -. ~;~~.~.tr\\&~;D:L f "",*~~:.**.****I :J::~:r;t;:;~.* *%---*

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