ML20212P534
Text
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O Rev. 57 07/16/86 (HKC 01/22/87)
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Document Sectica NFORM AT!ON ONL
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OPERATING PROCEDURE OP-209 PLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 PLANT COOLDOWN THIS PROCEDURE ADDRESSES SAFETT RELATED COMPONENTS APPROVED BY:
Responsible Section Superintendent Super isor
/2-w Da AS f$
INTERPRETATION CONTACT:
Nuclear Operations Superintendent 8703160144 870305 PDR ADOCK 05000302 P
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t 1.0 PURPOSE 1.1 This procedure provides the necessary steps to take the plant from HOT STAN08Y to COLD SHUTDOWN.
Mode Section Cooldown With Both Steam Generators 6.0 Cooldown With DH System 7.0 Cooldown With One Steam Generator 8.0 Alternate Methods for RCS Degas 9.0 1.2 Procedure cover sheet and applicable section(s) per-formed constitute a complete procedure for record pur-poses.
1.3 contains information whien will ne used to i52 generate a situation, specific cooldown procedure, i
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l following a fi re in the Control Room or Caole i,
l Spreading Room.
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2.0 DESCRIPTION
j 2.1 RC TEMPERATURE CONTROL i
l 2.1.1 Mode 3 - RC Temperature > 280*F j
Cooldown will be performed using the steam generators.
1 2.1.2 Modes 4, 5. and 6 - RC Temperature < 280*F Cooldow, will be perfermed using the decay heat re -
moval (oho' system.
2.2 RC PRESSURE CONTROL Reactor coolant (RC) pressure, during cooldown, will be controlled with the pressurizer spray and/or pres-surizer heaters.
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3.0 REFERENCES
l 3.1 09-302, RC Pump Operation 3.2 OP-402, Makeup and Purification System OP-209 Rev.
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HKC 11/19/85 3.3 OP-404, Decay Heat Removal System 3.4 OP-502, Control Rod Drive System 3.5 OP-605, Feedwater System 3.6 OP-304, Soluble Poison Concentration. Control 3.7 OP-414, Nitrogen and Hydrogen Systems 3.8 OP-604, circulating Water System 3.9 OP-608, OTSG Secondary Fill, Drain, and Layup 3.10 OP-401, Core Flooding System 3.11 OP-607, Condenser Vacuum System 3.12 OP-603, Condensate System 3.13 MP-108, Control Rod Drive Handling.
3.14 SP-422, RC System Heatup and Cooldown Surveillance 3.15 SP-435, Valve Testing During cold Shutdown 3.16 OP-606, Auxiliary Steam System 3.17 Westinghouse Instruction Book for Steam Turbine, 1250-C737 3.18 OP-103A, Operating Curves 3.19 OP-103B, Heatup/Cooldown Curves 3.20 AP-990, Shutdown from outside Control Room 3.21 SP-402, Core Flooding Isolation Valves Alarms Actuation 3.22 SP-113, Power Range Nuclear Instrument Calibration 3.23 SP-296, Documenting Allowable Operating Transient Cycles 3.24 SP-403, Decay Heat Removal System Valves Closure and Interlock Verification 3.25 SP-405, Core Flooding System Check Valve Operation Demonstration 3.26 SP-412, ECCS and Containment Spray System Leak Rate Test 3.27 SP-418, Main Feed Pump Trip Test 3.28 SP-441, Unit Shutdown Surveillance Plan 3.29 SP-603, Decay Heat / Core Flood Check Valve Leak Testing 3.30 OP-605, Feedwater System OP-209 Rev. 51r 1
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4.0 LIMITS AND PRECAUTIONS (TS) 4.1 The cooldown rate of tne RCS, including the pressurizer, shall not exceed the following limits:
RCS Temoerature (T)
Cooldown Rate RCS Temoerature Change in Any One Hour Period T > 270*F 100 F/HR 100 F 270*F > T > 170*F 50*F/HR 50 F 170*F > T 10*F/HR 10 e 1
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OP-209 Rev.
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4 HKC 01/22/87 (TS) 4.2 The pressurizer spray shall not be used if the AT between the RCS and pressurizer is > 410*F.
4.3 Maintain RC pressure and temperature within the limits of Curves 6 and 7 of OP-103B, Heatup/Cooldown Curves 4.4 The average shell temperature of the once-through steam genera-tor (OTSG) shall not exceed 60*F above or below RC temperature.
4.5 No more than three (3) RC pumps (RCp's) may be operated below 500*F.
4.6 Operation of the RCp's at system pressure of < 400 psig should 1
be minimized.
Operation at this low pressure will reduce One life of the seals.
4.7 System piping shall be operable to the extent of estaclasning a flow path from the boric acid storage tank (BAST) Ar.d the borated water storage tank (BWST) to the RCS whenever One RC temperature is > 200*F.
Either of the above flow paths shall be operable when the RC temperature is 1 200*F.
4.8 All subcritical boron changes in the RCS shall be verified.
4.3 The boron concentration in the RCS shall not be reduced unless at least one (1) RCp or one (1) (Decay Heat pump) is cir::u-lating RC at a flow rate 1 2700 gpm.
4.10 Following a significant change in boron concentration of the RC, pressurizer spray should be operated to equal:::e tn-concentration in the RC loops and pressurizer.
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' ar OP-209 Rev. 5 7 5
page 3 E Vms*vWf.h (, _%K %_-Ev,==C a:~a r + r72 T~~ ~~~'
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== - - O HKC 01/22/87 4.11 If the count rate increases during a boron concentra-tion increase, the operation shall be stopped imme-diately and suspended until a satisfactory evaluation of the situation has been made.
4.12 Safety Rod Groups 1 thru 4 should be at their fully withdrawn position whenever reactivity is being changed by a reduction in boren, action of. axial power shaping rods (ApSR's), or full length control bank rods.
4.13 The control rod drives (CRD's) will not be operated QE tripped unless the RC pressure and temperature are above slope "J" of Curve 6 of Op-103B, Heatup/Caoldown Curves.
Additionally, CRC's shall not be energized without applying nuclear service closed cycle cooling (SW) to them, 4.14 When RC temperature is ( 280'F, lock out and red tag to the NSS the breakers for the non-operating makeup pumps (MUp's) and high pressure injection (HpI) valves MUV-23, 24, 25, and 26 This will prevent overpres-surization of the RCS and DH system upon inadvertent actuation of HpI.
4.15 At 700 psig or less RCS pressure, the core fleed tank a
(CFT) block valves CTV-5 and CFV-6 will be shut and 4
l the breakers red tagged to the NSS in the ' Lock Reset
- position if required to prevent tanks from discharging, c4 Op-209 Rev. "5 7'I page 4
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HKC 11/19/85 4.16 Continuous blowdown of the secondary side of the steam generators via sample line is required whenever reactor power is ( 15% and RC temperature is > 250*F.
.4.17 The steam generators aust be filled to the 97 to 99%
level on the operate range instrumentation whenever the RC temperature is < 200'F.
4.18 The maximum fill rate of the secondary side of the steam generators is 2.47 x 105 lbs/hr.
4.19 Continuous feedwater (FW) flow to the steam generators via the manual byass valves (FWV-155 and 156) is required whenever reactor power is < SS. and RC temper-ature is > 180*F.
These valves may be closed when F*4 is no longer required.
4.20 The temperature difference between the RC and/or pres-surizer fluid and the injected nitrogen should not exceed 100*F.
4.21 When the DH system is in operation, do not close DHV-3, 4, or 41 unless the RCP's are available to cool the core.
4.22 If pressurizer level falls below the minimum level of curve 5 of Op-103A, Operating Curves, immediately increase makeup flow to regain level.
4.23 Maintain at least a 20*F subcooling margin while RCS pressure is > 1500 psig and 50*F subcooling margin while RCS pressure is ( 1500 psig in all regions of the RCS, except the pressurizer, during plant cool-down.
Op-209 Rev. 5 7 I
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4.24 Minimum RC makeup flow shall be > 15 gpm when above 200'F RCS ternperature.
4.25 Refer to AP-990 and Enclosure 3
for guidance
{S2 concerning cooldown following a fire in the Control l
Room or Cable Spreading Room.
l 5.0 SET POINTS 5.1 Pressurizer Hign-High Level Alarm:
275-in. water 5.2 oressurizer Low-Low Level Interlock: 40-i n, water 5.3 Pressurizer spray valve RCV-1 opens at 2205 psig.
5.4 Pressurizer Heater Bank Set Pqints:
A*
B*
C*
O E
On 2135 2135 2147 2120 2105 as';
Off 2155 2155 2155 2140 2125 ps'j
- Modulating Control Set Points:
2155 psig 5.5 Letdown Block Ori' ice Flow (Normal): 45 gpm 5.6 Letdown Temperature Hign Alarm:
130*F 5.7 Letdown Pressure Alarm Hign:
145 osig 5.8 RCP Seal Flow Low Alarm:
3 gpm 5.9 MUT High Alarm: 86-i n.
Low:
55-in.
Low-low level switch set at 18-i n..
This positions three-way valve flow to makeup tank (MUT).
5.10 MUT Pressure High Alarm:
40 asig 5.11 Makeup Filter aP Hign Alarm: 25 psi; 5.12 Letdown Temperature Hign Temperature Interlock:
135'F; closes MVV-49F
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09-209 R e v, d,,w Page 3 l
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PROCEDURE 6.0 C00LOOWN WITH BOTH STEAM GENERATORS Initials 6.1 INITIAL CONDITIONS 6.1.1 RCS is at HOT STANOBY (Mode 3).
6.1.2 At least one- (1) RCP is running in each loop.
6.1.3 Calculations to compensate for contraction and cora-tion have been completed per OP-304, Soluole Poison Concentration Control.
6.1.4 Safety Rod Group 1 witndrawn to "Out-Limit".
6.1.5 Notify ChemRad to sample the RCS and tne pressurizer water space for activity, dissolvec nycrogen, anc scron.
6.1.6 One (1) main feedwater pump (MFWP) is in coeotion.
6.1.7 Nitrogen system is operstle per OP-414, Nitrogen and Hydrogen Systems.
6.1.8 Startup FW bypass valves (FWV-155 and 166) are coen, allowing a continuous feed to botn OTSG's.
6.1.9 Continuous blowdown of steam generators is in progress enrougn lower tube sneet drains via sample sink,.
6.1.10 Veri fy auxiliary steam is available and aligned cer Section 8.0 of OP-606, Auxiliary Steam System.
6.2 COOLDOWN If this outage is planned to exceed 48 nrs, in cold snutdown, determine the last time SP-435, Valve Test.
Ing During Cold Shutdewn, was completed.
If the pro-OP-209 Rev.
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Initials cedure has not been performed in the previous three (3) sonths, start performing SP-435, Valve Testing During Cold Shutdown.
If the procedure was partially completed, start with those valves not tested during the Surveillance Procedure's performance.
NOTE:
The outage d.212 D.21 have to be extended solely for the complete performance of SP-435, valve Testing During Cold Shutdewn, but attempt as i
many valve tests as possible.
If this outage is a scheduled refueling Outage.
ne SP-410, Valve Testing During Refueling Outages, Jnall be performed.
As the unit is being cooled down, per this procedure, MUV-60 and MUV-72 check valves should be tested (partially stroked) following Step 9.15, and its substeps, of EP-410.
Should the NSS choose not to perform this test at this time, then the test shall be performed during heatup exercises (OP-202) fcilowing the refueling outage.
6.2.1 Commence RCS cooldown surveillance per SP-422. RC System Heatup and Cooldown Surveillance, and SP-44' Unit Shutdown Surveillance Plan, and continue until cooldown is completed or terminated.
u OP-209 Rev. $ y 1
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MaintainMU'l*1evelwithinnormalrang[or55to86-in.
6.2.2 6.2.3 During cooldown when the RCS is ( $$0 psig and > 100 j$.
psig the pressurizer level is limited to 1 180*.
When l
RCS is 1 100 psig, the pressurizer level ts limited to
< 275.
I 6.2.4 Establish a flow path to makeup systes per ' Op-< 02, Makeup and Purification Syste,s.
As shrinkage occurs,,
borate to calculated value obtained in Step 6.1.3.
6.2.5 Turn pressurizer heater otC: operate pressurizer sprsy valve (RCV-14) to stay within limits of Curve 7 of a
/
op-1038 Heatup/Cooldown Curves.
6.2.6 MANUALLY operate turbine bypass or atmospheric dump steam flow to control cooldown and nonitor we range RC temperature indicator for cooldawn. Plot points on Curve 7 of op-1038 Heatup/Cooldown Curves.
6.2.7 Maintain three (3) RC ;> ump operation until the RCS' is borated for final shutdown conditions and desired cooldown rate is no longer achievable.
6.2.8 CAUTION
ZFIC MSLI (Main steam line isolation) will occur at ( 600 psig 0TSG pressure if not in bypass.
place EFIC actuation. logic in bypass when PTSG CH. A pressure is ( 725 psig by depressing push buttons for CH. S _a.
Channels A, B, C and D.
these are located on MCB and CH labeled *< 725 asi OTSG pressure EPL' Ae':uation OH.
")
Bypass'.
The push buttons will backlight she.1 bypass is in effect.
6.2.9 When RCG is between 1900 and 1650 psig, rerform the following:
f Op-209 Rov.67 Page 1
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Initials a.
Terminate cooldown and maintain RC temperature.
b.
If cooldown is to facilitate removal of the reac-tor vessel (RV) head, insert Control Rod Group 3 to its "in-limit".
n c.
Orive safety rods (Group 1) to "i n-t imi t" per JP-502, Control Rod Drive System.
d.,_. Trip reactor and depressurize tne RCS to approxi-mately 1650 psig.
e.
Reset the hign flux trip to 5% FP, per SP-113, initiate shutdown
- bypass, reset reactor trip bistables, r% et reactor trip on Diamond Panel, and raset tne "HEA Reactor Tripped Locout",
f.' 9eset reactor trip and laten and vitn: raw safety rods (Group 1) per OP-502, Control Rod Ori se Sys-tem.
1 When RC pressure is between 1700 and 1550 asig, oypass engineered safeguards (ES) channels 'A' and
-/
"B", Hp! R;-1, RC-2, and RC-3.
I 6.2.10.
When desired cooldown rate is no longer acnievable on three (3) RC pump operation, then ensure shutdown by-pass is initiated and secure the remaining RC pumo 11
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the 'B' loop, i
NOTE:
If desired SP-402, Core Flood $ystem iso 13 tion 52 Valves Alarms Actuation, may be performed in conjunction with Step 6.2.10 or 6.2.11 of tnis i
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procedure if RCS Press. > 750 psig.
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6.2.11 Contin 63 c.sidown.
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OP-209 Rev. 5 7 %
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HKC 01/22/87 Initials a.
Maintain RCS cooldown rate at:
(_
< 100*F/hr. for temperature of 550 to 270*F
< 50*F/hr. for temperature of 270 to 170*F
( 10*F/hr. for temperature of 170*F and less b.
Maintain pressurizer level at below 180-in.
c.
Maintain RCS within limits of Curve 6 of OP-103B, Heatup/Cooldown Curves.
d.
Monitor both loops That on redundant instrument s
panel and Teold wide range to ensure equal cool-4 down on each leop.
NOTE:
EFIC EFW actuation logic for loss of both MFWP's 'is automatically bypassed at 10 '.
power.
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Initials 6.2.12 When secondary steam pressure has decreased to about 250 psig, stop MFWP per OP-605, Feedwater System. Use the FW booster pump for FW supply.
NOTE:
If coming to refueling mode, perform SP-418, Main Feedwater Pump Trip Test.
6.2.13 When secondary steam pressure is 200 psig, ent.. -
ASV-5/204 are closed and open breaker it CFCP 'B Fa.3.'
5.
Red tag to $500.
Enter STS action of 3.7.1.2.
6.2.*4 Setween 300 and 600 pst; RC3 prean r+.
- y: s n :.F : i; channels
'A' and '3*
?.C-4.
.1.:- 5, 2nd.0: - s 6.2.14.'
If the plant is expected to be in COLD 311UTOCW'l f-::
hrs. or more, contact the Inservice n:pection ::3:'
Specialist to ascertain whether SP-405, care ?':od'n-System Check Valve Operation Demonstration and :-
Testing, Part
- B", and SP-603, Decay Heat Check 'laive Leak Testing, need to be performed.
c.2.14.2 If coming to refueling mode, perform 3P-603, Decay He[t Check Valve Leak Test:ng: SP-402, Core F1codinc System !s51ation Valves Alarms Actuatton: and SP-405
"*S*
'2 OP-209 Rev. 5 7 E
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e Initials Core Flooding System Check Valve Operation Demonstra-tion and Leak Testing.
[These three (3) procedures shall be performed in their entirety.]
6.2.15 At 700 psig RC pressure, close CFT isolation valves CTV-5 and 6 and red tag the breakers in the ' Locked Reset' position to the NSS if required to prevent l52 tanks from discharging.
a.
CFV-5 b.
CFV-6 6.2.15.1 No testing of the HPI pumps (normal operation of a
,5:
single makeup pump exempted) will be performed wnen the reactor coolant temperature is below 230'? unless double valve isolation is maintained between the RCS and all flow paths from the pump (s) being tested.
6.2.15.2 whenever the core flood tank pressure is greater than or equal to the maximum allowable RC pressure for existing RC temperature: CFV-5 and CFV-6 will be j
closed and their breakers placed in the " locked reset' l
position and red tagged to the NSS.
6.2.15.3 When RCS is < 550 psig and > 1'00 psig the pressuri er l
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level is limited to f.180 inches.
When RCS is f. 100 psig, the pressurizer level is limited to
( 275
- inches, j
i OP-209 Rev. 3 7 ~
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Initials 6.2.16 When RCS pressure decreases to ( 600 psig and > 350 psig, sample and determine the required boron concen-tration to maintain shutdown margin at ambient temper-ature and Xenon-free core per OP-304, Soluble Poison Concentration Control.
NOTE:
Boration must be completed prior to insertion of safety rods (Groups 1 thru 4).
6.2.16.1 When RC system is < 550 psig and stable and at 250*F, 154 place the key-operated switch for the pressuri:er pilot-actuated relief valve in the
' Overpressure Protection
- position.
NOTE: This changes the set potat to 550 psig.
Op-209 Rev. 5 7 ~j ease 13a N-n
Initials C&UTION: If the *0verpressure protection
- mode is not operable, the Operator should control pres-sure < 550 psig by placing the control Switch for RCV-10 to the
- 0 pen
- position as necessary to maintain RC pressure < 550 psig.
6.2.16.2 Whenever the following conditions exist concurrently, l54 the pressurl:er heater banks will be selected to the l
OFF position:
- 1) During a normal cooldown, and l
2)
RCS pressure > 475 psig, and 3)
RCS temperature < 220*F.
6.2.17 Continue plant cooldown to < 300*F and plant depres-surl:ation to 400 psig while performing the following steps:
a.
When RCS <
350*F, commence filling the steam generators to maximum level allowed by S.T.S.
- 3. 4. 5 at a rate not to exceed 2.4 x 105 lbm/hr:
unless directed otherwise by Chemistry.
b.
When RCS <' 280*F, continue filling steam genera-tors to 96-99% on operate range.
c.
When RCS < 500 psig, place the overpressure miti-gation recorder / system in service by selecting the
' Fast
- position on chart recorder RC-154/TR.
d.
prior to achieving RCS < 400 psig and when bora-tion of RCS per Step 6.2.16 is complete, insert Safety Group #1 and trip the reactor.
l 6.2.17.1 Below 580*F 1-1/2* Drain / Blow valves for OTSG *A" and
- B*
may be opened inside reactor building to aid in boil control and chemistry control of OTSG's per or 2.
Rev.3 7 page 14 I
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s HKC 01/22/87 Initials 7.0 COOLDOWN WITH DH SYSTEM 7.1 INITTAL CONDITIONS 7.1.1 Cooldown in progress with OTSG's.
7.1.2 Pressurizer level at approximately 180 in.
7.1.3 Two (2) RCP's operating (A lodp).
7.1.4 Boration to the required concentration is complete.
7.1.5 All rods are inserted (except far APSR's uniess R '.*
head is to be removed).
7.1.6 RC temperature 1 300'F and RCS pressure within limits of Curve 6 of Op-1038, Heatup/Ccoldown Curves 7.1.7 Continuous blowdown of the OTSG's is in progress.
7.1.8 Manual bypass valves FWV-155 and 156 are enrottled open, providing a continuous feed to the OTSC's.
7.2 COOLDOWN NOTE:.To minimize the possibility of forming a steam bubble in the top of the RCS hot legs, it is necessary to use the secondary plant with forced RC flow via RCP's to as low a tempera-ture and pressure as achievable in accordance with Curves 6 and 7 of Op-1038, Heatup/Cocidown Curves, prior to placing the decay heat removal (DHR) system in operation.
OP-209 Rev. 6 7 Page 15 W _,__--_--_ - - - - ~~~ - ~ ~ ~.
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HKC 01/22/87 Ini 1als 7.2.1 Continue plant cooldown to < 280*F in accordance with Curve 6 of OP-103B, Heat /up Cooldown Curves, and perform the following steps:
a.
Place EFP-1 control switch in " Pull-to-Lock" b.
Motor operated valves MUV-23, MUV-24, MUV-25 and MUV-26 will be closed and de-energized with their circuit breakers " red tagged" in the 'iccked reset
- position to the NSS whenever the RC temp-erature is < 265'F.
If maintenance, testing or other plant.:endations require aperstion :f in+3e valves, the following requirements will be met:
1.
Double valve isolation on the main and recir-culation discharge lines is maintained between in]ection trains, and 2.
The HP Injection Pumps in the af fected train Is de-energized with its circuit breaker
' racked out' and " red tagged
- to the NSS, and 3.
The HPI pump suction or discharge valve in the affected train is in the " closed" position and
" red taqqed" to the NSS.
4 OP-209 Rev. 5 7 3 Page 16 (Continued on Page 16a) i-,
o HKC 01/22/87 Init:ali__
c.
Maintenance and/or testing of the PORV will not be performed when the RC temperature is ( 290*F unless all the following conditions are met:
1.
Pressurizer level 1 180*.
2.
Makeup tank level 1 86*.
3., RC pressure 1 250 psig.
4.
MUV-23, MUV-24, MUV-25, MUV-26 are closed and de-energized with their breakers
- red tagged" in the ' locked reset
- position to the NS3.
5.
CFV-5 and CFV-6 are closed and their breakers in the
' locked reset
- position and
- red tagged
- to the NSS.
J.
Close MUV-58 and 73 and bypass auto fun:ti:n sa;;n open on low MUT Level f<
13' 7.2.2 Reduce RCS pressure to 1230 psig in conformance sith Curve 6 of Op-1038, Heatup/Cooldown Curves.
a.
Establish initial conditions for DHR system opera-tion per OP-404, Decay Heat Removal System, Sec-tion 8.1.
b.
If the plant cooldown is for. the purpose at refueling, perform SP-403, Decay Heat Removal Sys-tem Valves Automatic Closure and Interlock Verifi-cation.
7.2.3 Continue plant cooldown and depressurl:ation.
7.2.4 At and below an RCS temperature of 250*F. perform :ne following steps.
a.
Per Chemistry instructions and maintenance requirements, determine and establish OTSG nitro-gen blanket / wet layup conditions in accordance with OP-608, OTSG Secondary Fill,
- Drain, and Layup.
OP-209 Rev. 51P ' ag Page 16a
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HKC 01/22/87 Ini-la' n b.
Maintain OTSG levels between 96 and 9 9 *. on the operate range instrumentation unless otherwise required for plant cooldown or OTSC wet layup con-dition.a determined above.
c.
P.I12I to securing all RCP's, bypass " Loss of All CH. A RCP's' logic to EFIC by going to bypass at initi-CH B ate module at EFIC cabinets in each channel.
push
_li.. C toqqle switch marked *RCP* up to *9ypass* ' switch
'H.
will spring return to mid position).
Observe that bypass status light marked *RCP Shut-down* 1s flashing (located it each EF:
cabinet upper portion).
NOTE:
The running RCP's should be stopped as soon as possible after starting a DH pump (DHp!
7.2.5 When further RCS cooldown is not practical using the secondary plant, perform the following steps:
a.
Start one (1) DHR train per OP-404, Decay Heat Removal System, while observing the requirements of Curve 4 of OP-1038, Heatup/Cooldown Curves, Plant Curve Book.
b.
Verify that DHR flow is automatically Ocntrollad between 2800 and 3100 gpm.
c.
Adjust applicable DHR temperature controller DH-18-MS or DH-17-MS to stabill:e RCS temperature.
d.
Stop the running RCP's per OP-302, RC Pump Opera-tion.
e.
Close the turbine bypass valves.
OP-209 Rev. > 2 e
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Initials NOTE:
RCS pressure control is now througn use of pressurizer heaters and DHR pressurizer auxili-ary spray valve RCV-53.
f.
Close RCV-13 and record the closure time on tne data sheet for SP-435, Valve Testing During Cold Shutdown.
g.
If RCV-53 is opened, record opening time on cata sheet 'for SP-435, Valve Testing During Cold Shut-
- down, n.
If the plant cooldown is f a.-
tne v :ose af refueling, perform SP J12, ECCS anc Containment
- Spray System Leak Rate Test.
NOTE: Hot le.g flasning may occur due to temperature stratification caused by pressuri zer outsurge to hot leg in response to RCS water contraction during plant cooldown or excessive spraydown of pressurizer.
7.2.6 Adjust applicable DHR temperature controller DH-17-MS or DH-18-MS to achieved desired cooldown rate in accordance witn limits of Step 6.2.10(a).
OP-209 Rev. 5 7 m
se la a
i r
,_.9
_,___,____m
s Initials 7.2.7 Slowly reduce RCS pressure by decreasing pressurl:er heater output and using minimal spray flow via RCV-53.
7.2.8 Manually control pressurizer level control valve (MUV-31) to allow pressurizer level to increase at 1 25-in. per hour while cooldown and depressurization of RCS continues.
7.2.9 Monitor all RCS temperatures (particularly "A*
loop Th on redundant instrument panel) and pressures for indi-cation of saturation.
If hot leg saturation or a sudden rise in pressurl:er level is observed, momentarily stop cooldown and ralce RCS pressure un 11 hot leg flashing has stopced 7.2.10
'4 hen the steam ;enerators are fliled ::,
n- :t:mra level per Step 7.2.4.
secure feedwater ! F'O : coster pump and close FWV-33 and 36, startup FW isolation valves.
7.2.10.1 Perform Section 9.7 of SP-435, Valve TesIng During Cold Shutdown.
7.2.10.2 If unit is going into a Refueling Outage, either
,5 perform Steps 9.15 through 9.15.10 of SP-410, Valve Testing During Refueling Outages, now, or schedule this test to be performed during the performance of OP-202, Plant Heatup.
7.2.11 At < 200*F and when RC pressure is I 150 psig:
a.
Verify pressurl:er level at approx 1mately
- 3C' then secure running MUP per OP-402, Makeup and Purification System, and rack out and red tag its breaker.
OP-209 Rev.
g Page 19
Initials b.
Rack out and tag the breakers for BSP-1 A and 19, and close and tag BSV-3 and 4 per OP-405, Reactor Building Spray System.
c.
Close BSV-99 and BSV-100 and red tag to SSOD.
d.
Close BSV-16 and BSV-17 and red tag to S500.
156 e.
Close DRV-34 and 35, BWST - DH isolations).
f.
Pressurizer level will be maintained below 275' when RCS pressure is < 100 psig.
7.2.12 At 180*F RC temperature, terminate steam generator blowdown by closing MSV-148, MSV-130 and MSV-439.
7.2.13 Remove condenser vacuum system frcs serti:e per CP-607, Condenser vacuus System.
7.2.14 Break vacuum on turbine.
a.
When vacuum reaches zero, secure gland sealtng steam on turbine by closing GSV-7, high pressure gland supply shut-off valve.
b.
Insure GSV-8, high pressure gland supply bypass valve, is closed.
Record time:
NOTE:
to avoid turbine rotor bowing, it is preferable to maintain the turbine turning gear and turbine oil circulating system in operation throughout the turbine shutdown period.
1 l
1 OP-209 Rev.
If h
Page 20 f5 jf 5
.-n
. - ~.,,,,
Initials 7.2.15 If it is required that tne turoine turning gear ano/or the turoine oil circulating system be secured for maintenance, perform one (1) of the following steps:
a.
Maintain the turbine turning gear and turbine oil circulation system in operation for a minimum of 48 hrs, after breaking condenser vacuum and secur-ing gland steam to the tur5ine.
(OR) b.
For situations wnere a costly delay in the outage schedule would occur, or the turoine rotor is stucx, consult Reference 3.'J f ar :arone :;rt,;
Jear ano ]il cir:J' a!' ng sf s!em "eQU 1 *e'Cea t s.
4 7.2.16 Remove condensate system f rom service per OP-603, Con-densate System.
7.2.17 Secure FW system per OP-605, Feecwater System.
7.2.18 If the plant is to remain at COLD SHUTDOWN operating Mode 5, stop cooldown and maintain RC temperature at i
< 200*F.
i 7.2.19 At 50 psig RCS pressure, close sample valves on pres-su ri zer.
a.
Close breaker #19 at ACDP-53 for NGHE-2.
b.
Close breaxer 416 at ACDP-3 for NGHE-3.
7.2.20 Open RCV-6, pressurizer isolation to waste disposal, 4
and RCV-7, nitrogen control valve to pressurizer.
Nitrogen snall now be controlled to tne pressurizer by way of NGV-85, nitrogen to pressurizer, at 40 psig.
l l
l l
OP-209 Rev. 5 7 E
page 21 l
l i
n,--
Initials 7.2.21 De-energize all pressurizer heaters and allow the pressurizer to cool to ambient.
7.2.22 At 140*F RCS temperature, cooldown is considered com-plete. However, DHR operation should continue to fur-ther reduce the RC temperature for personnel comfort.
7.2.23 Upon completion of this procedure, transmit a copy of tne Procedure Approval and Transmittal Sheet to ;ne Nuclear Results Engineer Specialist for updating SP-296, Documentation of Allowaole Operating Transient Cycles.
Snift Supervisor
.3:a 8.0 C00LDOWN WITH ONE STEAM GENERATOR
.' n : : T a i s 8.1 INITIAL CONDITIONS 3.1.1 Reactor is in HOT STANDBY condition.
8.1.2 One (1) or two (2) RCP's are running in each ' loop.
8.1.3 One (1) MFWP is in operation.
8.1.4 Calculations to compensate for contraction and Dora-tion have Deen completed per OP-304, Soluble Poison Concentration Control.
8.1.5 Safety Rod Group 1 witndrawn to Out-Limit".
8.1.6 Notify ChemRad to sample the RCS and the pressurizer water space for activity, dissolved nydrogen, anc boron.
OP-209 Rev. 617 jf Page 22
Ini tial s 8.1.7 Nitrogen system is operable per OP-414, Nitrogen and Hydrogen Systems.
8.1.8 Startup FW bypass valves (FWV-155 and 156) are open, allowing a continuous feed to both OTSG's.
8.1.9 Continuous blowdown of steam generators is in progress through lower tube sheet drains via sample sink.
8.1.10 Veri fy auxilia ry steam is available and aligned oer Section 8.0 of OP-606, Auxiliary Steam Syste:n.
8.2 STEAM GENEP.ATOR "A" ISOLATION 8.2.1 or isolation of steam gene o t or-clica.ne 30-4 lowing valves in :ne "'1anual Clated" aosi ";n:
a.
MSV-411, MS Iso.
b.
MSV-412, MS Iso.
c.
MSV-55, MS Supply to EFWP d.
FWV-30, MFW Block Viv e.
FWV-31, Low Load FW Block Viv f.
FWV-36, Startup FW Block Viv g.
FWV-28, Crossover FW Viv
- 5 '.
8.2.2 Outside of Control
- Center, ma nu al"ly close the following:
a.
MSV-303, MS Drain Trao-22 Iso. V1v b.
MSV-308, MS Drain Trap-22 Bypass Viv c.
MSV-301, MS Drain Trap-23 Iso. Viv d.
MSV-307, MS Orain Trap-23 Bypass V1v OP-209 Rev. 5 7 1
p3ge 23 1
a
,.7.,-
Initials 8.2.3 Proceed to Step 8.4.
8.3 STEAM GENERATOR *B" ISOLATION 8.3.1 For isolation of steam generator
- B*,
place the following valves in the
- Manual Close* position:
a.
MSV-413, MS Iso. Viv b.
MSV-414, MS Iso. Viv c.
MSV-56, MS Supply to EFWP d.
FWV-32, Low Load FW Block Viv e.
FWV-29, MFW Block Viv f.
FWV-33, Startup FW Block Viv 7
FWV-28, Crossover FW Viv 8.3.2 Outside of Control Center, manually close :ne :clicw-Ing:
a.
MSV-299, MS Drain Trap-24 Iso. Vlv b.
MSV-306, MS Drain Trap-24 Bypass Vlv c.
MSV-297, MS Drain Trap-25 Iso. Viv d.
MSV-305, MS Drain Trap-25 Bypass Viv l
l 8.4 Adjust turbine bypass or atmospheric dump valves on
- 54 l
unaffected steam generator to maintain cooldcwn rate.
8.5 Maintain flow in both RC loops.
t i
l
~?J Page 24
. i.
OP-209 Rev.517
NOTE: Cooldown with one (1) steam generator must be considerably slower tnan normal cooldown aue to RCS-to-shell aT temperature limits.
The tem-perature difference between average RC loop and average OTSG shell shall not exceed 100*F.
8.6 Complete the steps of Section 6.2, Cooldown.
9.0 ALTERNATE METHODS FOR RCS DEGAS 9.1 ALTERNATE METHOD FOR RCS DEGAS USING PZR VENT AND WG htA0t<
9.1.1 3 pen or vert 'y Joen WDV 405, aD! 206.
9.1.2 Close or veri fy :losed RCV-7, RCV-155 and '.10V-1022, i
9.1.3 Place RCDT on recire.
NOTE: Opening RCV-5 and RCV-6 will cause local adi-ation levels to increase, will lower RCS pres-sure, and have possible moisture carryover into the Auxiliary Building Waste Gas Header.
If moisture, carryover is coserved, consider ;s ng Second Alternate Degas Metnod.
9.1.4 Open RCV-6.
9.1.5 Throttle open RCV-5 to initiate RCS degas.
t 9.1.6 Upon completion of alternate degas metnod, close RCV-5 and RCV-6.
OP-209 Rev.
f Page 25 7 Continued on Page 25a)
9.2 SECOND ALTERNATE METHOD FOR RCS DEGAS USI'4G PZR VENT TO RCDT AND RCDT VENT TO MWST i
9.2.1 Close or veri fy closed WDV-405, WDV-406, WDV-949, WDV-1022, RCV-7, and RCV-166.
9.2.2 Open or veri fy open WDV-407, WDV-60, and WDV-61.
9.2.3 Place RCDT on recirc.
NOTE: Opening RCV-5 and RCV-6 will cause locii radi-ation levels to increase, and will lower R:3 pressure.
9.2.2 2 pen RCV-6.
9.2.5 Throttle open RCV-5 to initiate RCS degas.
9.2.6 Upon completion of alternate degas metnod, close RCV-5, RCV-6, WDV-60, and WDV-61.
ENCLOSURES 0TSG Blowdown Lineup OTSG Cleanup via Soak and Blowdown Information Concerning Cooldown Follo4ing a cire
- 3; in the Control Room or Caule Spreading Roon i
l f
i l
OP-209 Rev. 5 7 3
page 2sa
ENCLOSURE 1 9_T1G h D_2wn Line-up 1)
Ensure MSV-519, MSV-439, MSV-440, MSV-511, MSV-514, MSV-517, MSV-514.
- 52 MSV-518 are closed.
2) i 3) l 4)
Perform the following Valve Line-up:
X 91LG
.Qnc.a
.".E 9DG 0o*n MSV-124 MSV-142 MSV-125 aSV 43 MSt-125 MSv ' 14 MSV-127 MSV-145 MSV-176 MSV-177 5)
Open OTSG Blow Down isolation valve MSV-130 for "A'
'T:3 :: '42'i ';.
'B' OTSG.
6)
Slowly open MSV-514 to pressurize line between.MSV-514 and MSV-E's.
~~
7)
Open MSV-518.
8)
Crack open MSV-517 to allow line to warm-up for ? 15 n nutes 9)
Open MSV-517 after warm-up to maximum blow down not er s.t: ~.i
'T3:
+
I cooldown.
If more blowdown is needed, throttle open MSV-516 10)
'4he n changing from one 0TSG to ne other. open ne..
- 1.:
isolation (MSV-130, MSV-148) bef ore closing tne open one.
2" u..:
i prevent water hammer of the Blow Down line.
)
Line Up Completed:
/
Date Time OP-209 Rev.3 ? )
page 26
MEANUP VIA SOAK AND BLOWDOWN ENCLOSURE 2 Pg 1 of 3 1.1 Ensure MSV-439 and MSU-482 are closed.
1.2 Ensure MSV-474 and MSV 475 are closed.
1,3 Open MSV-481 and MSV-483.
1.4 Perform the following Valve Line-up:
"A" OTSG OPEN "B" OTSG OPEN MSV-124 MSV-142 MSV-125 MSV-143 MSV-126 MSV-140 MSV-127 M SV-145 MSV-176 MSV-177 "A" OTSG SOAK 2.1 Close turbine bypass valves on both generators.
2.2 Slowly increase level in "A" OTSG to approx. 80% on the operating range, while Maintaining RCS Temperature within 100F of Initial Temperature.
2.3 Close feed valve on "A" OTSG.
2.4 Maintain RCS temp constant by steaming the "B" OTSG.
2.5 Maintain "A" OTSG sample valves open during test.
2.6 Hold level in "A" OTSG constant for between 1.5 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
CAUTION: If level increases in "A" OTSG continue with step 2.7.1 of and throttle open MSV-482 to maintain OTSG level at approximately 30% on the operating range During Soak Period.
OP-209 Rev. U 7 ~E Pace 27 t
~
ENCLOSURE 2 Pg 2 of 3 2.7 After 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, open blow down line per step 2.7.1 with as much flow as possible not to exceed the safe capacity of the blow down line.
2.7.1 Open OTSG Blow Down isolation valve MSV-130 for "A" OTSG.
2.7.1.1 Slowly open MSV-439 to pressurize line between MSV-439 and MSV-482.
2.7.2 Crack open MSV-482 to allow line to warm-up for @l3 minutes.
2.7.3 Open MSV 482 after warm-up to maximum blowdown not to exceed OTSG cooldown. If more blowdown is needed, throttle open MSV-474 2.7.4 When changing from one OTSG to the other, open the Closed OTSG drain isolation (MSV-130, MSV-148) before closing the open one.
This is to prevent water harnmer of the Blou Down line.
2.3 Drain the OTSG level to 30" and repeat steps 2.1 thru 2.7 for a second time, if required by Chemistry.
"B" OTSG SOAK 3.1 Close turbine bypass valves on both generators.
3.2 Slowlv increase level in "B" OTSG to approx. 30% on the operating range, while Maintaining RCS Temperature within 100F of initial temperature.
3.3 Close feed valve on "B" OTSG.
3.4 Maintain RCS temp constant by steaming the "A" OTSC.
3.5 Maintain "B" OTSG sample valves open during test.
3.6 Hold level in "B" OTSG constant for between 1.5 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
CAUTION: If level increases in "B" OTSG continue with step 3.7.1 of Enclosure I to maintain OTSG level at approximately 30% on the operating Range.
i 57 i Page 2s OP-209 Rev.
l
ENCLOSURE 2 Pg 3 of 3 3.7 After 2 nours, open blow down line per step 3.7.1 with as much flow as possible not to exceed the safe capacity of the blow down line.
3.7.1 Open OTSG Blow Down isolation valve MSV-148 for "B" OTSG.
3.7.1.1 Slowly open MSV-439 to pressurize line between MSV-439 and MSV-482.
3.7.2 Crack op'en MSV-482 to allow line to warm-up for @ 15 minutes.
3.7.3 Open MSV-482 after warm-up to maximum blow down not to exceed OTSG cooldown. If more blowdown is needed, throttle open MSV 474 3.7.4 When changing from one OTSG to the other, open the Closed OTSG drain isolation (MSV-130, MSV-148) before closing the open one. This is to prevent water hammer of the Slow Down Line.
3.8 Drain the OTSG level to 30" and repeat steps 3.1 thru 3.7 for a second time, if required by Chemistry.
3.9 After completion of the second hot soak, continue blowing down the "A" and "B" OTSG as required per Chemistry.
3.10 At 15% power, close MSV 439, 474, 481', 482, 483,124, 125, 126, 127, 142, 143, 144, 145.
Line Up Completed:
/
Date Time l
l l
l OP-209 Rev. 3 "/
y Page 29 l
l L
ENCLOSURE 3 152
' 49e '. # 13
~
INFORMATION CONCERNING C00LDOWN FOLLOWING A FIRE IN THE CONTROL ROOM OR CABLE SPREADING ROOM Introduction Evacuation of the Control Room requires entry into AP-990 (Shutdown from Cut-side Control Room).
This procedure directs the operators to t-ia "cW oumos, initiate EFIC, tri p the reactor and turoine, and close tne "S: !'s.
'"e operators exit AP-990 when the plant is stable in Hot Standby,.vith o r.v i t n -
out RCP's running.
Plant temperature is controlled by steaming tne mi's through the ADV's.
Any fire so severe tnat aequi res Cantroi 400 3 avscuattan
.u j a,s 3 ; ;- - -
cant damage to plant equipment and controls.
Since it is imooss+Ce n predict wnat specific safe shutdown comoonents woul.1 oe affe:te; Oy s. : -' t fire, AP-990 directs the staff to review equipment ivai l abi li ty snd ' 3r,u ' 3:e a plant cooldown procedure accordingly.
1 This information is intended to assist tne staff in designing a spec t 'i c cooldown procedure following Control Room evacuation.
Va ri ou s c]ollow, scenarios are described, predicated upon the events in the to cao n 's provided.
In all cases, entry into a flowpath should not begi1 Jnti! !"e plant is stable and a clear picture exists of what necessary eW: ee availaole for cooldown.
At tnat point, tn e 3pp rop ri a t e fiacn ' : r'
'e followed and the scenario that most closely fits existing condi: ans selected.
Using this scenario as a gu id e, tne staff can :nen.. r t e a detailed cooldown procedure addressing specific components.
2
~
OP-209 Rev
") 7 g
Page 30
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"NCLOSURE 3 152
age Y
Scenario #1 - Plant Cooldown with Reactor Coolant Pumos Available Reactivity Control:
Adequate shutdown margin may be achieved by boration of tne RCS f rom the CBAST's via the normal (CAV-57) or the emergency (CAY-60) fl owc a tn s.
If these flowpaths are unavailable, BWST water may be injected into the RCS via the operable makeup pump (s).
Thermal Control:
EFP-1 and (poss.ibly; EFP-2 are availaole to supply feedwater :a :ne JTS3's.
EFIC controls 0TSG levels at Low Level Limits.
RCS 30: : awn cite
's controlled by the ADV's f om the RSP.
- f 7SD contro; is m er 2 12 e,
-e aDV's may De throttlec locally.
i?o-? snoi:: e sec. e: 1: :,: : -
af ?90 psi; ]r ;rea t er.
3el u :nts coi10, 'eedci
+r s
s...
t-TSG's ; sing IFP-1 ar t.,e fee:wate acas;a aw as.
If desired, isolate CFT's above 600 psig P.CS pressure.
CFV-5 enc ;:!-6 uy require local operation from inside containment.
Establisnment of decay neat removal is essentially normal exceot na:, a
.1 '
valve operations may be required.
This may require a containment er: y :)
open DHV-3 and DHV 4 Inventory Control:
Normal letdown is available via MUV-49.
If normal make';p eia MUV-31 is na:
available, throttle HPI valves (MUV-23, 24, 25, 26) as required to e :ai, 1
pressurizer level. These vaives may require local operation.
Pressure Control:
As during normal operation, pressurizer heaters and spray 3 e av 3i' 3M e ';-
pressure control.
Inese mus ce cantrolled nanaally, et:ner 'r:c :9 '?
e Shutdown Panel or locally.
l
. _u OP-209 Rev. 57 page n
a
~
+
/
v ENCLOSURE 3 i52:
' 3 3g+ i P.2 i
Scenario #2 - Plant Cooldown with RCP's Availabl3 (Letdown Unavailaole)
Reactivity Control:
/
Adequate shutdown margin may be schieved by boration of the RCS from ne CBAST's via the normal, (CAV-57} or the emergency (CAV-60) flowpatns.
these flowpaths are unavailable, BWST water may be, injected into the' RCS ri s the opersole makeuo pump (s),
t i
Thermal Control:
s EFP-1 and (possibly) EFP-2 are available to supply eedwater ta tne 0 Li's.
EFIC controls 0TSG levels at Low Level L i mi-t s.
RCS cooldown -ne
's controlled by - the ADV's f rom the RSD.
If RSP 300: 01 is sna n' ' n +.
a
~
A07's 1ay be throttled Ic:a:!y.
EFS-? schj:: ;e ;ec ec n a ; n m
af 200 osig 3r greater.
3e ' ;w *ni; 3 r,t, 'ee%a er
- s 4 r; -
- -
STSG's asing EFo-1 or taa 'ee:.va:ec noster p ros.
If desired, isolate CFT's above iGO asig RCS pressure.
?7-5 anc :7-5 737 require local operation from inside containment.
Establishment of decay neat remo va l is essenti311y normal except t'a: nr. 3 '
valve operations nay be required.
This may require a cont ainment ert j ::
open DHV-3 and DHV-4 Inventory Control:
' ~
~
Normai letdown is unavEtilacle.~ Makeup is accomplished ask og the coerso e 43*.
pump (s) with the BWST as tne water source.
Witn ' RCP 's; operati ng, sea' injection into tne RCS coul d eventually causr the p rec.s a ri ze r ta tec:,e j
solid.
To prevent this,. consideration should 3e given to 3dj isting cof ::wn rate sucn that; reactor coolant contraction equals or exceecs inventory ;3i-due to pump seal injection.
Alternatively, drain and/or sampie lines can 3e opened to remove ed:ess reactor coolant.
Throttle HP! v11ves (VU,7-M. ?!.
25, 26) to maintain presscrizer level, inese va'ees may
- d % ' :;t '
operation.
i Pressure Control:
As during normal operation, pressurizer heaters and spr3y are availlole ',0r pressure control.
These must be controlled manually, either 'com the Renate Shutdown Panel or locally.
/
)
OP-209 Rev. 57. ~
paye 3c 4
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ENCLOSURE 3 152 f
(> age 6 Y.3 Scenario #3 ' - Plant Cooldown with RCP's Available (EFP-1 and Letdown Unavailable) s r
Reactivity Control:
~
s s
Ade::uate shutdown margin may be achieved by boration of the RCS from :Ne CBAST's via the normal (CAV-57) or tne emergency (CAV-60) flowpatns.
If i
these ficwpaths are unavailable, BWST water may be injected into :ne ?CS eia the operabicaakaup pump (s).
t Thermal Control:
,o EFP-1 is unavailable.
EFIC controls 0TSG levels at Low Level Limits.
405 cooldown rate is controlled by tne ADV's f on t7e RSP.
If RS? CMa'
- navailaol e tne ADV's 13y Se nrot-!ad
- acally.
E0-2 s ;.
2+
-: n s
a steam ]ress are of 200 psi; ]r gres tr.
3el u.,i; :: :.
+-- :
e supplied to ;ne 075G's :na fee:wa:er Docster ;nnos.
IfJesired, isolate CFT's aoove 600 asig RCS oressure.
CFV-5 anc Fl-6 a.
c'equiae local operation from inside containment.
E 3.y.3M i s hment of decay heat removal is essentially nornal excep
- 1a-a ';a' vai Je operations may r; requi red.
This may require a containmen en: j :-
~
open 3HV-3 and DHV-4 Inventory Control:
Normal letdcwn is unavailable. Makeup is accomplished asing the operaale 4?'.
4 pump (s) with the BWST. as the water source.
Wit 9 RCP's operating, sea' injection into the RC5 could eventually cause the pressurizer to 3eco,e solid.
To prevent this, consideration should oe given to adj isting cla
- ]<-
rate such that reactor :colant contraction equals or exceeds inventory ga',
due to pump seal injecticn.
Alternatively, drain ahd/or sample lines ca, 3e opened to remove excess reactor coolant.
Throttl e 4DI vi' ves NUV-?l. ?!.
25, 25) to maintain pres su ri zer level.
~5ese va ses no
?.:. - e operation.
s
'Y-Pressure Control:
As during normal operatlon, pressurizer heaters and sp ray are avr 1a010 far pressure control.
These must be controlled manually, either f rom ne Remote Shutdown Danel or locally.
4 Rev. 5 7 h 0P-209
""9' 35 g
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ENCLOSURE 3 l52
'03ge 7 ]f.3' Scenario #4 - Plant Cooldown with RCP's Available (EFP-1 Unavailable)
Reactivity Control:
o Adequate shutdown margin may be achieved : by boration of the RCS from ne C8AST's via the normal (CAV-57) or the emergency: (CAV-60) flowpatns.
- f these flowpaths are unavailable BWST water May oe injected into tne RCS via the operable makeup pump (s).
Thermal Control:
EFP-1 is unavailable.
EFIC controls 3T6G levels at Low t.evel Limits.
R ",3 cooldown rate is cont. rolled by tne ADV's f roni :ne RSP.
If RSP control is unavailable, the ADv's? may oe throttled loct!!y.
IO-2 snou!1 oe u c. - i r.
3 steam pressure of 200 asig 3r greater.
3e' u 9's 105-0,
~:.+
's supplied to the O'5G's ising or ne 'ee wer.e was e w: 4.
If desired, isolate ^FT's above %0 psi; RCS oressare.
F/-5 2 ; : 3. -6 n a,,
require local operstf on from inside cont 3iament.
Establishment of decay hea't removal is essenti a l ly normal e xceo; t.' 3-in ai valve operations may 3e requi red.
This may requi re a cont 3! a nen: ect y :)
open DHV-3 and DHV-4 Inventory Control:
Normal letdown is ' available via MUV-49.
I' rormal makeup via MUV-31 is "ot availabled throttle HPI valves (MUV-23, 24, 25, 26) to maintain pressar129-level. TFese valves may require local operation.
Pressure Control:
As during normal oper 3 t. s.., p 2urizer heaters and spr3y are avail anle 'a-oressure control.
These must le cont-]Iled man; 31'j, eitner ' 2
-+
'e
+
Snutdown Patiel or locally.
\\
OP-209 Rev. 5 7
- as pace
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e------,,-n
... _... -.... _.. l.. _ :.. '. L.. :...
ENCLOSURE 3 152 (Page 3 of 13)
Scenario #5 - Plant Cooldown with HPI/PORV Cooling Reactivity Control:
Adequate shutdown margin may be achieved by boration of the RCS f*om 01e CBAST's via the normal (CAV-57) or the emergency (CAV-60) flowpa:ns.
these flowpaths are unavailable, BWST water may be injected into tne 7CS via the operable makeup pump (s).
Thermal Control:
No EFW is available to tne OTSG's.
BWST water is supplied to tne core ay the operable HPI pumos and is then relieved :nrough the PORV to :ne Orsia tank and the Reactor Building.
Duri ng HPi/00RV :coling, run 3 :?
adecuate subcooling.nargin exists) to promote :hermal mi dn g vi: 4 -.+-:5.
During cooldown in this mode, a point of :nerma' eau i l i a ri ;., nay w 33: e:
unere neat removal oy HPI balances heat production oy decay nea:.
point, cooldown rate is controlled by One natJr31 decrease of :ec3j "925.
When tne BWST level reacnes 2.5 feet, the L?I pumps are aligned to aro v :e suction to the HPI pumps from the RB sump.
This cooling mode continues r ',
the OH system is aligned for operation.
This.nay require 1anua' de operations. OHV-3 and DHV-4 may require local coeration witnin :onta'n,ea If desired, isolate CFT's above 600 psig RCS pressure.
CFV-5 and 7/-i sy require local operation from inside containment.
Inventory Control:
RCS inventory is maintained by HPI.
The pressurizer is in a solid :endition until after the establishment of DH operation.
HPI valves (MUV-23, 24, 25,
- 26) may require local operation.
Closely monitor MUT level and close 'tv-64 before the MUT empties.
Pressure Control:
Ouring HPI/PORY cooling, pressure is controlled ny :nrottling ',D:
'N subcooling margin requirements permit).
In this mode, tne PORV shoul; rena:,
open.
57 'E
'OP-209 Rev.
,,g, 37
=
ENCLOSURE 3 l52 (Page 7 of 13)
Scenario #6 - Plant Cooldown with Off-Site Power Unavailable Reactivity Control:
Adequate shutdown margin may be achieved by boration of the RCS from tne CBAST's via the normal (CAV-57) or the emergency (CAV-60) fl owp a tn s.
these ficwpaths are unavailable, BWST water may be injected into tne RCS v a i
the operable makeup pumo(s).
Thermal Control:
RCP's are unavailable and the reactor is being coo'e:
cy na ;r3' circulation. EFo-1 and (possibly) EFP-2 are available to sucaly 'recwner ta tne OTSG's.
EFIC :ontrols ]T5G levels at 5 0 ",.
RC3 :W:v n+
cantrolled oy t.1e ADV's ' m t,e RSP.
- ' RSP :catroi ';
+, :-
ADv's may oe t7rottled 13callj.
- 9-2 snou': ce sac. ed e i ; ti- _ ^{
^:
]f 200 asig or greater.
3elow tnis acint, 'aecan e-
's
- .
- : - 4:
-e JTSG's using EFD-1.
If desired, isolate CFT's acove 600 psig RCS pressure.
C 'l-i an 7 /-d,3j require local operation from inside containment.
Establishment of decay heat removal is essenti3lly norma' extept tn::
3 ;3' valve coerations may be required.
This nay equire a cantainmen: e-t j ::
open DHV-3 and DHV-4, 4
Inventory Cor. trol:
Normal letdown is available via MUV-49.
If normal makeup via MUV-31' i s not available, throttle HPI valves (MUV-23, 24, 25, 26) as ecuired ta mainta',
l pressurizer level.
These valves may require local operation.
Pressure Control:
With no of f-site power, pressarizer neaters and saray are ;navst'!C+.
3 pressure is.tsintained by using makeup to " squeeze" tne steam Duc7:e ir tne press uri ze r.
Minimize insurges and outsurges of p res su ri zer water to l
conserve the residual metal and water heat that keeps the steam buoble in 3 i
saturated condition.
l l
l i
l
[
j' OP-209 Rev.5 7 7
Pase 3a
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- - - - ~ - - -
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t, ENCLOSURE 3 152 (Dage ' ) af 13l Scenario 47 Plant Cooldown witn Off-Site Power Unavailaole (Letdosn Unavailable)
Reactivity Control:
Adequate shutdown margin may be achieved by boration of tne RCS f rom the CBAST's via the normal (CAV-57) or tne emergency (CAV-60) fi:woatns.
tnese flowpaths are unavailable, BWST water may be injected into tne RCS vf 4 the operable makeup pump (s).
Thermal Control:
RCP's are unavailable and the reactor is being cooled
')y
,at;rai circulation. EFP-1 and (possibly) EFP-2 see availabla to suco!y 'ee.+3:er :)
tne OTSG's.
E;iC controls STSG 1evels at 50%.
?C3 :20- :w w control'ed 3y 'ne ADV's 'com :ne a$d.
- ' 033 :ac:ro!
'3..
ADV's may oe 51 Ottlec locally.
E:3-2 sn::' 1 7e sa:: e: n 5 F 200 psig or greater.
3e':w :nis acint, fem. ate-
's 4
JTSG's using EFP-1.
If desired, isolate CFT's above 500 psig RCS pressure.
CFY-5 an: ^ Y-6 may require local operation from inside containment.
Establishment of decay heat removal is essentially normal except inat 13 m a i valve operations may be required.
This way requi e a antai~rea: act j ::
open OHV-3 and DHV-J.
Inventory Control:
Normal letdown is unavailable. Makeup is accomplished using t9e operable HP' pump (s) with the BWST as the water source.
RC? seal injection i nto t,e N3 could eventually cause the pressurizer to become solid.
To prevent
- ais, consideration should be given to adjusting cooldown rate suc7 that u ::]c coolant contraction equals or exceeds inventory gai, due ta po ; se C injection.
Alternatively, drain and/or samole lines can be coened ta remov3 excess reactor coolant. Throttle HP: alves :'duv-23, 20, 25, 26 3 ': t '
pressarizer level. These val ees.nay require local opera:'on.
Pressure Control:
With no off-site power, pressurizer heaters and spray are unavail3cle.
RCS pressure is maintained by using makeup to " squeeze" tne steam bucole in :ne pressurizer.
Mi nimi ze insurges and outsurges of pressurizer water ta conserve the residual metal and water heat that keeps the stearn Duable to a saturated c'ondition.
s.
OP-209 Rev 5 7 9
3 age 39
+
.s.
~
ENCLOSURE 3 l52 Page H 3t;I Scenario
- 3 Plant Cooldown with Off-Site Power Unavailable (EFA-;
Unavailable)
Reactivity Control:
Adequate shutdown margin may be achieved by boration of the RCS fran the CBAST's via the normal (CAV-57) or the emergency (CAV-60) flowpatns.
If these flowpaths are unavailable, BWST water may be injected into tne RCS iia the operable makeup pump (s).
Thermal Control:
RCP's are unavailable and the reactor is being cooled by
-2.. i circulation.
EFP-1 is unavailable.
EFP-? is availacle to supply 'ae u n e '
to the OTSG's.
EFIC controls OTSG levels at 50f..
RCS coolaown ra:4 s
controlled by the ADV's from the RSP.
If RSP control is ;navailaole, :na ADV's may be throttled locally.
Coerate EF3-2 until steam aress; e
's insufficient.
If possible, ootain auxilia y steam ' r c r-Jm ;:
<, ? 5: -e EFD-2 ape Stian my :ontinue.
- ' s:44, :a 'e n 19
- 1. W 3 vail 3cle to One OTSG's.
3WST wa:e-i; 5000ii90
)
N :n b --
.r.
MPI pumps and is :nen relievec ineoug, tne 30R7 :: :ne ;1
- r r
Reactar Bu i l di ng.
Duri ng cooldoun in tnis moce, a poin:
J'
- ^ :- - f equilibrium may be reached unere heat removal ny HPI calances heat )coca:.' r by decay heat.
At this point, cooldown rate is controlled oy the n n,r!'
decrease of decay heat.
When the BWST level reaches ?.5 feet, :ne 3:
r: s are aligned to provide suction to tne HPI pumps f ro.n tne R3 sumo.
~^';
cooling mode continues until tne OH system is aligned far cuerati:n.
- s may require manual valve operations.
DHV-3 and DT!
may e:ui e 3: C operation witnin containment.
If desired, isolate CFT's above 500 psig RCS pressure.
CFV-5 and :FV-6 naj require local operation from inside containment.
Inventory Control:
Normal letdown is available via MUV-49.
If normal makeup via vuY-31 is ca:
available, enrottle HPI valves (MUV-23, 24,- 25, 26) as requi ed to na'ata'-
pressurizer level.
These val ves may require local operation. When EF3-2 !s secured and HPI/PORV cooling is established, RCS inventary is maintat,ed entirely by HPI.
The pressurizer is in 3 solid condition 01 i l after N establisnnent of 04 operation.
Closely moni ar *1UT leve? 19d :' m
"".-f:
before the MUT empties.
Pressure Control:
With no of f-site power, pressurizer heaters and spray 3re unav3ilaole.
G pressure is maintained by using makeup to " squeeze" the steam bubble in t'e cressurizer, Minimize insurges and outsurges of pressurizer water ta conserve the residual metal and water heat that keeps the ste3m bubnle in a saturated condition.
During HPI/PORV. cooling, pressure is cont ro l led oy throttling HPI flow (i f subcooling margin requirements permit).
In :qi; node, the PORV should remain open.
OP-209 Rev. 5 7 o ge 40 a
i
.s..
e ENCLOSURE 3 152
'Jage 12 of 13-Scenario 49 - Plant Cooldown witn Off-Site ' Power 'Jnavailable (Letdown ano EFP-1 Unavailable)
Reactivity Control:
Adequate shutdown margin may be achieved by boration of the RCS from tne CBAST's via the normal (CAV-57) or the emergency (CAV-60)
'l owp a th s.
I' these flowpaths are unavailable, BWST water may be injected into the RCS via the operable makeup pump (s).
Thermal Control:
RCP's are unavailable and tne reactor is being cooled by nat;ra'
, circulation.
EFP-1 is unavailaole.
EFP-2 is available to supoly feecwater to the OTSG's.
EFIC controls 0TSG levels at 50%.
RCS cooldown rate is controlled by tne ADV's from tne RSP.
If RSP cont ol
's ma ail n's.
e DV's may oe tn r n tl ed incal y.
'o+-n e i:3-? 2,:i
>3-s 3 n. -:
i1su'fic!+nt.
If pos siale, 03:3i, 3W ! i 3 ry sten 'ro, -:
EF3-2 Ocer3: ion may con,ique.
Ii 3.e39 can,at 13 s m e7, i;-
availaole to the OTSG's.
%ST 4ater is suppliac to tne core n :,e me 3.c3 HPI pumps and is tnen relieved througn :ne PORV to One drii, ta,<
sn; :13 Reactor Building.
During cooldown in this mode, a coint of :ner a' equilibrium may be reached where heat removal by HPI 33 lances '10at J rN ;;;" :1 by decay heat.
At tnis point, cooldown rate is control!ad by :ne na t.ri' decrease of decay heat.
When the SWST level reacnes 2.5 feet, tne LSI p u:s are aligned to provide suction to the HPI pumps
- rom the RS sano.
cooling mode continues until tne DH system is aligned for apernion.
may require manual valve operations.
OHV-3 and DHV-4 may requi a ic:C operation.
If desi red, isolate CFT's above 600 psig RCS pressure.
CFV-5 and CFV-6 my require local operation from inside containment.
Inventory Control:
Normal letdown is unavailable. Makeup is accomplished using One oper20ie iPI pump (s) with the BWST as the water source.
RCP seal injection 'nt] :ne L's could eventually cause the pressurizer to ' ectne soli d.
- c re.P
-~s.
~
o consideration snould be given to adjusting cooicos, rue suc, :u:
4 4 :: :-
coolant contraction equals or exceeds in vent ory gai, due to Jm1: saa' injection.
Alternatively, drain and/or sample lines can be opened to remove excess reactor coolant.
If normal makeup via MUV-31 is not av3i13cie.
throttle HPI valves (MUV-23, ?4, 25, 26) as required to mai,tain pressarize-level.
When EFP-2 is secured and HPI/PORV cooling is level.
When EF'>-2 1s secured and HPI/PORV cooling is established, RCS invent ory is maintained entirely by HP I.
The pressurizer is in a solid condition unti1 after :1e establishment of DH operation.
Local operation of H?I and DH valves naf 3e necessary. Closely mcnitor MUT level and shut MUV-64 cef]re tne MUT e r-ies.
OP-209 Rev.
Page 41
~
ENCLOSURE 3 l52
'3a p
'.3 af Pressure Control:
With no of f-site power, pressurizer heaters and spray are unavailaole.
4C3 pressure is. maintained by using makeup to " squeeze" the steam buoble in tne pressuri zer.
Minimize insurges and outsurges of pressurizer datar to conserve the residual metal and water heat that keeps the steam bubble in a saturated condition.
During HPI/PORV cooling, pressure is controllec Dy throttling HPI flow (if subcooling margin requirements permit ).
In tnis mode, the PORV should, remain open.
l'.W nae '
OP-209 Rev. 57 page 42 I
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