|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARB17848, Startup Test Rept Cycle 7. with1999-09-30030 September 1999 Startup Test Rept Cycle 7. with ML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20211G1341999-08-24024 August 1999 Proposed Tech Specs Replacement Pages,Incorporating Addl Info for Pending TS Change ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210D4331999-07-31031 July 1999 Material Recovery Plan, for Haddam Neck Plant ML20210F5121999-07-28028 July 1999 Rev 0 to CY-HP-0031,Haddam Neck Plant Health Physics Dept Technical Support Document, Bounding Dose Assessment for Offsite Radioactive Matls ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20195C8591999-06-0303 June 1999 Proposed Tech Specs Incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 3.5.2,3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys. Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20199K4861999-01-18018 January 1999 Proposed Tech Specs to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TSs to TRM ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20210D4331999-07-31031 July 1999 Material Recovery Plan, for Haddam Neck Plant ML20210F5121999-07-28028 July 1999 Rev 0 to CY-HP-0031,Haddam Neck Plant Health Physics Dept Technical Support Document, Bounding Dose Assessment for Offsite Radioactive Matls ML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program ML20154G5311998-10-0707 October 1998 Rev 4 to Project Procedure PP-02, Accident Mitigation Sys Review ML20154G5351998-10-0606 October 1998 Rev 3 to Project Procedure PP-04, Regulatory Review Procedure ML20154G5521998-10-0606 October 1998 Rev 5 to Project Instruction PI-01, Svsr Implementation Checklists & Workbook ML20154G5391998-10-0606 October 1998 Rev 6 to Project Procedure PP-07, Discrepancy Repts ML20154G5251998-10-0505 October 1998 Rev 4 to Independent C/A Verification Program for Millstone Unit 2 Audit Plan ML20154A7401998-09-24024 September 1998 Spent Fuel Pool Cooling & Makeup Monitoring Program ML20236Q9341998-06-30030 June 1998 Rev 4 to PI-01, Sys Vertical Slice Review Implementation Checklists & Workbook ML20236Q9321998-06-25025 June 1998 Rev 4 to PP-01, Sys Vertical Slice Review ML20153C6221998-06-18018 June 1998 Rev 1 to CP 3804L, PASS Containment Air Sample ML20153C6171998-06-18018 June 1998 Rev 2 to CP 3804K, PASS Rcs/Rss Sample ML20249B7841998-06-12012 June 1998 Rev 1 to CY-HP-0025,HNP Health Physics Dept Technical Support Document, Background Cs-137 Concentration in Soil ML20153C6291998-05-31031 May 1998 Rev 0,Change 1 to CP 3804M, PASS Ventilation Samples ML20247R8081998-05-20020 May 1998 Rev 1 to Epop 4455F, Rumor & Inquiry Control ML20247Q6671998-05-20020 May 1998 Rev 1 to Epop 4422A, Thermal Hydraulic Evaluation Methods ML20247R7541998-05-20020 May 1998 Rev 1 to Epop 4455A, Nuclear News Manager ML20247R7851998-05-20020 May 1998 Rev 1 to Epop 4455C, Technical Assistant ML20247R7921998-05-20020 May 1998 Rev 1 to Epop 4455D, News Releases ML20247R7491998-05-20020 May 1998 Rev 1 to Epop 4455, Manager of Public Info ML20247Q7011998-05-20020 May 1998 Rev 1 to Epop 4490, Implementation of Recovery Operations ML20247Q6901998-05-20020 May 1998 Rev 1 to Epop 4475A, External Resources Coordinator ML20247Q6771998-05-20020 May 1998 Rev 1 to Epop 4428I, Direction of Posl Field Sampling ML20216B1791998-05-0808 May 1998 Independent Corrective Action Verification Program for Millstone Unit 3,Interim Rept,Executive Summary ML20247Q6491998-05-0707 May 1998 Revised Nuclear Emergency Planning Operating Procedure Index ML20217Q9101998-04-30030 April 1998 Matl Recovery Plan ML20247H4581998-04-0909 April 1998 Rev 19 to EOP 35 E-0, Reactor Trip or Safety Injection B17159, Backlog Mgt Plan for Unit 31998-03-31031 March 1998 Backlog Mgt Plan for Unit 3 ML20216K0641998-03-20020 March 1998 Rev 2 to Oversight Plan NNECO - Millstone Site Independent Third Party Oversight Program ML20216H7101998-03-13013 March 1998 Independent Corrective Action Verification Program Status Rept ML20216H7191998-03-0303 March 1998 Independent Corrective Action Verification Program Status Rept 1999-07-31
[Table view] |
Text
. _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _
- c. JUN 3 1988
, NUMBER TTlu REV. ISSUE /DATE
- FR C.1 RESPONSE TO INADEQUATE CORE COOLING Rev. 2 A. PURPOSE nis procedure provides actions to restore core cooling.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is entered fmm F-0.2, CORE COOLING Critical Safety Function Status Tree, on either RED condition.
i Page 1 of 9 80102502N 13 PDR ADOCK h$000 PDR 1 P
JUN 3 1988 NUMBER TIT 12 REY. ISSLTJDATE FR C.1 RESPONSE TO INADEQUATE CORE COOLING Rev.2 ;
I
.J STEP ACT10N/ EXPECTED RESPONSE RESPONSE NOT OBTAINED r 7 CAUTION 1 IF THE KW:T LEVEL DECREASES TO LESS THAN 130,D0 GALLONS, THE SI SYSTEM SHOULD BE ALJGNED FOR \
RHR RECIRCULA7 ION USib'G ES 13, TRANSFER TO RHR l RECIRCULATION L Jll l
l 1 VERIFY S1 VALVES IN PROPER hiANUALLY ALIGN VALVES AS l Eh1ERGENCY ALIGNhiENT NECESSARY.
j 2 VERIFY SI FLOW IN ALL TRAINS: START PUbiPS AND ALIGN VALVES AS NECESSARY.
o Check charging pump flow indicators - TRY TO ESTABLISH ANY OTTIER INDICATE FLOW 111G11 PRESSURE INJECTION SOURCE OR PATTI:
o Check llPSI pump Ah1P meters -
GREATER TliAN 115 AhtPS o Start metering pump and adjust for nuxtmum speed.
o Check LPSIpump AhiPmeters-GREABiR T11AN 60 AhiPS o IJne up for fill headerinjection:
I
- a. Open all four loop fill !
header hiOVs. !
i
- b. Open fill header flow control ;
valve (FH FCV 295) and bypass valve (Fli htOV 344). l
- c. Ensure charging pumps running. i 3 CliECK RCP SUPPORT SYSTEhtS TRY TO ESTABLISil SUPPORT AVAILABIA SYSTEhtS. i r
o Check Component Cooling Water j System -
j IN SERVICE
}
o Check RCP seal water supply and I retum system - 1 IN SERVICE 4 CliECK CORE EXIT QQIQ STEP 7. 4 111ERhiOCOUPLES . I LESS T11AN 1200' F !
l l
l Page 2 of 9
JUN 3 1988 NUMBER Tm2 REV. lSSLTJDATE I FR C.1 RESPONSE TO INADEQUATE CORE COOLING Rev.2 !
STEP ACT10N/ EXPECTED RESPO!!,E RESPONSE NOT OBTAINED 5 CHECK RVLIS PLENUM INDICABON:
- a. Check indication - a. E increasinJ, GREATER Di&N 15 % IEEN RET JRNIQ Step 1. ,
E NOIincreasing, l DIEN QQIQ Step 6. j
- b. RERJRN IQ procedure and I step in effect !
l 6 CHECK CORE EXIT i MERMOCOUPIES:
- a. Check temperature - a. E decreasing, LESS TilAN 700' F TIEN RETURNIQ Step 1.
E EQIdecreasing.
TlIEN QQIQ Step 7.
NOTE: THIS PROCEDURE SHOULD BE CONTINUED WHILE I OBTAINING HYDROGEN SAMPLE IN STEP 7.
i 7 CIECK CONTAINMENTIIYDROGEN CONCENTRADON:
- a. Obtain a containment air sam 31e with the Post Accident Samping System
- b. Check liydrogen concentration - b. Corsult plant engineering staff for l LESS DIAN 6.0 % IN DRY AIR additional recovery actions.
QQIQ Step 8.
i Page 3 of 9
JUN 31988 NUMBER TTT12 REV. ISSLTJDATE i
. F R.C.1 RESPONSE TO INADEQUATE CORE COOLING Rev. 2 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINTD i
r 7 CAUDON:
j o MONITOR DWST LEVEL. START MAKEUP TO DWST BEFORE LEVEL DECREASES TO S4,000 GALLONS. '
o A FAULTED OR RUPTURED SG SHOULD NOT BE USED IN SUBSEQUENT STEPS UNLESS NO INTACT SG 15 A VAILABLE.
L J 8 CIIECK INTACT SG LEVELS:
- a. Check wide range levels - a. Increase total AUX feedwater flow GREATER DIAN 63 % to restore wide range level in at least (67 % FOR ADVERSE one SG to greater than 63 %
CONTAINMENT) (67 % for adverse containment).
IE total AUX feedwater flow is less than 320 GPM, IHEN 00IQ Step 16 OBSERVE NOTE PRIOR TO STEP 16.
- b. Control AUX feedwater flow to ,
maintain wide range levels between 63 % and 69 %
(67 % and 69 % for adverse contamment) l!
9 CIIECK RCS VENT AND l DRAIN PAniS CLOSED: l i
i
- a. Check power to PRZR PORY a. Restore power to PRZR PORV block valves - block valves.
AVAIIABIE i i
- b. Check PRZR PORVs CLOSED b. Manually close PRZR PORVs.
l IE any PORV can b'QI be closed, 111EN nunually close its block valve. l
- c. Check other RCS vent paths - c. Manually OR locally close any open I CLOSED RCS vent paths.
- d. Check drain header ISOLATED d. Close all four loop drain header MOVs.
- e. Checkletdown ISOLA 11ID e. Close letdown isolation valve ll>MOV 200 Page 4 of 9
JUN 31988 NUMBER TT!12 REV. ISSUE /DATE FR C.1 RESPONSE TO INADEQUATE CORE COOLING Rev.2 i
S17.P ACT10N/ EXPECTED RESPONSE RESM)NSE NOT OBTAINED ;
NOTE: PARTIAL UNCOVER)NG OF SG TUBES IS ACCEPTABLE IN THE FOLLOWING STEPS.
10 DEPRESSURIZE ALL INTACT SGs AT MAXIMUM RATE: f I
- a. Dump steam to condenser at a. Dump steam at maximum rate I maximum rate using the fo!!owing:
o Atmospheric vent valve. i o Terry Turbine steam supply valves.
- b. Check SG pressures DECREASING b. E b'QI dec:-asing, 111EN QQIQ Step 16 OBSERVE NOTE PRIOR ;
TO STEP 16.
11 CliECK IF RCPs SilOULD BE STOPPED:
- a. Check at least two hot leg a. E RCS hot leg temperatuns temperatuns - decreasing, LESS T11AN 350' F TilEN RETURMIQ Step 8, l
E b'QIdecreasing,
, IliEN GQIQ Step 16.
OBSERVE NOTE PRIOR TO STEP 16. !
- b. Stop all RCPs 12 DEPRESSURIZE ALLINTACT SGs TO 50 PSIO:
- a. Dump steam to condenser at a.Du steam at ma.dm m rate ma.dmum rase usin the following:
o Atmos >heric vent valve.
o Terry Tuttine steam supply valves.
l Page 5 of 9
ww.. o 4J0o NUMBER TTI12 REV. ISSt'E/DA1T.
FR.C.1 RESPONSE TO INADEQUATE CORE COOLIhu Rev.2 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTALNED 13 VERIFY SI FLOW: CONTINUE EFFORTS TO ESTABLISH SI FLOW, o Cherv kWSTlevel DECREASING
'mY TO ESTABLISH ANY OTTIER
% IIIGH PRESSURE INJECTION PAT 1{.
o Check charging line flow IE CORE EXITTIIERMOCOUPLES Indicators INDICATE FLOW LESS TliE 1200* F.
TIIEN RERJRNIQ STEP 12.
lE b'M LESS THAN 1200' F.
o Check HPSI pump AMPS - THEN QQIQ STEP 16, GREATER T11AN 115 AMPS OBSERVE NOTE PRIOR TO ST11P 16.
3 o Check LPSI pump AMPS - -
GREATER 1TIAN 60 AMPS 14 CIIECK CORE COOLING:
- a. Check core exit thermocouples - a. QQIQ Step 16 OBSERVE NOT2 LESS TRAN 1200' F PRIOR TO STEP 16.
- b. Check at least two hot leg b. RETURNIQ Step 12. ,
Lb 350'F
- c. Check RVLIS slenum indication - c. RETURNIQ Step 12.
GREATER H AN 15 % i i
15 QQIQ E 1, LOSS OF REACIOR OR SECONDARY COOLANT, S'17.P 12 l
Page 6 of 9
f JUN 3 588 NUMBER "!TT12 REY. ISSUE /DATE F R.C.1 RESPONSE TO INADEQUATE CORE COOLING Rev.2 t
STEP ACTION / EXPECTED RESPONSE RFSPONSE NOT OBTALNED NOTEt NORMAL CONDITIONS ARE DESIRED BUT NOT REQUIRED FOR STARTING THE RCPs.
16 CHECK CORE EXIT START RCPs AS NECESSARY UNTIL THERMOCOUPLES - CORE EXITTHERMOCOUPLES LESS THAN 1200' F ARE LESS THAN 1200* F.
PERFORM 'n{E FOLLOWING:
- a. Try to start an RCP-
- 1. Place a umper across designated terminaIs on # 2 horizontal terminal botrd in upper RCP breaker cabinet:
RCP Terminal # Wire #
1 8 to 9 Pl71P2 to Pl71P4 2 8 to 9 Pl72P2 to Pl72P4 3 8 to 9 Pl73P2 to Pl73P4 4 8 to 9 P!74P2 to Pl74P4
- 2. Start oillift pump.
- 3. Open CH TV 240, CH TV 241 and CH TV 334.
(scal water return trip valves)
- 4. Open CC TV-1411 (RCP oilcooler CCW rerum trip valve)
- 5. Open seal water rerum MOV.
- 6. Start selected RCP.
E core exit thermocouples are greater than 1200* F M all available RCPs are running, MEN own all PRZR PORVs and block va,ves.
E core exit the mocouples are greater than 12(k. F M all PRZR PORVs and block valves are open, T11EN open all other RCS vent paths to containment.
Page 7 of 9
JUN 3 1988 NmSER m REY. ISSUESATE !
F R.C.1 RESPONSE TO INADEQUATE CORE COOLING Rev.2 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 TRY TO LOCALLY DEPRESSI.10ZE ALL LNTACT SGs TO ATMOSPHERIC PRESSURE:
- a. Use any QR allof the following: 3. Use faulted QR ruptured So, o Atmospheric vent valve o liog Jet steam supply valves ,
o Steam supply valves to the !
auxiliary feedwater pumps o Steam line "pecker head" vent valves 18 CHECK IF RCPs SHOULD BE STOPPED:
- a. Check at least two hot leg a. QQIQ Step 19.
temperatures -
LESS TilAN 350* F
- b. Stop all RCPs
- 1. Close all four seal water i retum MOVs l
- 2. IE containment pressure is greater than 5 PSIG, 111EN perform the follutig:
- a. Close CH W 240, CH TV 241 (Seal water retum trip valves),
- b. Close CC-W 1411 (CCW retum frnm RCP oil coolers) e Page 8 of 9
JUN 3 1988 NUMBER TTTLE REV. ISSULDATE F R.C.1 RESPONSE TO INADEQUATE CORE COOLING Rev.2 i
STEPf ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i
19 VERIFY SI FLOW: CONTINUE EFFORTS TO ESTABLISH SI FLOW.
o Check RWSTlevel DECREASING BtY TO ESTABLISH ANY ODIER OR HIGH PRESSURE INJECTION PADi. ;
o Check charging line flow indicators - RETURNIQ STEP 16. I INDICARI FLOW l ,
DE o Check HPSI pump AMPS -
GREATER THAN 115 AMPS o Check LPSI pump AMPS -
GREATER DIAN 60 AMPS i ,
20 CHECK CORE COOLING: RETURNIQ STEP 16.
o Check RVLIS plenum indication -
GREATER THAN 15 %
l o Check at least two RCS hotleg temperatues - I LESS THAN 350' F l
21 GQIQ E 1, LOSS OF REACTOR OR SECObtARY COOLAST. STEP 12. 1 Eht l
l l
Page 9 of 9