ML21209A233

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1 to Updated Final Safety Analysis Report, Chapter 10, Figure 10.4-13, Piping System Flow Diagram Steam Generator Blowdown
ML21209A233
Person / Time
Site: Summer 
Issue date: 04/30/2021
From:
Dominion Energy South Carolina
To:
Office of Nuclear Reactor Regulation
Shared Package
ML21209A581 List: ... further results
References
21-167
Download: ML21209A233 (1)
v • d • e


Text

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14 13 12 11 10 SYSTEM DATA

[(> GPM PSJG

° F REMARKS 1

111 ll'J93 557 MAX.BO RATE

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SIX PLACES __

2 1

13111 12111 SAMPLE FLOW 3

84 1080 120 MAX.BO RATE 4

250 40 120 MAX.BO RATE stfl'EY Cl.ASS VERIFJCATH>>JS allGINATED BY I

EJA 2-12-74 RE\\IIEIIED BY I

RHK 2-12-74 8

7 ISOLATION VALVES CLOSE SIGNALS

1. CONTAINMENT !SOLA TION SIGNAL PHASE 'A'
  • 2. START OF EMERGENCY F.W. SYSTEM NOTE:

A MANUAL OVERRIDE IS PROVIDED FOR SIGNAL (*) ABOVE.

SWITCHES FOR THESE VALVES ARE PROVIDED ON MAIN CONTROL BO <XCP-6112).

A COMMON SWITCH IS USED FOR "B" TRAIN VALVES.

6 E-4

< -011 "M""s=---

5 J-14

--~

I RM I ~3 PLACES 4

HIGH RADIATION SIGNAL FROM RM-L3 CLOSES VALVE 524 &

OPENS VALVES 525 & 541.

3 2

HIGH RAO!A TION SIGNAL FROM RM-Ll0 CLOSES VALVE 547 1

IRC ORC NEXT LETTER (j_)

STEAM GENERATOR WET7 LAYUP PURIFIER SKID RGL-1

/

XPT-9-BD 2"

100 GPM PUMP 2"

RGL-1 1/2"

/

4716-HR-BD RGL-1 1/4"

/

10533-BD 1-'-ll~f-SAMPLE RGL-1

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XPP-501116-BD RGL-1 VEN/' 10534A-BD 1/4'f RGL-1 4

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XFL-5045A-B0 C@:]1i,-,,---1

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RGL-1 10525A-BD F i--ll)§l'.J;,....,--,

2" 1/2" / RGL-1 10526A-BD s

RGL-1 DRAIN

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2" C@:]11o------1 RGI -l XPS-5032-BD VENT RGL-1

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10534B-BD 2"

RGL-1

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RGL-1 10525B-BD

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RGL-1 RGL-1 4715-HR-BD 10526B-BD 1/2"'

0 RGL-1

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I RGL-1 4717-HR-BD RGL-1 10527-BD RGL-1

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RGL-1 IFM-4 719-BD

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10529B-B0 DRAIN STEAM GENERATOR XSG-2A-RC 2"

RO -15 502A-BD STEAM GENERATOR XSG-2B-RC

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NOTE 1 SET Ill 135'F 1 '(1/

STEAM GENERATOR XSG-2C-RC ROo-15 5278-BD 2

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14"'

125 40 125 <1%

60 JJW PLS 3

1185 125 1304 600 <1%

1480 EJA KL 2

1185 125 1304 600 <lY.

1480 EJA KL I

1185 600 1304 600 <1%

148111 EJA KL

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PSIG OF PSIG OF DURA.

HY* BY CHKO REMARKS NORMAL UPSET ORO DESIGN DATA 1/4 11 ::: 1'*0 11 0'

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1" 2"

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RGh-2 519A-BD RGH-2 XHE-13A-BD2 " >--

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ROb-45

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ROb-45 10512-BD 2"

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NOTE 1

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SUMP ROb-9 ~~

CO lPT-4707A-HR-BD ROb-64 537-BD '--

RGH-2 XHE-13B-BDI RGH-2 I

XHE-138-B02 PRT-RNn-63 503B-BD 2A NOTE 2

csv PTR-RNn-63 503C-BD ROb-9 IFT-470 B-HR2-BD ROb-9 ROb-9 10500-BD VENT r
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VENT r::,

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IFT-4 702C*HR2-BD 3/4" ROb-'l b-9~

IFT-4702C-HR1-BD 0503-BD 902X 4702C

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ROb-9 MRF-21309 519C-BD

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902X 151X 2"

G,,.,.,._..__...1.~-,;"'--"'---fiB,..----I CO 151X 2"-151X MRF-20613 /

XVG-177111-BD L.C.

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ROb-9 529A-BD 3"

MRF-2111613 XVG-1771-BD

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3" R0b-64 528B-BO 3"

NOTES:

1. ALARMS LOCATED ON NUCLEAR SLOWDOWN PROCESSING PANEL (XPN111029) WITH ONE COMMON ALARM ON THE MAIN CONTROL BOARD.
2. QUALITY RELATED PER TRP-13, SECTION 9.

PIPING CONTROLLED FOR BREAK EUMINA TIDN ANALYSIS.

3. HOSE CONNECTION AVAILABLE TO SATISFY OPERA TING LICENSE CONDITION 2.C.(34).

./L-'"---- 3/4" BODY VENT 3" 4 3 MRF-20613 XVG-1772-BD Hv~

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C RDb-9 IPT-471117C-HR-BD ROb-6~

528C-BO ROb-64 \\

529C-BD /

RNo-44 525-80 3"

4" 4"

THIS IS A NUCLEAR SAFETY RELATED DOCUMENT. NO DEVIATION SHALL BE INITIATED OR PERFORMED WITHOUT PRIOR DOCUMENTATION AND WRITTEN APPROVAL FSAR Figure 10.4-13 DRAWING LEGIBILITY CLASS 1 SOUTH CAROLINA ELECTRIC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION 27 7/B/03 JMR 26 11/13/97 AVN 31 12/10/07 RHM 30 6/6/06 RHM 29 04125/06 JTS 28 7/13/04 DDJ NO.

DATE BY SCE&G CAD ENHANCED PIPING SYSTEM FLOW DIAGRAM CADD ENHANCED PER ECR-50239 REVISED PER CGSS-97-0579 REVISED PER ECR 50692A REVISED PER ECR-70878 REVISED PER ECR-70799 REVISED PER ECR-70481 REVISION STEAM GENERATOR SLOWDOWN MGR DDJ 6

LEK MGR SCE&G MGR RAT A SCANA COMPMY M/>OE MGR CCB

1.

MGR LHF MGR CCB LE CKD. BY APPROVAL

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NO SCALE TAK DESIGN ENGINEERING V. C. SUMMER NUCLEAR STATION JENl<JNSVILLE, S, C.

CHECKED LE APPROVAL

2.

DCW PJS D-302-781 31 ORAIIINO NUMBER A

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