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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
[Table view] |
Text
4 JUN 0 31988
. NUMBER TTI1E REY. ISSLT./DATE :
E S . I .1 SI TERMINATION Rev. 3 l
(
A. PURPOSE f This procedure provides the necessary instructions to terminate safety injection and stabilize plant conditens.
B. SYMPTOMS OR ENTRY CONDITIONS i
This procedure is entered from: ;
- 1. E 0, REACTOR TRIP OR S AFETY INJECTION, Step 25, f E 1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 7 when specified termination criteria are satisfied.
- 2. FR H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 26 after secondary heat sink has been reestablished and SI is terminated.
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001025o205 001007 Page 1 of 12 PDR ADOCK 05000213 P PDR
JUN O 31989
. NLStBER Tm.E REV. ISSUE /DATE j ES 1.1 SI TER511 NATION Rev. 3 i STEP ACTION / EXPECTED RESPONSE RESTONSE NOT OBTAINED
=
r 7 CAUTION: o IF OFF SITE POWER IS LOST AFTER RESETTING SI, ofANUAL ACTION AfAY BE REQUIRED TO RESTART '
SAFEGUARDS EQUIPESfENT.
o IF CONTROL SWITCH FOR ANY SHUTDOWN CHARGING PUhfP WAS TAKEN TO THE TRIP POSITION, THE PUhfP(S) i AfAY AUTO START WHEN BOTH SI WL RELAYS ARE RESET. I L J l l
NOTE: FOIDOUT PAGE SHOULD BE OPEN 1 RESET St Aht CONTAINhiEhT ISOLAT10N:
- a. Check containment pressure - a. Perform the folicwing:
LESS THAN 5 PSIG
- 1. Open CKTs A13 and B13 in DC panels A and B.
- 2. Reset SI WL Relays. ,
- 3. IE charging pump control !
switch (es) are NQIin TPO, '
TIIEN restore low discharge !
pressure auto start for shutdown charging pump (s) by taking pump control switch (es) to the "Trip" position then releasing switch (es) to i the "Auto" position. I
- 4. G.Q IQ Step 2. !
- b. Reset Si and containment isolation (SEE OPPOSITE PAGE) l 2 CilECK CONTAINMENT START ONECONTAINMENT r INSTRUMENT AIR PRESSURE INTRUMENT AIR COMPRESSOR .
GREATER THAN 118 PSIG TO ESTABLISH INSTRUMENT AIR ;
PRESSURE. !
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Page 2 of 12
JUN 0 31988 NUMBER TIT 1.E REV.15 SUE /DATE !
SI TERMINATION I ES 1.1 Rev.3 i
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 VERIFY ONE CHARGING P'JMP E RCP LOWER BEARING RUNNING AND PLACETHE TEMPERATURES ARE LESS WAN OmER PUMP IN STANDBY 170' F, WEN PERFORM THE FOLLOWING:
- a. Check closed CH MOV 257.
E NQIclosed, !
WEN manually QR locally l close CH MOV 257. '
i
- b. Check open BA MOV 373.
E EQI open, I WEN manually open BA MOV-373 QR BA MOV-32.
- c. Take charging pump control switch !
to the "Trip" then to the "Start" position.
E RCP LOWER BEARING TEMPERATURES ARE GREAHR THAN 170* F.
THEN PERFORM THE FOLLOWING:
- a. Isolate sealinjection !
- b. Check closed CH MOV 257. i E NQIclosed, j WEN manually QR locally close l CH MOV 257. i
- c. Check open BA MOV 373.
E HQI open, WEN manually open BA MOV 373 QR BA MOV 32. ;
- d. Take charging pump control switch to the "Trip" then 'o the "Start" position.
4 CllECK RCS PRESSURE STABLE DO NOT STOP St PUMPS.
OR INCREASING GQIQ E 1, l.OSS OF REACTOR OR SECONDARY COOLANT, STEP 1.
5 CONTROL CHARGING FLOW TO E PRZR LEVEL CONTINUES TO f MAINTAIN PRZR LEVEL DECREASE, THEN QQIQ ES 1,2, POST LOCA COOLDOWN AhD DEPRESSURIZATION, SEP 1.
P I
l Page 3 of 12
JUN 0 31988 I
, NUMBER TTR.E REV. ISSUE /DATE ;
ES 1.1 SI TERMINATION Rev.3 i i
(
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 CHECK IF HPSI PUMPS SHOULD l BE STOPPED:
- a. Check RCS pressure - a. E any SG is faulted. !
THEN DO EQIproceed until faulted o STABLE DE INCRFASING SG depressurization stops.
o GREATER THAN 1.75 PSIG E no SG is faulted (1700 PSIG FOR ADN ERSE THEN QQIQ ES 1.2 CONTAINMENIi POST LOCA COOLDOWN AND DEPRESSURIZATION, Step 1.
E criteria for stopping HPSI pumps can EQIbe satisfied after faulted SG depressurization stops, THEN QQIQ ES 1.2.
POST LOCA COOLDOWN AND DEPRESSURIZATION, Step 1.
- b. Stop HP6; pu ng.s and p: ce in standby I
- c. Close all four loop S.t MOW ;
7 STOP LPSI PUMPS AND Pi ACE IN STANDBY:
- a. Close both core dJuge MOVs 8 VERIFY SI FLOW NGY REQUIRED: l
- a. Check RCS sabcooling based on a. Manually operate SI pumps as l core exit thermocriupies - necessary, GREATER THAN 32' F GQIQE1, (SEE OPPOSiTc PAGE LOSS OF REACTOR OR FOR ADVERSE CONTAINMENI) SECONDARY COOLAST, Step 1.
- b. Check PRZR Icw :- b. Control charging flow to maintain GREATER THAN l' 1 PRZR level (24 % FOR ADVE"dd E PRZR level can EE be mainte.ined.
CONTAINMEhT) manually operate Si pumps as necessary.
THEN 00IQ E 1.
LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
Page 4 of 12
JUN O 31988 NUMBER TTIU REY. ISSUE /DATE :
ES 1.1 SI TERMINATION Rev.3 l l
l STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAI ED 9 INCREASE PRZR LEVEL TO CONTROLCHARGING AS !
GREATER TRAN 15 % NECESSARY l (35 % FOR ADVERSE l CONTAINMENT) I I
10 ESTABLISH LETDOWN IE CONTAINMENT PRESSURE IS (SEE OPPOSITE PAGE) LESS THAN 5 PSIG, I
THEN ESTABLISH ALTERNATE LETDOWN BY PERFORMING THE '
I FOLLOWING:
l i 1. Reset Containment HCP WL Relays.
- 2. Open DH TV 1841, drain header trip valve.
- 3. Reset solenoid in blowdown room for drain header trip valve, DH TV 1847.
- 4. Line up drain header to VCT:
- a. Close DH V 408, drain header to PDT.
- b. Open CH V 383, drain header to VCT.
- 5. Close breaker for DH MOV 310. '
- 6. Open one loop drain MOV.
- 7. Throttle DH MOV 310 to maintain !
PR2R level.
- 8. Close CH MOV-292B and CH.MOV 292C.
I i1 CHECK VCT MAKEUP CONTROL .'
SYSTDt:
- a. Check VCT makeup blender ratio - a. Adjust makeup blender ratio to greater SET FOR GREATER THAN RCS than RCS boron concentration. l BORON CONCENTRATION i i
- b. Check VCT makeup controls - b. Place makeup controls in automatic.
IN AUTOMATIC l
I Page 5 of 12
JUN 0 31985 NUMBER TTG REV. ISSUE /DATE >
ES 1.1 SI TERMINATION Rev.3 '
i STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i
i i
12 ALIGN CHARGING PUMP SUCTION TO VCT:
- a. Open CH MOV-257 ,
f
- b. Close BA MOV-373 i
- c. Check BA MOV 32-CLOSED c. Close BA MOV 32 13 CHECK IF RCP SEAL WATER STOP AFFECTED RCP(s).
RETURN FLOW (s)IS GREATER THAN 0.2 GPM 14 INSURE HIGH PRESSURE STEAM IE CONDENSER b'QI AVAILABLE, DUMP OPERA ~ES TO MAINTAIN IHEE DUMP STEAM USING ONE TAVG QR MORE OF'IEE FOLLOWING: ,
- s. Atmes sheric vent valve.
- b. Terry 7urbine steam sup )ly valves. l
- c. Hog Jet steam supply va..ves. j i ,
15 CHECK RCS COLD LEG CONTROL STEAM DUMP ASD TOTAL l l TEMPERATURES STABIE AUX FEEDWA'ER FLOW AS NECESSARY TO STABILIZE RCS TEMPERATURES.
16 CONTROL PRZR PRESSURE:
- a. Turn on PRZR heaters a. IE normal spray EQIavailable AND operate normal spray as AEQ letdown is in service necessary to maintain PRZR THEN use auxiliary spray, pressure stable f IE auxiliary spray b'QIavallable. l IljEE use one PRZR PORV.
I i
I Page 6 of 12 m
tJN 0 31W8 NUMBER TTIM REV. SSUE/DATE l E S . I .1 SI TERhi! NATION Rev.3 j l
STEP ACTION / EXPECTED RESPONSE RESPONSE SOT OBTAINED i
r ,
l CAUTlONt of0NITOR DWST LEVEL. START ofAKEUP TO DWST BEFORE LEVEL DECREASES TO $4,000 GALLONS. l L J l l
l 17 CHECK INTACT SG LEVELS:
f I
- a. Check wide range levels - a. hiaintain total AUX feedwater flow greater than 320 GPhi until wide !
GREATER THAN 63 %
(67 % FOR ADVERSE range levelin at least one SG is l CONTAINhtENT) greater than 63 f l' (67 % for adverse. sontainment).
- b. Control AUX feedwater flow to b. IE any So wide range level continues maintain wide ran ge levels to increase, l between 63 % anc. 69 % THEN stop AUX feedwater flow (67 % and 69 % for adverse to that SG.
containment) 18 CHECK RCP COOLING SYSTEhtS: ESTABLISH NORhtAL COOLING ,
FLOW TO RCPs, !
o RCP CCN System flow - NORhiAL IN ACCORDANCE WIT 11, I o RCP sealinjection flow NORhiAL l NOP 2.81, 1 OPERATION OF COhiPONEhT l COOLING SYSTEht, [
ASR t NOP 2.61, SEAL WATER STARTUP NOR\tAL OPERATION. i
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Page 7 of 12
JUN 0 31986 NUMBER TTTLE '
REY. ISSUE /DATE ES I.1 SI TERMINATION Rev.3
(
STEP ACTION /EXPECIED RESPONSE RESPONSE NOT OBTAINED 19 VERIFY ALL AC BUSES ENERGIZED VERIFY EMERGENCY BUSES BY OFFSITE POWER ENERGlZED BY DIESEL GENERATORS THEN PERFORM THE FOLLOWTNG: I o Verify MCC 5 energized.
E NQIenergized.
THEN energize MCC 5 E MCC 5 can NOIbe energized, l THEN QQIQ EOP 3.1-50 f LOSS OF MCC 5, Step 1.
o Start CARFANS as equired.
o Stop allruuologicalt ' chemical releases, o isolate steam to the Air Ejectors.
o Check RCP cooling status:
- 1. Elower bearing temperature is less than 170 F. .
THEN perfo.m the following:
l
- a. Start one CCW pump,
- b. Start one charging pump,
- c. Initiate RCP seal water flow.
- 2. Elower bearing temyerature is greater than 170' F.
TriEN perform the following:
- a. Close RC? thermal barrier manual retum isolation valve (CC V 841),
- b. Close RCP seal supply valves (CH V-b5A through D).
- c. Start one CCW pump.
- d. Start one charging pump.
- c. Slowly open RCP thermal barrier manual return valve,
- f. WHEN lower bearing temperature is le .s than 170' F.
THEN slowly initiate RCP seal water flow.
o Try to restore offsite power (SEE OPPOSITE PAGE).
L Page 8 of 12
JUN 0 31988 NUMBER TTTIE REY. ISStEDATE '
E S . I .1 SI TERMINATION Rev. 3 i STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED r 7 j CAUTIONt IF RCP SEAL COOUNG FLOW HAD PREYlOUSLY BEEN LOST, THE '
AFFECTED RCP(s) SHOULD NOT BE STARTED PRIOR TO AN !
ENGINEERING STATUS EVALUATION. ;
k J J
NOTEt RCPs SHOULD BE RUN IN ORDER OF PRIORilY TO PROVIDE l NORbfAL PRZR SPRAY.
20 CHECK RCP STATUS:
- a. Check RCPs - a. Tr> to start one RCP: l AT LEAST ONE RUNNING
- 1. Establish conditions for starting an RC
- a. Close loop Tc isolation valve.
- b. Open loop bypass valve, i
- c. Start oil hft pump.
- d. Insure seal water and component cooling water supplied to RCP.
- e. Insure lower bearing temperature i is less than 170' F.
- f. Check RCS pressure l' g eater than 300 PSIG.
- g. Open CH TV 240, CH TV 241 and CH TV-334 t (seal water return trip valves) j
- h. Open CC TV 1411 (otl cooler CCW return trip valve) !
- i. Open seal water return MOV.
- 2. Start selected RCP, ;
THEN perform the following: i
- a. Oyn loop Te isolation valve.
- b. C..ose loop bypass valve.
l IE RCP can b'QI be started, THEN perform the following: i I
- a. Open loop Tc isolation valve.
- b. Close loop bypass valve,
- c. Verify natumi circulation '
(SEE ATTACHMENT A).
IE natural circulation b'QI verified, THEN increase dumping steam ;
from intact SG(s). ,
l d. Attempt to start another RCP. ;
Page 9 of 12 !
l
JUN 0 31988
. NUMBER EU REV. ISSUE /DATE !
E S. I.1 SI TERMINATION Rev.3 i i
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTANED 21 CHECK SOURCE RANGE DETECTORS ENERGIZED: ,
- a. Check intermediate range flux - a. Continue with step 22, i LESS THAN 5 x 1010 AMPS WHEN less than 5 x 1010 AMPS, IliEN do steps 21 b, c and d.
- b. Verify source range detectors - b. Manually energize source range !
ENERGlZED detectors.
- c. Transfer nuclear flux recorders .
to source range scale
- d. Transfer SUR meters to source range 22 CHECK IF DIESEL GENERATORS !
SHOULD BE STOPPED-
- a. Verify ac emergency buses energized - a. Try to restore off site power to l BOTH TRAINS BY OFF StrE both trains.
I POWER (SEE OPPOSITE PAGE) i i
BUSES 8,4 and 5 E b'QI restored, WEN check the following equipement l ASI2 BUSES 9,6 and 7 loaded on ce ac emergency buses:
- 1. MCC - 5. i
- 2. Control air compressors.
- 3. Semi vital 120 V buses.
l 4. Closed cooling system pumps.
- 5. Battery charger I A. i l 6. One component cooling water i pump.
I 7. One service water pump for each l diesel generator.
l 8. E service water is supplied to l RHR heat exchangers, THEN use at least two service water pumps.
- 9. Start CARFANS as required to 1 limit containment pressure and l temperature.
- b. Stop any unloaded diesel generator and place it in standby i
(SEE OPPOSITE PAGE) l Page 10 of 12 i -
JUN 0 3198e NUMBER TTI1E REV. ISSUE /DATE ES 1,1 SI TERMINATION Rev.3 1
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTMNED 23 SHUT DOWN UNNECESSARY PLAST EQUIPMENT l
- a. Stop one main feedwater pump 1
- b. Stop one condensate pump
- c. Place standby heater drain pump .
In TPO ,
- d. Place running heater drain pump a TeO 24 MAINTAIN STABLE PLANT CONDITIONS:
o PRZR pressure o PRZRlevel o SG wide range levels o RCS average temperature l
25 VERIFY St FLOW NOT REQUIRED:
- a. Check RCS subcooling based on a. Manually operate SI pumps as l core exit thermocouples - necessary, GREATER ' IRAN 32' F Q.Q IQ E 1, '
(SEE OPPOSlu PAGE LOSS OF REACTOR OR FOR ADVERSE CONTAINMEN'O SECONDARY COOLANT, Step 1. l 1
- b. Check PRZR level- b. Control charging flow to maintain GREATER ' IRAN 10 % PRZR level.
(24 % FOR ADVERSE IE PRZR level can SQIbe maintained, CONTAINMENT) manually operate Si pumps as necessary, TliEN GQIQ E 1, LOSS OF REACTOR OR SECONDARY COOLAST, Step 1.
26 GQIQ APPROPRIAE PLANT PROCEDURE EhD ;
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JUN 0 31986 i TTT12 '
NUMBER REY. ISSU1RDA'!1! 1 E S. I .1 SI TERMINATION Rev.3 i !
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ATTACHME?G A l The following conditions suppon or indicate natural circulation flow:
o RCS subcooling based on core exit thermocouples is greater than 32' F.
l o SO possures are stable or decreasing.
o RCS temperature based on core exit thennocouples and average temperature indications is stable or decreasing.
l o RCS cold leg temperatures are at saturation temperature for SG pressures.
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