ML22194A423

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2 to Updated Final Safety Analysis Report, Figure 10.3-1, Rev. 42, System Flow Diagram Main Steam (Nuclear)
ML22194A423
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 06/27/2022
From:
Dominion Energy South Carolina
To:
Office of Nuclear Reactor Regulation
Shared Package
ML22194A236 List: ... further results
References
22-179
Download: ML22194A423 (1)


Text

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14 SYSTEM DATA

~ 6LB c,:;.,-- X10 HR 4.273 PSIG 991 M1mmol 1092 14 0.786 951 15 0.025 1092 16 0.93 1176 17 0.93 1190 18 0.93 1205 19 0.93 1220 OF 545 557 540 557 REMARKS 100% LOAD NO LOAD WHEN IN OPERATION SEE NOTE-A SEE NOTE-A SEE NOTE-A SEE NOTE-A 13 12 NOTE:

A. FLOW LISTED lS THE ASME RATED CAPAClTY (90% ACTUAL AT 3%

ACCUMULATION) IN LB. PER HOUR WHEN THE SAFETY VALVE IS FULL OPEN AT THE HIGHEST SET SAFETY VALVE SET PRESSURE (1235 PS(G).

THE PRESSURES LISTED ARE THE INDIVIDUAL SAFETY VALVES SET PRESSURE.

11 10 TURBINE DRIVEN EFP AUTO-START SIGNAL I. 2/3 LOW-LOW LEVEL SIGNALS IN ANY 2 STEAM GENERATORS

2. UNDERVOLTAGE ON BOTH ESF BLISSES
3. AMSAC

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_______________________________________________________________ _J ALL PORTIONS OF THE MAIN STEAM PIPING WITH A WALL THICKNESS GREATER THAN,(,"TO BE HY RDSTATICALLY TESTED WITH WATER AT A MINIMUM TEMPERATURE OF 120° F. THE REMAINING PORTIONS OF THE SYSTEM MAY BE TESTED WITH WATER AT A TEMPERATURE OF 60°F.

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NOTES:

I. PIPING WITHIN THESE FLAGS IS TD MEET ALL THE REQUIREMENTS EXCEPT FDR STAMPING, OF ASME CODE SECTION TI! CLASS 2 AND IS SPECIFICALLY INCLUDED IN THE SCOPE OF SPECIFICATION SP-544-044461-000

2. 0UBLE ROOT VALVES ARE USED ON MAIN STEAM.
3. MAIN STEAM SYSTEM (NUCLEAR) IS DESIGNED IN CONFORMANCE WITH ASME BOILER & PRESSURE VESSEL CODE SECTION III 1971 AND S-73 ADDENDA.

4, ALL INSTRUMENTS WITH 400 TAG SERIES NUMBERS ARE SUPPLIED BY@

5. ALL {:> STATUS LIGHTS INDICATE BOTH OPEN &

CLOSED POSITIONS UNLESS OTHERWISE NOTED.

6. FOR HYDRAULIC CLEANING OPENINGS, SEE PHYSICAL PIPING OWG.
7. THE EMERGENCY FEEDWATER PUMP DRIVE TURBINE EXHAUST PIPING SHALL BE DESIGNED FABRICATED & INSTALLED IN ACCORDANCE WITH ASME B & PV CODE SECTION TI! CLASS 3 RULES, HOWEVER, THIS PIPING ODES NOT REQUIRE HYDROSTATIC TESTING & CODE STAMPING.

PIPING IS CLASSIFIED 2b, TECHNICAL REQUIREMENTS ARE DISCUSSED IN TRP-13,

8.. R. PER TRP-13, SECTION 8. PIPING CONTROLLED FDR BREAK ELIMINATION ANALYSIS.
9. MANUAL CONTROL CIRCUITRY FDR 2801A/B/C INTERLOCKED WITH 2869A/B/C OPEN LIMIT SWITCH CONTACT TD ENSURE 2869A/B/C FULL OPEN PRIOR TD 2801A/B/C OPENING. TRAIN A NL Y O'

a, N 5

TRAIN "A" 4"

15 4

3 2

1

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EMERGENCY CLOSURE OF MAIN STEAM ISOLATION VALVE & BYPASS VALVE I. 2/3 HI CONTAINMENT PRESSURE.

12 PLACES 3 PLACES

2. 2/3 HI STEAM FLOW WITH 2/3 LO-LO AVG. PRIMARY COOLANT TEMPERATURE.
3. MANUAL -CONTROL ROOM.(A TRAIN HAS INDIVIDUAL SW PER VALVE &

B TRAIN HAS COMMON S.W. FOR 3 VALVES.

4.2/3 LOW STEAM PRESSURE.

HOR."A' MS ISOLATION VALVE RE -OPEN SIGNAL MS ISOLATION VALVE TEST CLOSE SIGNAL G.A.I. owe. 808-001 TO CONTROL & PROTECTION LOGIC @ OWGS, 1080932 &

108D837 27 PLACES OPEN LIMIT SWITCH ACTUATOR WILL ISOLATE BO. SEE B-208-009.

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(12 PLACES)

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X en NUCLEAR SAFETY RELATED DOCUMENT, NO DEVIATION SHALL BE INITIATED OR PERFORMED WITHOUT PRIOR DOCUMENTATION ANO WRITTEN APPROVAL ESSENTIAL FSAR FIGURE 10.3---1 SOUTH CAROLINA ELECTRIC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION PIPING SYSTEM FLOW DIAGRAM MAIN STEAM (NUCLEAR)

DESIGN ENGINEERING V. C. SUMl.4ER NUCLEi'R STATION JENKINSVILLE S. C.

MADE CHECKED LE APPROVJt..

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41 03/1812010 CMS REVISED PER ECR-72666 chk GFK RHM MGR

3.

JEW 40 00/07117 JMR REVISED PER ECR-50828 RHM NIA D-302-011 42 LE NO.

DATE BY REVISION CK. BY APPROVAL DRAWING NUij8ER SHT. NUMBER REV A

B C

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