Letter Sequence Other |
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MONTHYEARML20135H8071985-04-12012 April 1985 Procedure CP.104 Re Transient Occurrence That Leaves RCS Being Cooled by HPI Cooling Project stage: Other ML20135H8001985-04-12012 April 1985 Procedure CP.102 Re Normal Cooldown Project stage: Other ML20127D9261985-05-10010 May 1985 Requests Fee Re 850412 Application for Permanent Exemption from Installation of Reactor Vessel Head Vent Project stage: Approval ML20135H8091985-05-29029 May 1985 Rev 1 to Procedure CP.105 Re Transient Termination Following Occurrence That May Require Pressurizer Recovery Solid Plant Cooldown w/once-through Steam Generator Removing Heat & RCS Subcooled Project stage: Other ML20135H8031985-05-29029 May 1985 Rev 1 to Procedure CP.103 Re Transient Termination Following Occurrence That Leaves RCS Saturated w/once-through Steam Generators Removing Heat Project stage: Other ML20135H7971985-05-29029 May 1985 Rev 1 to Procedure E.07 Re Operator Action Project stage: Other ML20126K2251985-06-17017 June 1985 Submits Fee for 850412 Exemption Request Re Vessel Head Vents (10CFR50.44(c)(3)iii),per 850510 Request Project stage: Other ML20135H8121985-08-12012 August 1985 Rev 33 to Procedure B.4 Re Plant Shutdown & Cooldown Project stage: Other ML20135H7931985-09-19019 September 1985 Forwards Operating Procedures,Per Miner Request,To Aid in NRC Review of 850412 Request for Permanent Exemption from Requirements of 10CFR50.44(c) Re Installation of Reactor Vessel Head Vent Project stage: Request ML20138K6991985-12-11011 December 1985 Environ Assessment & Finding of No Significant Impact Re Util 850412 Application for Exemption from 10CFR50.44(c)(3)(iii) Requirements Re Installation of Reactor Vessel Head Vent Project stage: Approval ML20138K6751985-12-11011 December 1985 Forwards Environ Assessment & Finding of No Significant Impact,Re Util 850412 Application for Exemption from 10CFR50.44(c)(3)(iii) Requirements.Notice Forwarded for Fr Publication Project stage: Approval ML20137B5421985-12-24024 December 1985 Safety Evaluation Supporting 850412 Exemption Request from Reactor Vessel Head Vent Requirement of 10CFR50.44(c)(3) (III) Project stage: Approval ML20137B5311985-12-24024 December 1985 Exemption from Requirements of 10CFR50.44(c)(3)(iii) Re Installation of Reactor Vessel Head Vent & Other Sys Required to Maintain Adequate Core Cooling If Accumulation of Noncondensible Gases Causes Loss of Function of Sys Project stage: Approval ML20137B5151985-12-24024 December 1985 Forwards Exemption from Requirements of 10CFR50.44(c)(3) (Iii),Re Installation of Reactor Vessel Head Vent Based on Verification That Noncondensible Gas Bubble Can Be Safely Removed Via Hot Leg High Point Vents,Per 850412 Request Project stage: Approval 1985-05-10
[Table View] |
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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 ML20044F1091993-05-14014 May 1993 Proposed Permanently Defueled TS Section D6.0 Re Administrative Controls 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 ML20043B2551990-04-26026 April 1990 Rev 0 to Technical Svcs Administrative Procedure TSAP-4400, Environ Qualification Program ML20034A2741990-04-12012 April 1990 Proposed Tech Specs Re Hpi,Chemical Addition & Low Temp Overpressure Protection Sys ML20059E0141990-01-31031 January 1990 Rev 0,App a to CAP-0002, Odcm ML20011E1731990-01-11011 January 1990 Rev 0 to Procedure NDP-039, Sys Required to Support Defueled Mode ML20005E8781989-12-31031 December 1989 Revised Rancho Seco Physical Security Plan,Training Program & Emergency Plan ML20005E3651989-12-27027 December 1989 Process Control Program 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 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 ML20043B2551990-04-26026 April 1990 Rev 0 to Technical Svcs Administrative Procedure TSAP-4400, Environ Qualification Program ML20059E0141990-01-31031 January 1990 Rev 0,App a to CAP-0002, Odcm ML20011E1731990-01-11011 January 1990 Rev 0 to Procedure NDP-039, Sys Required to Support Defueled Mode ML20005E8781989-12-31031 December 1989 Revised Rancho Seco Physical Security Plan,Training Program & Emergency Plan ML20005E3651989-12-27027 December 1989 Process Control Program 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 ML20235U0461987-08-18018 August 1987 Procedure AP.2.06, Validation of Emergency Operating Procedures ML20235U0581987-08-18018 August 1987 Procedure AP.2.07, Verification of Emergency Operating Procedures ML20237L6371987-08-12012 August 1987 Sys Review & Test Program Mgt Overview 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 ML20238D5981987-08-0606 August 1987 Rev 0 to ADM-0037, Maint Administrative Procedures Manual 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 1997-08-19
[Table view] |
Text
05-29-85 Rev. 1 WP0011F
.(
0-0058P CP.103 TRANSIENT TERMINATION FOLLOWING AN OCCURRENCE THAT LEAVES THE RCS SATURATED WITH OTSG(S) REMOVING HEAT
.l.0 VERIFY THAT HEAT TRANSFER IS BEING CONTROLLED.
.1 Verify maximum HPI flow (Rule 1).
.2 Raise SG. levels to 95% on the operate range.
2.0 lE THE CORE FLOOD TANKS ARE EMPTYING, THEN GO TO CP.101.
3.0 ENSURE THE CFT ISOLATION VALVES (HV-26513 AND HV-26514) REMAIN OPEN.
4.0 BEGIN COOLDOWN OF RCS.
.1 Increase OTSG steaming by opening the TBVs or ADVs.
.2 Verify that OTSG continue to provide heat sink for the RCS by:
.1 Remaining pressurized ANO
.2 Incore T/C temperature decreases as OTSG pressure is' lowered.
.3 Continue saturated cooldown by decreasing OTSG pressure.
.4 If the RCS does not cooldown as the OTSG are depressurized, THEN bump a RCP to reestablish heat transfer via natural circulation.
5.0 (( HEAT TRANSFER TO THE OTSG(S) CANNOT BE MAINTAINED, THEN GO TO CP.104 6.0 [E THE RCS SUBC00 LED MARGIN IS RESTORED, THEN START ONE RCP.
.1 Determine that both incore T/Cs and hot leg RTDs indicate subcooled conditions.
.2 If only one OTSG is available then start one RCP in that loop, otherwise start RCP B or D.
8509240244 850919 PDR ADOCK 05000312 p
PM
4 V
j r-t 7.0 1E THE RCS REMAINS SU8C00 LED AFTER STARTING THE RC PUMP, START A SECOND I
RCP; THEN GO TO CP.105, OTHERWISE CONTINUE.
8.0 IF FOR ANY REASON THE RCS BECOMES SUPERHEATED, THEN GO TO ICC SECTION
- P i E.07.
s F
f A
9.0 1[ THE RCP(S) CANNOT BE STARTED,- AND JHE SU8C00 LED MARGIN IS RESTORED
~~ "G!n TT &
j
- DURING THE NATURAL CIRCULATION C00LDOWN,1THEN GO TO CP.105,: OTHERWISE.
n! : 7 CONTINUE.
<^
j
.. d, t a.
1
~
l
~
10.0 WHEN THE CORE FLOOD TANK LEVELS DECREASE TO ZERO FT INDICATED,ETHENlRACK I
IN BREAKERS 20228 AND 20229 AND CLOSE CFT' ISOLATION VALVES HV-26513 AND.i inti,G j,
441 P. J E :
1 HV-26514 TO PREVENT NITROGEN INTRODUCTION INTO.THE RCS,.
l r LPI/0HS COOLDOWN IS TLEr~ a,,
j_
11.0 SELECT LPI/0HS OR NATURAL CIRCULATION C00LDOWN.
SELECTED,' THEN GO TO STEP 13.0, OTHERWISE CONTINUE WITH OTSG COOLING.
..h t EcP ',
12.0 WHEN RCS DEPRESSURIZES TO L;d5 THAN _150 PSIG, THEN 'CLOSE ALL HIGH POINT fl{gl "r j'
1+*
VENT VALVES (HV-20533. HV-20534, HV-20579, HV-20580, HV-21528,m and veni un 1; ;[
HV-21522), EMOV and EMOV Block.
37-2.52.
i
.c
.1 Prior to RCS being cooled to 280*F and 250 psig, sample the primary
.4 ; e (
.o,
coolant for isotopic analysis and notify the Plant Superintendent of ir o e results before placing the LPI/0HS in service.
r -!
m 4
.2 With RCS parameters stable, do not shift LPI suction to the sump until 3-the decision has been made to complete cooldown with LPI/0HS. Alternate a r
cooldown method can be in accordance with OP B.4, Section 6 Natural o i un p
Circulation Cooldown.
a i
13.0 WHEN LPI FLOW HAS BEEN IN EXCESS OF 1000 GPM IN EACH INJECTION LINE FOR t,
AT LEAST 20 MINUTES, STOP HPI PUMPS AND CONTINUE, OTHERWISE, GO TO STEP, -
16.0.
14.0 TRANSFER LPI SUCTION TO RB SUMP.
.1 WHEN the BWST lo-lo-level alarm actuates (minimum time 1/2 to I hour),
t THEN transfer LPI suction to RB sump within 4 minutes of receipt of alarm.
a.
Open valves HV-26105 and HV-26106 to supply heter from the RB
[
emergency sump to the DH suction header.
b.
Close valves STV-25003 AND SFV-25004 to isolate the BWST.
Rev. 1 CP.103-2 o
(
t
_. 1
4 4.
g' s
14.1 c.
' E OH high flow alarm is received, THEN throttle valves SF-26039
}(
(Loop A) and SFV-26040 (Loop B) to below 3000 gpm per pump to
. prevent pump runout.
15.0 GO TO STEP 18.0' t.i ~
~.
I t,
,,3]:
16.0 E THE CONDITIONS OF STEP 13.0 ARE NOT MET BEFORE THE BWST LO-LO-LEVEL 3.
s
' ALARM ACTUATES (MINIMUM TIME 1/2 TO 1 HOUR), THEN:
4 I
i.
.1 I Align one _ HPI pump to take suction from the R8 Sump using the.LPI'. i., ils Id system to provide HPI suction, m ~ i l j*
j r
.2 Stop second HPI pump if running.
.?-
t, i
h
.3' On BWST lo-lo-level, shift one HPI pump suction from the BWST to f-
+
the operable DHS pump discharge.
1 i
i
.4 Align the operable OHS pump suction to the RB sump in accordance
> f r 'I with OP A.8, Section 4.2.
u;
!{'
if.
17.0 ESTABLISH CONDITIONS FOR LPI COOLING.
~. ' E 31lE T'I U
.1 Continue HPI/LPI " piggyback" mode until RCS pressure is 250 psig.
., te r t u ; 2
.2 Maintain 250 psig and continue cooldown until adequate subcooling margin t at, o t i(
is established.
f-
- !i p i
18.0 WHEN ADEQUATE SUBC00 LING MARGIN IS ATTAINED, THEN ESTABLISH LPI/0HR
~
COOLING.
.1 IfF, two decay heat trains are operable, THEN continue with Step '18.5.
J F_
r,.
. k only one decay heat train is operable, THEN continue with Step 18.2.
l l
.2 WHEN the HPI/LPI piggyback operation has been supplying at least 1000
)
gpm to each loop for,20 minutes AND, during this time the RCS pressure., :
j has been less than the maximum pressure for LPI operation alone, THEN:
r-
.1 Verify that the LPI to RCS valves (SFV-26005 and -26006, are open.
.2 Establish normal makeup as required.
i
~
s
.3 Close LPI to HPI valves (HV-26007 and -26008).
i i
r
.3 When two OH systems are operable, THEN follow Steps 18.5 through 18.6.
-f r:-
I
.4 Until two OH systems are operable, continue with Step. 18.8 j
1 1
i Rev. I
{(
CP.103-3 l.
4
f
(.
l CAUTION:
00 NOT ESTA8LSH A FLOW PATH IN ANY SYSTEM ISOLATED BY THE SFAS WITHOUT i
REVIEW Of THE POTENTIAL RELEASE Of RADI0 ACTIVE GAS OR LIQUID.
.10 '
~
18.5 Open the DH Loop A suction manual isolation from reactor vessel valve' i
HV-20005.
l
.6 Establish core cooling with the LPI Loop 'lin'the DHS mode in accordance '
A r
'CE li with OP A.8, Section 4.
. 4.-
i 3
.7 WHEN DH system flow has been gr'eaterlthan 1000'gpm in each line for at' -
l-1:
i least 20 minutes, THEN:
i
.1 Trip'RCPs if running, j
)
.2 Establish'both LPI systems, in DHR mode,
.3 Establish overpressure protection.
-e' i
.8 Maintain seal water flow to all RCPs in anticipation of innedtate t'
restart should LPI flow be interrupted (one RCP/ loop if required).
NN Should RCP restart be required, use the bump start.
l 19.0 CONTINUE COOLDOWN ON LPI. SYSTEM.
.] %.'.
'k I
.1 When on DHR flow, core AT 15 monitored by comparing DHR pump inlet and c
cooler outlet temperature or incore thermocouples and cooler outlet 3
temperatures.
j j
NOTE:
If OHR pump inlet and cooler outlet temperatures are not i --
available, use RCS thermocouples (incure and loop) to j
prevent exceeding cooldown limits.
.2 Continue RCS cooldown to 140*F with core cooling provided by OHR and RCS 1
i pressure controlled by HPI and/or pressurizer control.
.3 If LPI flow is interrupted AN_0 RCPs are not available, THEN continue RCS cooldown in accordance with OP B.4, Section 6.
.4 With core cooling provided by LPI, place OTSGs in wet layup as j
conditions permit. Stop AFW pumps. Ensure at least one AFW pump is 1
available for restart.
.5 _If_ adequate subcooling margin is lost, THEN align one LP! pump to BWST i
or RB sump. Maintain maximum flow until adequate subcooling margin is regained.
20.0 ESTABLISH LONG TERM COOLING PER CP.101, STEP 7.0.
i END Rey. I CP.103-4 i
i
.-