ML24191A212

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Final Safety Analysis Report Rev. OL-27 and Technical Specification Bases Rev. 25, Chapter 5, Figures
ML24191A212
Person / Time
Site: Callaway Ameren icon.png
Issue date: 05/06/2024
From:
Ameren Missouri, Union Electric Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML24191A265 List: ... further results
References
ULNRC-06877
Download: ML24191A212 (1)


Text

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DATE DRAWN 22 40198 RLW CHKD. SUPV, APPD.

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DATE DRAWN 23 12229 RLW CHKD. SUPV. APPD.

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1. DRILLED RESTRICTION 3/8 11 IN DIAMETER. POINT AT WHICH QUALITY GROUP CLASSIFICATION IS CHANGED FROM "A" TO "B".
2. SEE WESTINGHOUSE DRAWING 8756037 SHT. 7.
3. SEE WESTINGHOUSE DRAWING 8756037 SHT. 8.
4. SEE WESTINGHOUSE DRAWING 8756037 SHT. 9.
5. SEE WESTINGHOUSE DRAWING 8756037 SHT. 10.
6. DETAILS OF REACTOR COOLANT PUMP MOTOR COOLING, SEAL WATER INJECTION, AND INSTRUMENTATION AND CONTROLS ARE SHOWN ON M-22BB03.
7. RTD STRAPPED TO LINE.
8. TYGON HOSE TO BE INSTALLED AT THESE CONNECTIONS TO VENT PRESSURIZER DURING DRAINING AND FILLING.
9. DELETED.
10. REFERENCE WESTINGHOUSE DRAWINGS 1145E01 SHT. 1, 1145E01 SHT. 2, AND 1145E01 SHT. 3.

11

  • DELETED.

~HB-37-BCD-2"

12. FOR P & ID LEGEND AND SYMBOLS SEE DRAWINGS M-220101 THRU M-220104.

2 1 3.

1 4.

DETAILS OF STEAM GENERATOR SECONDARY SIDE PIPING AND CONTROLS ARE PROVIDED ON M-22AB01, M-22AE02, ANO M-22BM01.

A DIRECT READING DIGITAL PRESSURE INDICATOR IS CONNECTED TO THIS LINE AT THE NUCLEAR SAMPLE STATION, DOWN STREAM OF THE SAMPLE COOLER, FOR PURPOSES OF CALIBRATING THE PRESSURIZER PRESSURE INSTRUMENT CHANNELS.

1 5. DELETED.

1 5. PRESSURIZER SAFETY & RELIEF VALVE DISCHARGE LINE IS ANALYZED SO AS TO ASSURE THE INTEGRITY OF THE PRESSURIZER RELIEF TANK DURING & FOLLOWING AN SSE.

17. SG-AR-7: PEAK RECORDING ACCELEROMETER, TO BE MOUNTED ON SURFACE OF HORIZONTAL PIPE SECTION.

1 8.

1 9.

SEE WESTINGHOUSE DWG. 7250064 SHT. 6, ANNUNCIATOR IPAH-4551 IS PROVIDED FOR HI PRESSURE PORV OPEN.

MCB PZR ASTS (AUXILIARY SHUTDOWN TRANSFER SIGNAL) IS INITIATED AT RP118B BY RP-HIS-3 WHICH TRANSFERS CONTROL TO THE AUXILIARY SHUTDOWN PANEL WHILE ISOLATING THE MAIN CONTROL BOARD CONTROLS AND INDICATION.

20. PRT IS A SEISMICALLY QUALIFIED ASME SECTION VIII COMPONENT.
21.

THE INTERNALS OF THIS VALVE HAVE BEEN REMOVED AND REPLACED WI TH A STAINLESS STEEL PLUG. THE VALVE HAS BEEN TRANSFORMED TO A go* ELBOW.

22. DELETED.
23. DELETED.
24. DELETED.
25. THE INTERNALS OF VALVE BB8949A HAVE BEEN REMOVED:

6" CHECK VALVE BODY REMAINS IN SYSTEM.

AS-BUILT CLASS 1 DRAWN

( DATE I N/A

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(°F) gpm (1) lb/hr (2)

Volume 1

Reactor coolant 2,235.0 618.8 108,781 36.2040 2

Reactor coolant 2,233.7 618.8 108,781 36.2040 3

Reactor coolant 2,189.7 557.7 97,452 36.2040 4

Reactor coolant 2,186.1 557.7 97,453 36.2040 5

Reactor coolant 2,282.3 558.0 97,368 36.2065 6

Reactor coolant 2,281.0 558.0 97,361 36.2040 10-15 Reactor coolant See Loop #1 Specifications 19-24 Reactor coolant See Loop #1 Specifications 28-33 Reactor coolant See Loop #1 Specifications 37 Reactor coolant 2,282.3 558.0 1.0 0.00037 38 Reactor coolant 2,282.3 558.0 1.0 0.00037 39 Reactor coolant 2,282.3 558.0 2.0 0.00074

CALLAWAY - SP NOTES TO FIGURE 5.1-2 (Sheet 2)

Rev. OL-14 12/04 (1) At the conditions specified.

(2) X 10.

Pressure Temperature Flow Location Fluid (psig)

(°F) gpm (1) lb/hr (2)

Volume 40 Steam 2,235.0 652.7 720 41 Reactor coolant 2,235.0 652.7 1,080 42 Reactor coolant 2,235.0 652.7 2.5 0.0007 43 Reactor coolant 2,235.0 652.7 2.5 0.0007 44 Steam 2,235.0 652.7 0

0 45 Reactor coolant 2,235.0 300 0

0 Minimize 46 N2 3.0 120 0

0 47 Reactor coolant 2,235.0 300 0

0 Minimize 48 N2 3.0 120 0

0 49 N2 3.0 120 0

0 50 N2 3.0 120 450 51 Pressurizer relief tank water 3.0 120 1,350 52 Steam/H2 2,235.0 559 0

0 53 Reactor coolant 3.0 120 0

0 54 Reactor coolant 50 170 0

0 6

NOTES:

7 eves EMERGENCY LETDOWN RMWSRMW WPS (L)

RCDT HX WPS(L)

RCDT PUMP CONTAINMENT SUMP STEAM GENERATOR LOOP 2 PUMP LOOP 1 THIS DIAGRAM IS A SIMPLIFICATION OF THE SYSTEM INTENDED TO FACILIATE THE UNDERSTANDING OF THE PROCESS. FOR DETAILS OF THE PIPING, VALVES, INSTRUMENTATION, ETC. REFER TO THE ENGINEERING eves CHARGING FLOW DIAGRAM. REFER TO PROCESS FLOW DIAGRAM TABLES FOR THE CONDITIONS AT EACH NUMBERED POINT.

SIS Sl AND RHR PMPS SIS Sl PUMPS RHRS PUMP 1 SIS Sl AND RHR PMPS SIS Bl SIS Sl PUMPS RHflS PUMP 2 STEAM GENERATOR STEAM GENERATOR LOOP 3 eves LETDOWN REACTOR COOLANT PUMP 31 LOOP4 (SEE NOTES ON THE FOLLOWING PAGES)

CALLAWAY PLANT FIGURE 5.1-2 REACTOR COOLANT SYSTEM PROCESS FLOW DIAGRAM 000223-1 REVOL-8 11/95

0.....

8" - 300#

W/NECK R. F. FLANGE 6" - 900#

LG/NECK R.F. FLANGE 22" DIA.

21 1/8" 21 1/8"

r:

! I !

I

-16" VENTSTACK 0

N

+

8 3/4" 6" EXTRUDED OUTLET

-28" (28.38 O.D.) Rev. OL-0 6/86 CALLAWAY PLANT FIGURE 5.2*1 INSTALLATION DETAIL FOR THE MAIN STEAM PRESSURE RELIEF DEVICES

CALLAWAY PLANT FIGURE 5.2 - 2 PRIMARY COOLANT LEAK DETECTION RESPONSE TIME

  • REV OL-26 11/22

--=-

J FIGURE 5.3-l REACTOR VESSEL

BOLTS OR STUDS AND NUTS REV. OL-9 5/97 CALLAWAY PLANT FIGURE 5.4-1 REACTOR COOLANT CONTROLLED LEAKAGE PUMP

600 500 Q)

Ql 400 Ll..

r tl) c.. z

"'C 300 s::

ra

"'C ra Q)

r rc - 200 0

1-100 0

14113-5 Required Net Positive Suction Head 0

10 20 30 40 50 60 70 80 90 100 110 120 130 140 Flow (Thousands of GPM)

CALLAWAY PLANT FIGURE 5.4-2 Rev. OL-0 6/86 REACTOR COOLANT PUMP ESTIMATED PERFORMANCE CHARACTERISTIC

Pressure Tap Sampling Tap Primary Coolant Inlet Nozzle~

Steam Outlet Nozzle

/

Secondary Manway Level Tap Feedwater Nozzle


LeveiTap

/

Inspection Port (typ.)

6 Handholes Primary Manway REV. OL-15 5/06 CALLAWAY PLANT FIGURE 5.4-3 Areva Model 73/19T Steam Generator

CALLAWAY -

SP Figure 5.4-4 Deleted REV. OL-~15 5/06

CALLAWAY -

SP Figure 5.4-5 Deleted REV. OL-15 5/06

CALLAWAY -

SP Figure 5.4-6 Deleted REV. OL-15 5/06

IIICSIGTL.ai LOIP l r

<lllt~T 1

UG r

<liltS HOT L£G Ull'.

IICQ.IIIT-

~

t _.,_TUP I 1 t 9 ll.JNT.\\INIIO(f~

L- --

_ ___J

'IICI'""' £ I I

/'CSs~*

<<';I';()<<;F'I.JIPS

  • '-~......l-4...

o<JTE

~SHOTL£C~

~*

D 1

TI-llS OlofiQIMIII IS A SUI'ltflt.t.TUJII f7 M

,S'Tal,,,._, 'm f.fiCILITATI flo.,._,....,.!>>' lMl "'-EEl

.III'TAIU OF T11[ l"tl"lllli. WLWS. I~ATI

... £TC.et l1) M Dll1.0.1115 FUJI 01~ -- l'D,._.,.,. 01-r-.rs F1:Jt H. t'OGITICIIlT UD4 ~

(SEE NOTES ON THE FOLLOWING PAGES)

CALLAWAY PLANT FIGURE 5.4-8 RESIDUAL PROCESS HEAT REMOVAL SYSTEM FLOW DIAGRAM Rev. OL-0, 6/86

CALLAWAY - SP Rev. OL-14 12/04 NOTES TO FIGURE 5.4-8 MODES OF OPERATION MODE A - INITIATION OF RHR OPERATION When the reactor coolant temperature and pressure are reduced below approximately 350°F and 400 psig, approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after reactor shutdown, the second phase of plant cooldown starts with the RHRS being placed in operation. Before starting the pumps, the inlet isolation valves are opened, the heat exchanger flow control valves are set at minimum flow, and the outlet valves are verified open. The automatic miniflow valves are open and remain so until the pump flow exceeds approximately 1,650 gpm (at 300°F) at which time they close. Should the pump flow drop below approximately 816 gpm (at 300°F), the miniflow valves open automatically.

Startup of the RHRS includes a warmup period during which time reactor coolant flow through the heat exchangers is limited to minimize thermal shock on the RCS. The rate of heat removal from the reactor coolant is controlled manually by regulating the reactor coolant flow through the residual heat exchangers. The total flow is regulated automatically by control valves in the heat exchanger bypass line to maintain a constant total flow. The cooldown rate is limited to 100°F/hr, based on equipment stress limits and a 120°F maximum component cooling water temperature at the RHR heat exchanger inlet.

MODE B - END CONDITIONS OF A NORMAL COOLDOWN This situation characterizes most of the RHRS operation. As the reactor coolant temperature decreases, the flow through the residual heat exchanger is increased until all of the flow is directed through the heat exchanger to obtain maximum cooling.

Note:

For the safeguards functions performed by the RHRS, refer to Section 6.3, ECCS.

CALLAWAY - SP NOTES TO FIGURE 5.4-8 (Sheet 2)

Rev. OL-14 12/04 VALVE ALIGNMENT CHART O = Open C = Closed P = Partially Open Valve No.

Operational Mode A

B 2

C C

3 C

C 10 O

O 11 O

O 12 C

C 13 C

C 14 C

C 15 C

C 16 P

C 17 P

C 18 P

O 19 P

O 20 C

C 21 C

C 22 O

O 23 O

O 24 O

O 26 O

O

CALLAWAY - SP NOTES TO FIGURE 5.4-8 (Sheet 3)

Rev. OL-14 12/04 MODE A - INITIATION OF RHR OPERATION (a) At reference conditions 350°F and 400 psig Pressure Temperature Flow Location Fluid (psig)

(F)

(gpm) (a)

(lb/hr) 24 Reactor coolant 400 350 3,800 1.60 x 106 25 407 350 3,800 1.60 x 106 26 542 350 3,800 1.60 x 106 27 541 350 1,259 0.56 x 106 31 539 140 1,259 0.56 x 106 29 496 350 2,541 1.13 x 106 32 496 280 3,800 1.69 x 106 28 480 280 3,690 1.64 x 106 19 Loop 4 404 280 1,992 0.885 x 106 19 Loop 3 419 280 1,698 0.755 x 106 34 400 350 3,800 1.69 x 106 35 407 350 3,800 1.69 x 106 36 542 350 3,800 1.69 x 106 37 541 350 1,259 0.56 x 106 41 539 140 1,259 0.56 x 106 39 496 350 2,541 1.13 x 106 42 496 280 3,800 1.69 x 106 38 479 280 3,910 1.74 x 106 20 Loop 1 404 280 1,955 0.87 x 106 20 Loop 2 404 280 1,955 0.87 x 106

CALLAWAY - SP NOTES TO FIGURE 5.4-8 (Sheet 4)

Rev. OL-14 12/04 MODE B - END CONDITIONS OF A NORMAL COOLDOWN (a) At reference conditions 140°F and 0 psig.

Pressure Temperature Flow Location Fluid (psig)

(F)

(gpm) (a)

(lb/hr) 24 Reactor coolant 0

140 3,800 1.87 x 106 25 7

140 3,800 1.87 x 106 26 156 140 3,800 1.87 x 106 27 149 140 3,800 1.87 x 106 31 129 120 3,800 1.87 x 106 29 93 120 0

0 32 93 120 3,800 1.87 x 106 28 75 120 3,800 1.87 x 106 19 2

120 1,900 0.935 x 106 34 0

140 3,800 1.87 x 106 35 7

140 3,800 1.87 x 106 36 156 140 3,800 1.87 x 106 37 149 140 3,800 1.87 x 106 41 129 120 3,800 1.87 x 106 39 93 120 0

0 42 93 120 3,800 1.87 x 106 38 75 120 3,800 1.87 x 106 20 2

120 1,900 0.935 x 106

350 LL.

0 -

Ql 300

s IV

~ 250 Q. E

~ 200 c:

~ 150 0 u 0 100

~

IV Ql a:

\\

\\

4 8

12 16 Time After Reactor Shutdown (Hours)

I 20 CALLAWAY PLANT FIGURE SA-O NORMAL RESIDUAL HE'R' REMOVAL COOLDOWN REV. 1e 8114

350 0 -

~ 300

~

Ill

~ 250

a.

E

~ 200

.... c Ill -8 150 u

~ 100 I

Ill Ql 4

a::

8

\\

\\

I I

I I

12 16 20 24 Time After Reactor Shutdown (Hours)

I I

28 32 CALLAWAY PLANT FIGURE 5.4-10 SINGLE RESIDUAL HEAT REMOVAL TRAIN COOLDOWN REV.16 9/14

HEATER SUPPORT PLATE SPRAY NOZZLE SAFETY NOZZLE UPPER HEAD INSTRUMENTATION NOZZLE LIFTING TRUNNION SHELL LOWER HEAD INSTRUMENTATION NOZZLE ELECTRICAL HEATER SUPPORT SKIRT SURGE NOZZLE Rev. OL-0 6/86 CALLAWAY PLANT FIGURE 5.4-ll PRESSURIZER

PRESSURIZER RELIEF VALVE DISCHARGE LINE CONNECTION RHR SUCTION RELIEF VALVE DISCHARGE LINE CONNECTION VESSEL SUPPORT SPRAY WATER INLET VENT CONNECTION SAFETY HEADS SPARGER PIPE


.,r-

  • 1

)1\\_--

1 * \\

_../.

~

DRAIN CONNECTION VESSEL SUPPORT CALLAWAY PLANT FIGURE 5.4-12 PRESSURIZER RELIEF TANK REV. 1 3/09

l DET PLAN VIEW G_ REACTOR DETAIL oD REACTOR VESSEL SECTION RI=.ACTOR VI:SSEL SUPPORT

(~ RFQ'D) 1299~1 SECTION B @

CALLAWAY PLANT FIGURE 5.4-13 Rev. OL-0 6/86 REACTOR VESSEL SUPPORTS

LIMIT STOP 13,557-34 UPPER LATERAL SUPPORT LOWER LATERAL SUPPORT WIDE FLANGE COLUMNS DIRECTION OF THERMAL EXPANSION

CRO:S-OVER LEG rCOLD LEG I

TIE RODS WIDE FLANGE COLUMNS 12999 CALLAWAY PLANT FIGURE 5.4-15 Rev. OL-0 6/86 REACTOR COOLANT PUMP SUPPORT~

  • r,

PLAN


SUPPORT SKIRT SUPPORT CONCRETE SLAB

~ ANCHOR BOLTS l.

.J AT SUPPORT SKIRT FRAMING SUPPORT FRAMING 1,.

I r

/~

( \\1.---- PRESSURIZER

~

T l

1 SECTION@

SHIELD WALL BOLT

( TYP.)

CALLAWAY PLANT FIGURE 5.4-16 Rev. OL-0 6/86 REACTOR BUILDING INTERNALS PRESSURIZER SUPPORTS

PRESSURIZER SKIRT BEARING PLATE GROUT CALLAWAY PLANT FIGURE 5.4-17 38lf2-5 Rev. OL-0 6/86 PRESSURIZER SUPPORTS

tl R.C. PUMP CROSSOVER PIPE tl S.G. VERT.

RUN PIPE

~--SUPPORT DEACTIVATED BY REMOVAL OF SHIM PLATES

( CMP 03-1 011 )

CALLAWAY PLANT FIGURE 5.4-18 CROSSOVER LEG RES1RAINT REV. OL-15 5/06

CALLAWAY -

SP Figure 5.4-19 Deleted REV. OL-15 5/06

SADDLE AND SHIMS REMOVED _____

___J CALLAWAY PLANT FIGURE 5.4-20 HOT LEG RESTRAINT REV. OL-15 5/06

(0) £<;;88£0-::>

T I

I t tri.. "x5"x2'-4"(SHIM)

M.A'tH AS REQ'D IN FIELD-.... -----~

TY 8

t REACTOR 111'-o:

--+

1 i-o*

PLAN AT EL 2014'-6'

~

TYPCB

\\'

/~***3LG SHEAR I '

STUDS AT 300 (TYP) 0 SEC: CHART FOR 0 q_:

COLD GAPS OF SHIMS 1.0 J......l..:

IU' I 1'-431132" R (REF)

~~~~~~1-o,.l~~~~t~l§ J----*--H~~tlt-+--.

INSULATION (SEE OWG M-05002)

TYPICAL COLD PIPE SECTION A

SCALI 1"*,.-0" I. 1....

'*-2x 1~ xO *2 STOP Sli.R AT END 7

~{'J CJ)

  • a

-~

..N a
,_N a

b

-~

..... N

/

TACK WELD 1i-1 "TO q; 0 a

  • a

-,0

.J.i:{.IQ.£...

~~A-~TQtL

~**x 3 LG SHEAR STUDS AT 30° (T'rP) 3'-3~' TO WP

~B"x2" COMPRESSIBLE MATERIAL (ROOOFOAM IT BY GRACE & CO, OR I EQUAL) (BY OWNER) ;.j

[

f_,:}o"x3"x1'-8"l~OT PIPE) l, (SHIM) MACH AS tfi8 *;*3"x2'-4"(C0LD IPE)j REQ'D IN FIELD 5

4 r

5/8~ ~ ~~~:: GAP(COLD POSITION)

I HOf PIPE ONLY

£1}4.< ~'x1'-10"1HOT PIPE)

It 1l-.4'x 4'x 2-6(COLD PIPE)


~~~to 25oe'!H01 PIPES) 23132'CCOLD PIPES) 3 t Rf:ACTOR BLDG

~---------N-O T_E_S----------~G TYP DETAIL 6

SSALE1"~1'-C1' 1

ALL DIMENSIONS GIVEN ARE IN COLD POSITION UN 0 2

MATERIAL FOR HU 1"' THICK COLLAR RING SHALL 8E ASTM A!>lfl J

THE 1" THICK COLLAR RING AND BUILT UP FILLER MEMBERS SHALL BEPOSTWELDHEATTAEATED 4

SURFACES WHICH RECEIVE SHIMS ANDIOA BEARING SHALL BE MACHINED TO THE DESIGN CONTOUR 5

SHIM AREA AS INDICATED ON THE DRAWING SHALL BE ~ROVIDED WITH NOT LESS THAN 50'110 OF THE BEARING AREA 6

SHIM PlATES SHALL BE SHOP TACK WELDED TO THE ~UIL T UP FILLfA MEMBER AFTER PAOPfAL Y ALIGNED 7

THE RADIAL LOCATION tO A INSIDE RADIUS AT ANY POINT Of THE 1 THICK COLLAR RING SHALL NOT VARY FADM THE DESIGN RADIUS BY MORE THAN 1/B 8

RESTRAINT ASSEMBUH SHALL BE SHOP PRE ASSEMBLED TO INSURE PROPER ALIGNMENT AND DELIVER TO SITE AS ONE UNIT FOR EACH 9

THE MAXIMUM ALLOWABLE GM AT THE SHIM OR BEARING SURFACES SHALL B~ 1/1~" SHIMS MAY 8E ADDED BETWEEN THE OUTSIDE FACE Of THE INNER RING AND THE INSIDE FACE OF THE SPOKE TO MH_T THIS REQUIREMENT 10 THE FIELD MACHINED SHIMS SHJ.LL ACCOUNT FOR THE AS BUILT DIMENSIONS OF THE RESTRAINT RING THE INSIDE FACE OF THE INNER RING AND THE OUTSIDE DIAMETER OF TH( HOT AND COLD PIPES AT EACH LOCATION 12 THE OVTfR ~lNG SHALL 8E PAE5SEO AGAIN!.T THE COMPRESSII!oLE MATERIAL AS MUCH AS POSSIBLE TO PRE~ENl LEAKAGE OF u

THE AS*8UILT C0\\.0 GAP AT SHIM.J MUST 8[.

AI 5MALI ER THAN lOR EOUAl TO) THE AS*BUIL T COLO GAP AT SNIM *2 B) SMALLER THAN (OR [QUAL TO) THE AS*8VIlf COlD GAP AT SHIM... PLUS

)J\\6".

REFERENCE DRAWINGS C-OL2930 REACTOR BUILDING LINER PLATE REACTOR CAVITY WALL MATERIAL RESPONSIBILITY 1 STEEL TO BE FURNISHED UNDER SPEC 10466-C202 Rev. OL-0 6/86 CALLAWAY PLANT FIGURE 5.4-21 HOT AND COLD LEG LATERAL RESTRAINTS (C-038853(01-41 2

1 e'ov 1~

t;** SIZE F

E D

c B

~-'

A