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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
-._ ,
EFFECTIVE DATE 02-18-87 E.04 <
O LOSS OF HEAT TRANSFER POST TRIP I WINDOW That
=
i O -
SATURATION CURVE VARIABLE SUBC00 LED SECONDARY MARGIN _
SYSTEM
~
SATURATION
= TEMPERATURE l
O -
Ret 5 b0 $000K 0 00 2 4
. R J .:- -
1 INFORMATION PAGE g l l
1.0 Either MFW or AFW must be capable of feeding an OTSG.
] 2.0 Acoustic monitors for pressurizer code safeties and EMOV should be checked on IDADS for indication.
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^
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O s.o4
, LOSS OF HEAT TRANSFER e
- 1. 0 E FY IS AVAILABLE !
! M
! .1 Go to step 7, otherwise continue.
-! 2.0 E RCS PRESSURE INCREASES TO EMOV SETPOINT BEFORE FW IS ESTABLISHED E
, .1 Go to step 5, otherwise continue.
- 3. 0 ATTEMPT TO ESTABLISH FY i n .1 Manually initiate EFIC channels A & B.
() .1 Place AFW pump R-318 on electric drive;
- (RULES 3 & 4)
.2 E AFW la not available M use MFW Pump and/or Condensate Pump. ;
i 4.0 E FW IS REESTABLISHED i
j
.1 Go to step 7.0, otherwise continue. ,
s l
Re s E04-3
a..
INFORMATION PAGE O O
O nov. 5 E.04-4
o e .
l l E.04 l IDSS OF HEAT TRANSFER STATUS ENTRY FROM STEP 2, 4, 9,12, OR 15 CAUTION WITH NO HPI/MU FLOW AVAILABLE DQ. HQI OPEN THE EMOV.
5.0 INITIATE HPI C0011NG (RULE 2)
.1 Manually initiate SFAS channels 1A and 1B.
! .1 Inunediately take manual control and open RCP Seal Return Isolation Valves (SFV-24004 and SFV-24013).
.2 Balance HP1 flow.
! .3 Open EMOV Block Valve (HV-21505).
l .4 Open EMOV (PSV-21511). .
.5 Run one RCP as long as Subcooling Margin is anaintained.
O .6 Turn off Pressuriser heaters. '
.2 E'the EMOV can not be opened '
'!2iEt[ do HQI throttle HPI until SCM existe '
AND incore T/cs decrease.
STATUS GOING TO CP.104, PLANT CONDITIONS ARE:
THERE IS NO HEAT TRANSFER TO EITHER OTSG. NATURAL CIRCULATION DOES NOT EXIST AND CANNOT BE STARTED DUE TO A TOTAL LOSS OF FEEDWATER. THE OTSGs ARE DRY AND THE CORE MUST BE C00!J:D BY HP! COOLING.
6.0 GO TO CP.104 i
l Q .
hv. 5 E.04-5 l .
~
O O -
INFORMATION PAGE g 7.0 EFIC initiate on OTSG Low Level 13.5", controls at 27.5".
8.0 Verify alarms with CFT A and D level and pressure.
Core Flood Tank low level alarms at 12.7 ft.
Core Flood Tank low pressure alarms at 585 psig.
O O
Rev. 5 E.04-6 -
E.04 LOSS OF HEAT TRANSFER STATUS ENTRY FROM STEP 1 OR 4 FW IS AVAILABLE 7.0 MAINTAIN APPROPRIATE OTSG LEVEL (RULE 4) 8.0 E CORE FLOOD TANKS ARE EMPTYING nun
.1 Go to CP.101, otherwise continue.
STATUS .
O CORE FLOOD TANKS EMPTYING IS AN INDICATION OF A LOCA.
CP.101 PROVIDES INSTRUCTIONS FOR LONG-TERM COOLING FOLLOWING A MAJOR LOCA. PRIMARY TO SECONDARY HEAT TRANSFER IS LOST AND CANNOT BE REGAINED.
4 9.0 E AT ANY TIME PRIOR TO RESTORING HEAT TRANSFER, RCS PRESSURE INCREASES TO 2450 PSIG (EMOV SETPOINT) DE AN RV PTS LIMIT (IF APPLICABLE)
- nun
.1 Go to step 5, otherwise continue.
l0 Rev. 5 E. 04-7 i
l
) l 1 !
l INFORMATION PAGE a [
! . W i i !
I I
1 !
i 1
11.0 For incore temp, use SPDS Normal or Post Trip Display with !
- incore button or ICC Display (question mark following value !
j means it's a questionable ' reading).
l Computer Point G-643 Highest VALID incore temp.
l For secondary Sat Temp. use SPDS Post Trip Display purple vertical line or use OTSG A and B Pressure. l
}'
I l l
1 i
! . h-i i
l 4
! r i ,
4 12.0 A RCP bum? means start the pump, allow starting current to die ,
) off, then al,ow the pump to run 10 seconds before stopping. '
j RCP interlocks.
1 < 30% Rx Power RCP Motor 011 Lift > 1,750 psig .
) RCP Motor Upper Bearing 011 1.evel i 2 inches. '
t RCP Motor Lower Bearing 011 Level 2 inches.
1 Seal Injection Flow > 3 spm. ,
i RCP Pump / Motor CCW Plow > 307 gpm.
I To start Fourth RCP To > 5007.
l Motor 86 Lockout (Motor Protection Relay).
i Normal - Green Light Dim
{ Abnormal - Green Light Bright. ,
i Rev. 5 ,
E.04-8 '
I i'
2 E.04 :
LOSS OF HEAT TRANSFER 1
l l
10.0 .IE RCPs ARE OPERABLE {
i i .M i :
! .1 Go to step 12, otherwise continue.
,l 11.0 RESTORE PRIMARY TO SECONDARY HEAT l
)
1 TRANSFER (RCPs INOPERABLE) - l l .1 2 the RCS is Subcooled j .1 Open the Hot Les HPVs and maintain RCS pressure, j .2 lower OTSG pressure until secondary Tsat is i 90 - 110*F lower than incore temperature.
! .3 Increase OTSG level to "ECC SETPOINT". l l (381" EFIC or 957.)
l
.2 2 the RCS is Saturated !
Lower OTSG pressure until secondary Tsat is I
l .1 .
i Q' .2 40 - 607 lower than incore temperature.
Increase OTSG level to "ECC SETPOINT". I l (381" EFIC or 957.) j
.3 2 heat transfer has been established !
] M Go to step 16. t a !
! .4 2 heat transfer has HQ.I been established :
i M Go to step 5. l l
f t
i 12.0 RESTORE PRIMARY TO SECONDARY HEAT !
l TRANSFER (RCPs OPERABLE) l l .1 E RCSs IS Subcooled i
M start one RCP. l
.1 Preferred starting sequence is D, B, A, C.
l j .2 E the RCS is saturated 1 .1 Bump one RCP every 15 minutes.
1
.2 Lower 0750 pressure until secondary Tsat is '
90 - 1107 lower than incore temperature. !
.3 WHEN all operable RCPs have been bumped ;
M so to step 13. !
O i Rev. 5 I E.04-9 1
- . i
INFORMATION PAGE g
13.0 Indications of 11 eat Transfer Incore Temp within 107 of Th.
Max expected RCS A T of 50' to 007.
Tc approx equal Tsat OTSG.
Iowering OTSG Pressure causes corresponding decrease in Tc.
O 10.1 C.41 Recovery form SFAS Actuation.
O Rev. 5 E. 04- 10
- O G ;
i t
j E.04 :
LOSS OF HEAT TRANSFER i
I
! 13.0 E HEAT TRANSFER IS ESTABLISHED i THEN ;
{
j .1 Go to step 16, otherwise continue.
14.0 START AND RUN ONE RCP TO INDUCE '
HEAT TRANSFER i i
! .1 2 at least one hour has passed since Rx trip and any !
i RCP is capable of being started. even if RCS is saturated !
! IEEg start and run one RCP Preferably in the loop I which has the 0750 with the highest level !
i i
15.0 E HEAT TRANSFER M M BEEN ESTABLISHED j 1 233g .
{
O .1 Go to step 5, otherwise continue. '
i
! I 1 STATUS i l
l ENTRY FROM STEP 11 I I i i
CAUTION !
PRIOR TO THROTTLING HPI FLOW BELOW 105 GPM PER PUMP, HPl !
WIN! FLOW VALVES SFV-23645, SFV-23646 AND MAKEUP TANK OUTLET j VALVE SFV-23508 MUST BE OPEN, t i
i l i
10.0 .WHEN HEAT TRANSFER HAS BEEN ESTABLISHED ,
I IHEN !
I 1 .1 Secure from HP! cooling if initiated.
! .1 Establish letdown and establish makeup.
j .2 Close EMOV (PSV-21611). f
.3 2 EWOV (PSV-21511) does not close ;
THEN close EMOV block valve (HV-21505). !
O i
! hv. 5 l E.04-11 i l
L j
i o o . ;
\
t INFORMATION PAGE i O
i l l
17.0 Reactor Vessel Thermal Shock Criteria RCS temperature dropped l l below 5007 and exceeded a 1007/hr cooldown rate !
I QB
- RCS temperature dropped below 5007 and RCPs are off and HPI '
! flow exists through any HPI injection valve as indicated on i the HPI flowmeters.
i The PTS limit takes priority over the fuel pin in compreselon ,
limlL t j .
I l
l 18.0 SPDS Post Trip Display 0750 Tsat Line (purple vertical line) i should be approx equal to Tc.
Il i 075G Tsat can also be read using computer. point 0-161.
19.0 Indications of Subcooling Margin.
System pressure /incore temperature above Variable Subcooling Margin line on SPDS.
j Saturation Temperature for RCS pressure 507 or greater than incores or Th.
i t j > 50' subcooling read on subcoollag margin monitors, j l i i :
i !
1 l I
) . I 1
i I
j i i
l Rev. 6 l E.04-12 !
l i
f
E.04 !
IDSS OF HEAT TRANSFER 17.0 E Rx VESSEL THERMAL SHOCK LIMITS EXCEEDED m :
.t Stabilize temperature and pressure below the Interim l Brittle Fracture curve and DEPRESSURIZE if in the !
restricted region. Pressuriser spray, pressuriser vents or EMOV can be used as required to avoid or exit the t
restricted region. !
.2 The PTS limit remains in effect for the remainder of the cooldown.
I r l 18.0. CONTROL HEAT TRANSFER RATE I
i .1 Adjust TBV or ADY position to maintain RCS i l Lemperature at present value, i 1
Q ,
19.0 E THERE IS ADEQUATE SUBC00 LING MARGIN -
THEN !
.1 Oo to CP.105, otherwise continue. I
, STATUS {
THE RCS IS SATURATED. A SMALL BREAK 15 INDICATED. COOLDOWN WITH l THE OT50 CAN BE PERFORMED WHILE HPI MAINTAIN 5 RCS INVENTORY. I 20.0 GO TO CP.103 i l
O Nov. 5 E.04-13
O O -
FIGURE 1 REACTOR COOLANT SYSTEM INTERIM FRACTURE LIMIT O NO FORCED FLOW AND THERMAL SIIOCK OPERATING REGION NOTE: Maintaining the reactor hATURATION 3000.. coolant subcooled takes precedence pURVE over the Interim Brittle Fracture ysM Curve (D&W 74-1122501 page 6) NO FORCED PMW \
2000- OPERATING AND INCORE TC's TO MONITOR W/IIPI m 2000- PREFERRED AI. TERNATE
'm C HVE h 1) T9254 70250 M 2400- 2) m 50 m 00 [1.d-- ~-
1 P d 3) TV203 T9252 NDT'UM T D'
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- 4) T9272
- 5) T0200 79200 79270 7/
b]2000- f
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8 u 8 o 1000-y/-p /g f f 7 1400- /
}1200- [, -
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