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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20203H7501997-08-19019 August 1997 Rev 10 to Radiological Environ Monitoring Program Manual ML20203H7351997-02-10010 February 1997 Rev 9 to CAP-0002, Off-Site Dose Calculation Manual ML20203H7231997-01-21021 January 1997 Rev 9 to Radiological Environ Monitoring Program Manual ML20059C1861993-12-22022 December 1993 Proposed Tech Specs Amend 186,rev 1 Re Nuclear Organizational Changes ML20058L4371993-12-0909 December 1993 Proposed Tech Specs Amend 187 Including Changes Making PDTS Consistent W/New 10CFR20 Regulations ML20127N3671993-01-19019 January 1993 Proposed Tech Specs Section D6.0,administrative Controls for Proposed Amend 186 ML20059E0191990-08-0303 August 1990 Rev 0 to CAP-0002, Odcm ML20059E0141990-01-31031 January 1990 Rev 0,App a to CAP-0002, Odcm ML20059E0241989-11-22022 November 1989 Rev 3 to Environ Monitoring & Emergency Preparedness ML20246A4081989-08-16016 August 1989 Rev 5 to Inservice Testing Program Plan ML20245L7281989-07-18018 July 1989 Rev 5 to Administrative Procedure RSAP-0101, Nuclear Organization Responsibilities & Authorities ML20246F1241989-07-0505 July 1989 Proposed Tech Specs,Deleting App B in Entirety ML20246A5221989-06-30030 June 1989 Closure Plan ML20245H5781989-06-22022 June 1989 Proposed Tech Specs for Amend 109 to License DPR-54 ML20246E8551989-04-30030 April 1989 Analysis of Capsule RS1-F Smud Reactor Vessel Matl Surveillance Program ML20245L0461989-04-27027 April 1989 Proposed Tech Specs for Proposed Suppl 1 to Amend 134 Re Application for Amend to License DPR-54,clarifying Unacceptability of Analysis Allowing Imperfections Greater than 40% of Nominal Tube or Sleeve Wall Thickness ML20235Y6071989-03-0606 March 1989 Proposed Tech Spec Page 4-17,including one-time Extension for Certain Surveillances Required to Be Performed by 890329 ML20245G1941989-02-28028 February 1989 Procurement Engineering Assessment Plan Final Rept ML20245H8911989-02-28028 February 1989 Revised Proposed Tech Specs,Including Pages 3-30a,3-30b, 3-40a,3-45,3-46,4-18a & 4-75 Re Addition of Operating Requirements Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations ML20195F7701988-11-18018 November 1988 Proposed Tech Spec Section 3.4, Steam & Power Conversion Sys ML20206F2881988-11-15015 November 1988 Proposed Tech Specs 4.6.4.f (Page 4-34i) Re Surveillance of Equipment Required to Verify Vital 120 Volt Ac Bus Operability ML20205R8681988-11-0404 November 1988 Proposed Tech Specs Re Local Leakage Rate Tests & Reactor Bldg Containment Integrity ML20205M8971988-10-28028 October 1988 Proposed Tech Specs Re Nuclear Svc Battery Operability & Surveillance Requirements ML20205L2661988-10-25025 October 1988 Proposed Tech Spec Table 3.14-3, Carbon Dioxide Suppression Zones ML20155G2201988-10-0707 October 1988 Proposed Tech Specs Clarifying Operational Mode Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Sys Train ML20155B8481988-09-30030 September 1988 Proposed Tech Specs Re Reactor Protection Sys Trip Setting Limits,Rcs High Point Vents,Leakage & Leak Detection,Reactor Coolant Inventory & Auxiliary Electric Sys ML20155B4591988-09-30030 September 1988 Proposed Tech Spec Sections 1,3,4,5 & 6,reflecting Numerous Editorial Corrections & Administrative Changes ML20206A8151988-09-28028 September 1988 Rev 0 to, Effluents & Water Mgt Project Action Plan ML20154J5611988-09-19019 September 1988 Proposed Tech Specs,Changing Local Leak Rate Test Requirements for Containment Penetrations ML20154D7591988-09-0808 September 1988 Proposed Tech Specs Re Administrative Controls,Onsite & Offsite Organizations & Facility Staff ML20153E6481988-08-31031 August 1988 Proposed Tech Specs on Limiting Condition for Operation Re Containment Isolation Valves ML20151K1041988-07-28028 July 1988 Rev 0 to Special Test Procedure STP.668, EFIC High/Medium Decay Heat Test ML20207C0831988-07-27027 July 1988 Revised Proposed Tech Specs,Consisting of Rev 1 to Proposed Amend 102,deleting App B ML20151H6131988-07-15015 July 1988 Rev 0 to Matl Control Dept Action Plan for Rancho Seco Nuclear Generating Station ML20196A2281988-06-21021 June 1988 Proposed Tech Specs Providing Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation & Modifying Existing Purge Sys Operation Requirement ML20155K0971988-06-14014 June 1988 Proposed Tech Specs Making Minor Corrections to Table 3.5.5-1, Accident Monitoring Instrumentation,Items 5 & 14 & Table 4.1-1 Items 65 & 92 & Adding Second Note to Table 4.1-1,Item 80 ML20195J4921988-06-10010 June 1988 Proposed Tech Spec Pages 4-69 Through 4-85a,modifying Radiological Effluent Tech Specs to Reduce Count Time Required for prebatch-release Sample Analysis ML20151R0641988-04-15015 April 1988 Rev 0 to STP.1154, Remote Shutdown Panel Test ML20151X3211988-04-0606 April 1988 Rev 1 to Procedure Development Project Action Plan for Temporary & Interim Procedure Change Incorporation as Procedure Rev ML20151V5871988-04-0202 April 1988 Rev 1 to Sys Engineering Action Plan SYSTEM-012, CRD Breaker Action Plan ML20151X2871988-03-31031 March 1988 Rev 0 to Sys Engineering Action Plan SYSTEM-009, Letdown Cooler Thermal & Hydraulic Shock Prevention ML20150D1861988-03-17017 March 1988 Proposed Tech Specs,Correcting Typos & Making Further Editorial Changes to Proposed Amend 139,dtd 860129 ML20196G5131988-03-0101 March 1988 Proposed Tech Specs,Revising Tech Spec 4.1-1,Item 44.c & Tech Spec 4.10.1.E.2 Re Total Quantity of Gaseous Chlorine in Restricted Area ML20147F0771988-02-25025 February 1988 Revised Proposed Tech Spec Table 4.1-1 & Tech Spec 4.10.1.E.2,requiring Performance of Surveillances Only When Gaseous Chlorine Onsite ML20147B1761988-02-15015 February 1988 Rev 0 to RECM-6878, Radiological Effluent Control Manual ML20148D9931988-02-12012 February 1988 Post-Trip Transient Investigation,Assessment & Reporting ML20149K8621988-02-12012 February 1988 Proposed Tech Spec 6.5.1.6.d,identifying Items Not Requiring Plant Review Committee Review ML20196D9091988-02-11011 February 1988 Proposed Tech Specs,Adding Term Dewatering to Process Control Program ML20149G1781988-02-0808 February 1988 Proposed Page 3-19 to Tech Spec 3.3, Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Sys ML20196B8071988-02-0101 February 1988 Proposed Tech Spec Figure 6.2-2, Nuclear Organization Chart 1997-08-19
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20203H7501997-08-19019 August 1997 Rev 10 to Radiological Environ Monitoring Program Manual ML20203H7351997-02-10010 February 1997 Rev 9 to CAP-0002, Off-Site Dose Calculation Manual ML20203H7231997-01-21021 January 1997 Rev 9 to Radiological Environ Monitoring Program Manual ML20059E0191990-08-0303 August 1990 Rev 0 to CAP-0002, Odcm ML20059E0141990-01-31031 January 1990 Rev 0,App a to CAP-0002, Odcm ML20059E0241989-11-22022 November 1989 Rev 3 to Environ Monitoring & Emergency Preparedness ML20246A4081989-08-16016 August 1989 Rev 5 to Inservice Testing Program Plan ML20245L7281989-07-18018 July 1989 Rev 5 to Administrative Procedure RSAP-0101, Nuclear Organization Responsibilities & Authorities ML20246A5221989-06-30030 June 1989 Closure Plan ML20245G1941989-02-28028 February 1989 Procurement Engineering Assessment Plan Final Rept ML20206A8151988-09-28028 September 1988 Rev 0 to, Effluents & Water Mgt Project Action Plan ML20151K1041988-07-28028 July 1988 Rev 0 to Special Test Procedure STP.668, EFIC High/Medium Decay Heat Test ML20151H6131988-07-15015 July 1988 Rev 0 to Matl Control Dept Action Plan for Rancho Seco Nuclear Generating Station ML20151R0641988-04-15015 April 1988 Rev 0 to STP.1154, Remote Shutdown Panel Test ML20151X3211988-04-0606 April 1988 Rev 1 to Procedure Development Project Action Plan for Temporary & Interim Procedure Change Incorporation as Procedure Rev ML20151V5871988-04-0202 April 1988 Rev 1 to Sys Engineering Action Plan SYSTEM-012, CRD Breaker Action Plan ML20151X2871988-03-31031 March 1988 Rev 0 to Sys Engineering Action Plan SYSTEM-009, Letdown Cooler Thermal & Hydraulic Shock Prevention ML20147B1761988-02-15015 February 1988 Rev 0 to RECM-6878, Radiological Effluent Control Manual ML20148D9931988-02-12012 February 1988 Post-Trip Transient Investigation,Assessment & Reporting ML20196B6901988-01-31031 January 1988 Rev 0 to Radiological Effluents Action Plan ML20149E2771988-01-29029 January 1988 Rev 4 to Inservice Testing Program Plan for Pumps & Valves ML20196C8521988-01-27027 January 1988 Rev 2 to Procurement Engineering Assessment Plan ML20148T0071988-01-20020 January 1988 Rev 1 to STP.961, Loss of Offsite Power ML20147H9261988-01-13013 January 1988 Rev 2 to Monthly Surveillance Test of Control Room/ Technical Support Ctr Essential Ventilation Sys Loop A. W/One Oversize Drawing ML20147H8771988-01-13013 January 1988 Rev 3 to Refueling Interval,Special Frequency Control Room/ Technical Support Ctr Essential HVAC Sys Actuation by Rad Monitors & Chlorine Detectors Train a ML20234F4601987-12-21021 December 1987 Rev 5 to AP.310, Offsite Dose Calculation Manual ML20236U1391987-11-20020 November 1987 Emergency Operating Procedure Technical Basis EOP POM-248 ML20236P5221987-11-13013 November 1987 Rev 0 to Special Test Procedure STP.961, Loss of Offsite Power Test ML20236Q0601987-11-10010 November 1987 Rev 1 to Radiological Environ Monitoring Program Manual ML20236X3591987-10-31031 October 1987 Rev 3 to Wire & Cable Program Rept ML20236L1481987-10-30030 October 1987 Rev 4 to Procedure AP.310, Offsite Dose Calculation Manual ML20236P1941987-10-14014 October 1987 Rev 1 to STP.660, Integrated Control Sys Tuning at Power ML20236D3191987-10-0707 October 1987 Rev 0 to Radiological Environ Monitoring Program Manual ML20236B7491987-09-23023 September 1987 Rev 1 to D-0050, Engineering Action Plan ML20235Q7561987-09-0303 September 1987 Twelve Sys Expanded Assessment of Expanded Augmented Sys Review & Test Program Rept ML20234C2331987-09-0101 September 1987 Motor-Operated Valves Program ML20235Z5811987-08-31031 August 1987 Rev 2 to Wire & Cable Program Rept ML20235N8631987-08-26026 August 1987 Rev 0 to Surveillance Procedure SP.486, Monthly Control Room/Technical Support Ctr Ventilation Gas Monitor Test ML20238E2451987-08-24024 August 1987 Rev 1 to Maint Administrative Procedure MAP-0009, Preventive Maint Program ML20235U0581987-08-18018 August 1987 Procedure AP.2.07, Verification of Emergency Operating Procedures ML20235U0461987-08-18018 August 1987 Procedure AP.2.06, Validation of Emergency Operating Procedures ML20237L6371987-08-12012 August 1987 Sys Review & Test Program Mgt Overview Manual ML20238D5981987-08-0606 August 1987 Rev 0 to ADM-0037, Maint Administrative Procedures Manual ML20235N5461987-08-0606 August 1987 Rev 1 to Surveillance Procedure SP.485A, Refueling Interval,Special Frequency Control Room/Technical Support Ctr Essential HVAC Sys Actuation by Rad Monitors & by Chlorine Detectors Train a ML20236J7071987-07-15015 July 1987 Expanded Augmented Sys Review & Test Program (Easrtp) Evaluation Plan ML20236J6921987-07-15015 July 1987 Expanded Augmented Sys Review & Test Program Methodology Guidelines ML20216H8221987-06-25025 June 1987 Rev 3 to Inservice Testing Program Plan,Rancho Seco Nuclear Generating Station ML20238E2501987-06-23023 June 1987 Rev 3 to Inservice Testing Program Plan for Pumps & Valves ML20214K3051987-04-24024 April 1987 Nuclear Records Mgt ML20214K2981987-04-24024 April 1987 QA Records 1997-08-19
[Table view] |
Text
_
'.) O i
EFFECTIVE DATE 02-18-87
"" 2 O s.o:,
LOSS OF SUBCOOLING I
POST TRIP WINDOW =
That
/
i 1 t SATURATION
_. .O. .
z curve VARIABLE SECONDARY
'SUBC00 LED MARGIN _
SYSTEM SATURATION
= TEMPERATURE O
p'2 nan E88ljp "y;.4
O.s ,
INFORMATION PAGE h ,
i 1.1 To prevent mechanical damage to all the RCPs only two RCPs, one in each loop, should be operated. If they fail, the two pumps which were idle should be started even if mechanical 1
damage is again likely.
2.0 HPI should be initiated by actuating SFAS Channels 1A and 1B at panel HIRC ONLY. and IMMEDIATELY opening RCP seal return valves SFV-24004 and SFV-24013.
If pressurizer level is recovered during HPI, the pressurizer may not be at saturation conditions, and pressure control 'may -
g
_not be as stable as expected. ,
- 3.1 AFW must be started any time OTSG level is required to be !
controlled at 95% (381" EFIC) 3.2 Imvel will control at 50% (317" EFIC) if "ECC SETPOINT" is not selected when RCP's are tripped 3.3 If RCP's are still running, the "ECC SETPOINT" cannot be actuated.
3.4 CONTfNUOUS AFW flow raises OTSG thermal center above i
951 invel increase may be gradual to avoid overcooling .
E flow must be continuous and level must HQI decrease.
AFW X&I be throttled to hold a constant level during an
! OVERC0011NG regardless of setpoint.
I i
4.0 A.65 " Radiation Detection Gaseous System".
l A.52 " Hydrogen Monitor and Purge System".
l
. O l hv. 1 i
E.03-2
. . _ _ . _ _ - . _ _ _ . . _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ . , . . , . - _ . . , . _~_ . _ _ _ _ . _ . - . _ _ _ _ _ _ _ _ _ _ . _ . , , . _ _ . . _ . . . _ , _ . _ _ _ _ . . _ _
O )
9 ..
- x. ;
O 's. -
E.0a IDSS OF SUBCOOIJNG .
.__ CAUTION IF RCPS ARE NOT TRIPPED WITHIN TWO MINUTES, THEN ONE (1) PER IDOP MUST BE LEFT RUNNING UNTIL SCM IS RESTORED.
- 1. 0 TRIP ALL RCPs TMMEDIATELY
.1 2 the RCPs are 10.I tripped within the required 2 minutes i
.IHEt[ shift to 1 RCP per loop. (
)
.1 2 the rimaing RCPs trip before SCM is recovered
.THEt[ start the non tripped RCPs.
2.0 INITIATE AND CONTROL HPI (RULES 1 and 2).
.1 Manually initiate SFAS Channels 1A and 1B.
e-- O *
.1 Immediately take manual control and open RCP
. seal Return Yalves. (SFV-24004 and STV-24013)
.2 Balance HPI Flow .
- 3. 0 MANUALLY INITIATE EFIC CHANNEIE A & B i AND INITIATE "ECC SETPOINT" FOR CHANNEIS A & B (RULE 3)
.1 2 any RCPs are ri==ia:
.IHEt[ manually raise OTSGs level to the "ECC SETPOINT".
(381" EFIC or 957.)
4.0 PLACE RB H.' MONITORS (AE-53811, AE-53812)
AND R-15100 IN SERVICE O .
Rev. 1 E.03 ~
_ _ _ _ - - - - - - I
O O .
INFORMATION PaGE h
5.0 Typical loss of SCM Trace Due to Overcooling I
POST TRIP r Tg SATURETION CURVE VARIABIE -
~
SECONDARY =--
SUBC0012D .
MARGIN _
N -
7 SATURATION -
f ~ TEMPERATURE 6.0 Acoustic monitors for pressurizar code safeties, EMOV, Vent and Hot Img Vents should be checked on IDADS for indication of possible leakage flow paths.
On IDADS - RCS - Z1122 to Z1141, Z9109 to Z9120 for position indication open/olosed or in % open/ closed.
l l
O \
Rev. 1 E.03-4
G .
s '
- ../ .
L l.
O E.03
! LOSS OF SUBCOOllNG '
1 i
l 5.0 IE EXCESSIVE HEAT TRANSFER EXISTS i
(GUIDELINE 3) 4 .
.1 Go to E.05, " Excessive Heat Transfer",
otherwise continue. l l
! i 1
-i 4
i f
i
! 6.0 ISOLATE POSSIBLE RCS LEAKS I
.1 SFV-22025 Imidown Isolation Valve
.2 HV-21505 EMOV Block j .3 PSV-21511 EMOV i .4 HV-21510 PZR Spray Block j .5 PV-21509 PZR Spray Valves
! PV-21520 I .6 HV-21515 PZR Vents i HV-21517 i i HV-21528 i i HV-21522 i
- .7 SFV-70003 PZR Samples
- SFV-70001 HV-21518 l .8 HV-20533 Hot Leg Vents HV-20534 1
l O av-=o5va HV-20580 1 l I
l 4 hv. 1 t
E.03-6 1
i.-.+ de &, 4 ,.w.-, s .&--5 44; 44sLe.A-e.-ee a-.--.es meM J-d.-s'= a+ - +-,e a-e.g.-4 an. .54E-mi.--8E S - 4d .2a h- 1n M4J4-:m----+4V4 A4A--.244, J A
- - _ an-.u Am~u an.m 44A mm.d. ,.
k s
4 f
l INFORMATION PAGE h' !'
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,cw.--,-,.*--......-r-.,-.r.--e.r--r-w.---mo-ww--.r-- w*w-.-=~r-w+--r,- r,- =-%y----<ww.,w*w.w-~-.,--c-----=~.--.v.ww1.-..%~-- - --
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O = o3 LOSS OF SUBC00 LING k
l 7.0 E SUBC00 LING MARGIN IS RESTORED i
(GUIDELINE 1) ,
L - :
3
.1 Go to Step 12, otherwise continue.
8.0 E SUPERHEATED (GUIDELINE 5)
.THEN i
{
) .1 Go to E.07, "lCC.", otherwise continue. !
I !
3 9.0 E CORE FLOOD TANKS ARE EMPTYING :
!O t
.IHgg
. m . _ --
j .1. Go to CP.101, a *or IACA is indicated, t otherwise conti -
l l
l 10.0 E PRIMARY TO SECONDARY HEAT TRANSFER
! EXISTS IN BOTH OTSGs (GUIDELINE 2)
- rum
- . 1 Go to CP.103, otherwise continue.
i i i
i !
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t
! Rev. 1
, E.03-7 i
.-,-,.,-_-.,----..-mm--,_
. .~.,,,,..-,---,-,--.--.---.,,y-, . .,,_-,-,-e,..., , . , - . , , . , , - , . . . ,--,_,r .,- . _ _ - ----.,--- -.r,.,,------,,..,.-,,,,--y.,
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3)
.2-INFORMATION PAGE h 11.0 Typical loss of Heat Transfer Trace after a Loss of SCM.
I POST TRIP WINDOW That
/
i f SATURATION -
CURVE Q
/'4.
VARIABLE SUBC00 LED SECONDARY MARGIN _
SYSTEM SATURATION m TEMPERATURE e
Rev. 1 E.03-8 e
,m ,
1 O s.oa l LOSS OF SUBC00 LING 11.0 IE PRIMARY TO SECONDARY HEAT TRANSFER IS LOST IN ONE OR BOTH OTSGs (GUIDELINE 2)
THEN
.1 Go to E.04, " Loss of Heat Transfer".
~ ~
.O. . . . . . . . ..
STATUS THE RCS IS SATURATED. A SMALL BREAK IS INDICATED. CORE COOLING IS PROVIDED BY ONE OTSG WHILE HPI MAINTAINS RCS INVENTORY.
O Rev. 1 E. 03- 9
9, i
INFORMATION PAGE h NOTE Any water put into the pressurizer to recover level is or will be subcooled when subcooling margin is regained. Even though the !
pressure may be artificially held up by compressing the steam bubble, the time frame to achieve a true saturate pressure will be dependent on the degree of subcooling and the amount of water in pressu'rizer that must be heated to saturation. If the Pressurizer low level cut i
off (40" indicated) de-energized pressurizer heaters, they have to be reset at H1RC for groups 2-3-4.
12.0 Typical Loss of SCM after an SCM Recovery.
roer m e
y ,
)
- = e J-
== f._iiHlim 13.0 Reactor Vessel Thermal Shock Criteria.
RCS temperature dropped below 500*F and exceeded a 100*F/hr cooldown rate.
D.E RCS temperature dropped below 500*F and RCPs are off and HPI flow exists through any HPI injection valve as indicated on the HPI flowmeters.
The PTS limit takes priority over the fuel pin in compression limit.
t i
o
~
Rev. 1 E.03-10
., -...-.--.n.. -
,,,,.._..-..-..,--,,-,...n -m. ,.,-,w. -.n. , . - ,,. v.w-v-n-.---n,---, - , - . . , .- ,--, .,..
i 3 .
E.03 LOSS OF SUBcoouNG l 1
l STATUS ENTRY FRoM STEP 7 ADEQUATE SUBCooLING MARGIN HAS BEEN ESTABLISHED ,
I 12.0 JE ADEQUATE SUBC00 LING MARGIN IS LOST
- DURING THE FOLLOWING STEPS OF THIS PROCEDURE (GUIDELINE 1)
THEN
@ .1 Go BACK to Step 8, otherwise continue.
I.
- 13.0 THROTTLE HPI AS NECESSARY TO PREVENT
! EXCEEDING THERMAL SHOCK LIMITS IE tt.ermal shock limits have been exceeded ,
MN
.1 Stablize temperature and pressure below the Interim Brittle Fracture curve and DEPRESSURIZE if in the restricted region. Pressurizer spray, pressurizer vents or EMoV can be used as required to avoid or exit the i restricted region. (FIGURE 1)
.2 The PTS limit remains in effect for the remainder of the cooldown. l 1
l0 .
i Rev. 1 l E.03-11 i
i
. _ , _ . - , . . . - , , --m.-, --,_..----,,...--~---,,.---,.,-,-.--.--.,,e-- _m , , ,, .-. ,- ~ , ~ - ~ . _r- . . mm.,-- -m . - - - , - - - - - -
l
! INFORMATION PAGE g l i !
l 1
I 15.0 ECC setpoint will reset upon first RCP start. It will have to be activated again if RCP's cannot be run continuously.
15.1 RC Pump start interlocks.
<30% Reactor power RCP motor oil lift > 1750 psig RCP motor upper bearing oil level 2 inches a RCP. motor' lower bearing oil level i 2 inches. W.
Seal injection flow > 3 gpm .
RCP CCW flow > 307 gym .
, To start fourth RCP T. > 500 7 Motor 86 Lockout (Motor Protection Relay)
Normal - Green Light Dim i Abnormal - Green Light Bright i 15.2 Normal pump start cycle limits apply. :
i Number of allowed RCP motor successive starts with motor i
! initially at ambient temperature is 3 starts. l Number of allowed successive starts with motor initially at t j rated temperature is 2 starts. An interval of 20 minutes '
1 with motor running, or 40 minutes with motor not running, !
j must elapse before an additional start.
) 16.0 When the Condenser is available, use TBV's.
i l
l 5
i f
1 i Rev. 1 i i E.03-12
I O o ..
i O E.03 l IDSS OF SUBCOOLING .
I CAUTION DO NOT DELAY BETWEEN STEPS 14 AND 15 14.0 TAKE MANUAL CONTROL AND CLOSE OTSG A AND B ADVs AND TBVs CAUTION STARTING RCPs MAY CAUSE SIGNIFICANT DECREASES IN RCS ,
TEMPERATURE, PRESSURIZER LEVEL, RCS PRESSURE, AND SUBC00 LING MARGIN DUE TO THE POSSIBILITY OF VOIDS IN THE SYSTEM.
15.0 START DJ1E RCP PER LOOP
.1 Preferred RCP starting sequence is D, B, A & C. .
O
.2 2 SCM is 1ost when si.rtin, RCP l l .IHEN allow RCP to run up to 2 minutes while q
- attempting to recover SCM, otherwise continue.
i i ;
1 16.0 STABILIZE Tc AT PRESENT VALUE WITH i TBVs OR ADVs !
- 17.0 IE RCPs CANNOT BE RUN lO
- .1 Go to OP B.4, Section 6.0, otherwise continue.
i Rev. 1 j E.03-13 I
O O .
x.
MFORMATION PAGE h O
l 1
0 Rev. 1 E.03-14
)
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- s.
4 O N
~
z.oa .
1 IASS OF SUBC00 LING l 18.0 E PRIMARY TO SECONDARY HEAT TRANSFER l: IS LOST (GUIDELINE 2) -
32iEN ,
I
.1 Go to E.04, "Ioss of Heat Transfer",
. otherwise continue.
i ,
19.0 OPEN PZR SPRAY BLOCK VALVE (HV-21510)
, .1 Verify RCS pressure does not decrease.
f 20.0 E AN SGTR IS INDICATED (GUIDELINE 4)
- .IHEN
.1 Go to E.06, "SGTR", otherwise continue.~ -
~
STATUS
] RCS IS SUBC00 LED WITH RCPs RUNNING AND CORE COOIJNG BY OTSG.
21.0 GO TO SECTION CP.105 4
i l
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! E.03-15 .
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i FIGURE 1 REACTOR COOLANT SYSTEM INTERIM FRACTURE LIMIT O
4 NO FORCED FIM AND THERMAL SHOCK OPERATING REGION
[
l l
- NOTE
- Maintaining the reactor SATURATEN 3000- coolant subcooled takes precedence CURVE over the Interim Brittle Fracture ysM \
l Curve (B&W 74-1122501 page 8) NO FORCED FIDW \\
2800 OPERATlNG MAND g i I INCORE TC's TO MONITOR W/HPI gai 2600- PREFERRED ALTERNATE i " PT5 CLRVE
- 1) 79254 79256
$ 2400- 8
! 2) Teesa Ts2s0 _j3,,t,""
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- 4) T9272 79266 \ r [/j {
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! INDICATED RC TEMPERATURE F
{ Rev. 1 i E.03-16
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. n E W e n l .----__= ' - - - - - -