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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 ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 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 ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL 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 ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls 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 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 ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements 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 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 ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys 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 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 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 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 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 ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls 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 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 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 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 B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan 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 ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program ML20154G5311998-10-0707 October 1998 Rev 4 to Project Procedure PP-02, Accident Mitigation Sys Review 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 ML20154G5351998-10-0606 October 1998 Rev 3 to Project Procedure PP-04, Regulatory Review Procedure 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 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 ML20247Q6671998-05-20020 May 1998 Rev 1 to Epop 4422A, Thermal Hydraulic Evaluation Methods ML20247R8081998-05-20020 May 1998 Rev 1 to Epop 4455F, Rumor & Inquiry Control ML20247R7921998-05-20020 May 1998 Rev 1 to Epop 4455D, News Releases ML20247Q7011998-05-20020 May 1998 Rev 1 to Epop 4490, Implementation of Recovery Operations ML20247R7491998-05-20020 May 1998 Rev 1 to Epop 4455, Manager of Public Info 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 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
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STAT!6N PROCEDURE COVER SHF' g A. IDENTIFICATION Number; E0P 35 FR-C.1 Rev. 2,
Title:
RESPONSE TO INADEQUATE CORE COOLING 1
Prepared By: J. BUCKINGHAM/H. K. COVIN B. REVIEW I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATURE DATE DEPARTMENT HEAD No (,, fl J- \
C. SPECIFIC UNREVIEWE0 SAFETY QUESTION EVALUATION REQUIRED:
Modifies intent of procedure and changes operation of systems as described in design documents. YES [ ] NO [4 (If yes, perform written USQ determination and Safety ,
Evaluation, and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)
ENVIRONMENTAL REVIEW REQUIRED (Adverse environmental impact) YES [ ] NO C -7
- 0. SPECIFIC SAFETY FVALUATION REQUIRED Affects response of safety systems, performance of systems which may have been credited in the safety analysis or non-credited systems which may indirectly affect safety system response. YES [ ] NO [-7 (If yes, perform written Safety Evaluation and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)
E. INTEGRATED SAFETY EVALUATION REQUIRED YES [ ] NO [ T F. PROCEDURE REQUIRE b /SORC REVIEW (In addition to rebiew, item with a YES response must be documented in the 50RC meeting minutes.) YES [ g NO [ ]
- G. 50RC APPROVAL /$0RC Meeting Number 3 -8 7-/hf H. APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the date below:
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$~/S~~ Yb Station / Service / Unit Superintendent Effective Date SF301/9/s/SES/87-12/lofi 8910260497 001007 PDR ADOCK 05000213 P PDR
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E0P 35 FR-C.1 Page 1
. Rev. 2
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0 RESPONSE TO INADEQUATE C,')RE COOLING Paae No. Eff Jej.,
1-9 2 4
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RESPONSE TO INADEQUATE CORE COOLING E0P 35 FR-C.1 Page 2 L Rev. 2 V
A. PURPOSE This procedure provides actions to restore core cooling.
d B. ENTRY CONDITIONS This procedure was written for Modts 1, 2, and 3. Using this procedure when not in these modes requires a step by step evaluation to determine if the required action is s'ill applicable to current plant conditions.
This procedure is entered from EOP 35 F-0.2, CORE COOLING Critical Safety Function Status Tree, on the RED condition.
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r RESPONSE TO INADEQUATE CORE COOLING E0P 35 FR-C.1 Page 3 Rev. 2
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STEP ACTION /EXPECTF0 RESPONSE HESPONSE NOT OSTAINED l CAUTION
- 1. If RWST level decreases to < 520,000 gal, the ECCS systems should be aligned for cold leg recirculation using E0P 35 ES-1.3, TRANSFER TO COLD LEG RECIRCULATION.
- 2. RHR pumps should not be run with RHR Hx inlet temperatures > 195*F without RPCCW to the RHR Hxs. g 1 Verify ECCS Valve Alignment - Manually align valves-PROPER EMERGENCY ALIGNMENT as necessary 2 Verify ECCS Flow In All e Trains
- a. Charging pumps SI a. START pumps and align flow indicator - valves as necessary CHECK FOR FLOW
's b. SI pump flow b. START pumps and align indicators - CEECK valves as necessary FOR FLOW
- c. RER pump flow c. START pumps and align indicators - CHECK valves as necessary FOR FLOW 3 Check RCP Support Conditions
- a. Any 6.9 KV bus - a. Restore power to buses.
ENERGIZED
- b. RPCCW to RCPs - b. Establish RPCCW to RCPs.
AVAILABLE
- c. Seal injection to RCPs - c. Establish seal injection.
CHECK FOR FLOW
- d. Seal water return d. Establish seal water from RCPs - CHECK leakoff.
FOR FLOW oPSO441 3-44 l
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RESPONSE TO INADEQUATE CORE COOLING EOP 35 FR-C.1 Peg 2 4 Rev. 2 STEP ACTION / EXPECTED RESPONSg RESPONSg NOT 08TAINED 4 Check SI Accumulator Isolation Valve Status
- a. Isolation valves - OPEN a. Open isolation valves as follows
- 1) Restore power to isolation valves (32-2R-R5F, 32-2W-R3J, 32-2R-F4M, 32-2W-F4M)
- 2) OPEN isolation valves UNLESS closed after e accumulator discharge
- 3) Remove power from isolation valves.
5 Check Core Exit TCs < 1200*F Go to Step 7.
6 Check Core Exit TCs .
- a. Temperature < 720'F a. IF decreasing THEN return to Step 1. IF NOT, THEN go to Step 7'.
- b. Return to procedure f- g and step in effect '
7 Check Containment Hydrogen Concentration
- a. Determine containment a. Have Chemistry obtain a hyrogen per OP 3313A, hydrogen sample per the NYDROGEN RECOMBINERS, POST ACCIDENT LIQUID HYDROGEN MONITORS AND SAMPLING SYSTEM RECOMBINER BLDO VENTILATION
- b. Hydrogen concentration b. Consult Director of
- < 5.0% Station Emergency l Organization (DSEO) for l tiditional recovery actions. Go to Step 8
- c. Hydrogen concentration c. Turn on hydrogen
< 0.5% recombiner system per OP 3313A, NYDROGEN RECOMBINERS AND RECOMBINER BUILDING VENTILATION O
OPKel t 3 44 l
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RESPONSE TO INADEQUATE CORE C004}NG EOP 35 FR-C.1 Page 5 Rev. 2-(-
d STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED CAUTION
- 1. CST water source for AFW pumps will be necessary IF,DWST level decreases to < 80,000 gal.
- 2. A faulted or ruptured SG should NOT be used in subsequent steps UNLESS no intset SG is available.
8 Check Intact SG Levels
- a. Narrow range level a. Raise total feed flow
> 4% (34% FOR ADVERSE to restore narrow range CONTAINMENT) level > 4% (34% FOR
' ADVERSE CONTAINMENT).
IF total feed flow
< 525 gps, TNEN go to Step 17. OBSERVE NOTE l PRIOR TO STEP 17.
- b. Control feed flow to maintsin narrow range level between 4%
(34% FOR ADVERSE CONTAINMENT) and 50%
9 Check RCS Vent Paths
- a. PZR PORVs - CLOSED a. Manually close PZR PORVs.
IF any valve can NE be closed, THEN manually close its block valve.
! b. Block valves - AT b. Open block valve UNLESS LEAST ONE OPEN it was closed to isolate
- an open PZR PORV.
- c. Reactor vessel head vent c. Manually close reactor isolation valves - vessel head vent CLOSED isolation valves.
- d. PZR vapor space d. Manually close PZR vapor sample isolation space sample isolation valves - CLOSED valves.
O CP50ss 1 3-s4
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, RESPONSE TO INADEQUATE CORE COOLING EOP 35 FR-C.1 Page 6 Rev. 2 0 -
eTEP ACTION / EXPECTED RESPONSE RESPONSE NOT OETAINEO NOTE
- 1. Partial uncovery of SG tubes is acceptable in the following steps.
- 1. Bypass Low Low Tavg interlock at 553*F to maintain steam dump operation.
- 3. Block steamline isolation when P-11 light lit.
10 Depressurize All Intact SGs To 134 psig
- a. Dump steam to the a. Dump steam at maximma condenser at maximum rate to atmosphere rate
- b. Check SG pressures b. IF SG pressure
< 231 psig decreasing, THEN return to Step 8. IF NOT, THEN go to Step 17. OBSERVE NOTE PRIOR TO STEP 17..
- c. Check RCS hot leg c. IF RCS hot leg temperatures - AT temperatures decreasing, ps LEAST TWO < 375*F THEN return to Step 8.
\ ,) IF NOT, THEN go to Step
- 17. OBSERVE NOTE PRIOR TO STEP 17.
- d. Stop SG depressurization 11 Check If SI Accumulators Should Be Isolated
- a. At least two RCS a. Go to Step 17. OBSERVE hot leg temperatures NOTE PRIOR TO STEP 17.
< 375'F
- b. Restore power to isolation valves (32-2R-R5F, 32-2W-R3J, 3?-2R-F4M, 32-2W-F4M)
- c. CLOSE isolation valves c. Vent any unisolated accumulator
- d. Remove power from isolation valves.
12 STOP All RCPs O
OPS 0641 3-44
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e e e RESPONSE TO INADEQUATE CORE COOLING E0P 35 FR-C.1 Pagn 7 Rev. 2 (m
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED 13 Depressurize All Intact SGs To Atmospheric Pressure
- a. Dump steam to condenser a. Dump steam at maximum at maximum rate rate to atmosphere 14 Verify ECCS Flow
- a. Charging pump SI flow a. Continue efforts to indicator - CHECK establish ECCS flow.
FOR FLOW IF core exit TCs
< 1200*F, THEN OR return to Step 13. IF NOT, THEN go to Step 17.
SI pump flow OBSERVE NOTE PRIOR TO indicators - CHECK STEP 17.
FOR FLOW OR .
RHR pump flow indicators - CHECK FOR FLOW 15 Check Core Cooling
- a. Core exit TCs < 1200*F a. Go to Step 17. OBSERVE NOTE PRIOR TO STEP 17.
- b. At least two RCS hot b. Return to Step 13.
leg temperatures < 350'F
- c. RVLMS plenum level > 19% c. Return to Step 13.
16 Go To EOP 35 E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 12 O
CP50641 3-44
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RESPONSE TO INADEQUAIE CORE COOLING E0P 35 FR-C.1 Pega 8 Rev. 2
! )
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Normal conditions are desired but not required for starting the RCPs.
17 Check Core Exit TCs < 1200*F Start RCPs as necessary until core exit TCs < 1200*F IF core exit TCs > 1200*F and all available RCPs running, THEN open all PZR PORVs and block valves. IF-core exit TCs > 1200*F and all PZR PORVs and block valves are open, THEN open all other RCS vent paths to containment.
18 Try To Locally Depressurize ,
All Intact SGs to Atmospheric Pressure
- a. Locally open steam a. Use faulted OR ruptured dump valves OR SG.
Atmospheric Dumps OR
~ ~ , Atmospheric Dump
( ') bypass valves.
U 19 Check If SI Accumulators Should Be Isolated
- a. RHR pump flow a. Return to Step 17.
indicators - AT LEAST INTERMITTENT FLOW
- b. Restore power to isolation valves (32-2R-RSF, 22-2W-R3J, 32-2R-F4M, 32-2W-F4M)
- c. CLOSE isolation valves c. Vent any unisolated accumulator
- d. Remove power from isolation valves.
C'T L- J OPN681 3-44 o,
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RESPONSE TO INADEQUATE CORE COOLING E0P 35 FR-C.1 Pags 9 Rev. 2 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED 20 Check If RCPs Should Be Stopped .
- a. At least two RCS hot a. Go to Ste; 21.
temperatures < 350*F
- b. STOP all RCPs 21 Verify ECCS Flow
- a. Charging pump SI a. Continue efforts to flow indicator - establish ECCS flow.
CHECK FOR FLOW Return to Step 17.
EE SI pump flow indicators - CHECK ,
FOR FLOW .
9E RKR pump flow indicators - CHECK FOR FLOW 22 Check Core Cooling
- a. RVLMS plenum level a. Return to Step 17.
> 19% AND at least two RCS hot leg temperatures
< 350'F 23 Go to E0P 35 E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 12
-FINAL-O OPS 0041 3 44