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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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Text
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JUN 3 1988 UTH NUMBER REV. ISSUE, TATE
. ES 3.2 POST.SGTR COOLDOWN USING BLOWDOWN Rev. 3
(
A. PURPOSE I l
This procedure provides actions to cooldown and depressurize the plant to cold shutdown conditions following a steam generator tube rupture. This recovery method depressurires the ruptured SG(s) by c raining it using SO blowdown.
B. SYMPTOMS OR ENTRY CONDITIONS '
, This procedure is entered from E 3, STEAM GENERATOR RJBE RUPTURE, Step 36, $
if plant staff selects the blowdown method. j l t
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8010250241 DR 001007 ADOCK 05000213
, PDR i
Page 1 of 12 l
JUN 3 1988
. NtmBER TT12E REY. ISSUE /DATE ES 3.2 POST.SGTR COOLDOWN USING BLOWDOWN Rev.3 1
STEP /.CTION/EXPECIED RESPONSE RESPONSE NOT OBTAINED l NOY8: o FOIDOUTPAGE SHOULD BE OPEN.
l o IF THE LOOP WITH THE RUPTURED SG(s) WAS IS0 LATED BY CLOSING THE LOOP IS0lATION VALVES. THE LOOP SHOULD BE COOLED DOWN IN ACCORDANCE WITH ATTACHMENT A. ;
1 TURN ON PR7.R }{ EATERS AS NECESSARY TO SATURATE PRZR
' WATER AT RUI'IURED SG(s)
PRESSURE.
2 BORATETilE RCS FOR COOLDOWN IN ACCORDANCE WITH !
SUR 5.3-19,
- BORATION REQUIREMENTS FOR REACTOR SIRTIDOWN !
- a. Check MCC 8 ENERGlZED a. Energize MCC . 8.
3 VERIFY ADEQUATE SHUIDOWN
, MARGIN: '
- a. Sample ruptured SG(s) (
- b. Sample RCS ,
i
- c. Check shutdown margin ADEQUATE c. Borate Rs'S as necessary. j I
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JUN 3 R8B
, NUMBER TTn.E REY. ISSUE /DATE l ES 3.2 POST SGTR COOLDOWN USING BLOWDOWN Rev.3 l l
t
~
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l
r 7 l
CAUTIONt MONITOR DWST LEVEL. START MAKEUP TO DW.VT BEFORE l LEVEL DECREASES TO $4,000 Gall.ONS.
L J 4 CliECK INTACT SG LEVELS: l
- a. Check wide range levels - a. Maintain total AUX feedwater How GREAlliR TilAN 63 % greater than 320 GPM until wide (67 % FOR ADVERSE range levelin at least one SG is CONTAINMENT) greater than 63 %
(67 % for adverse containtnent),
- b. Control AUX feedwater now to b. lE any So wide range level continues maintain wide range levels between to increase in an uncontrolled manner, 63 % and 69 % TliEN QQIQ E 3, (67 % and 69 % for adverse STEAM GENERATOR TUBE containment) RUl*TURE, Step 1.
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JUN 3 WBB
, NUMBER TTIM REV. ISSUE /DAR ,
ES 3.2 POST-SGTR COOLDOWN USING BLOWDOWN Rev.3
( '
STEP ACI10N/ EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: SINCE RUPTURED SG(s) hfAY CONTINU2 TO DEPRESSURIZE TO LESS THAN THE hilNihtubi RCS PRESSURE NECFSSARY FOR CONTINUED RCP OPERATION, COOLDOWN TO COLD SHUTDOWN SHOULD BE COSfPLETED AS QUICKLY AS POSSIBLE, NOT TO EXCEED 100*F / HR.
L i 5 INITIATE RCS COOLDOWN TO 300* F (277' F FOR ADVERSE CONTAINMENT)
- a. Mair.tain cooldown rate in RCS l ,.
cold legs - !
LESS THAN 100* F/ HR ;
- b. Dump steam to the condenser b. Manually OR locally dump steam from intact SG(s) fmm intact SG(s): ,
o Uv atmospheric vent valve. ,
IE ns intact SG available, THEN perform one of the following: l l
o Use faulted SG I QR o GQIQ ECA 3.1, SGTR WITH LOSS OF REACTOR COOLAST-1 SUBCOOLED RECOVERY I
DESIRED, Step 1.
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JUN 3 1988
, NUMBER EU REV. ISSUruDATE ES.3.2 POST.SGTR COOLDOWN USING BLOWDOWN Rev.3 l
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STEP ACTION / EXPECTED RESPONSE RESTONSE NOT OBTAINED r 7 CAUTION: RCS AND RUPTURED SG(s) PRESSURES MUST BE MAINTAINED LESS THAN THE RUPTURED SG(s) SAFETY VALVE SETPOINT.
& J 6 CONTROL RCS PRESSURE AND htAKEUP FLOW TO hilNIbilZE f RCS TO SECONDARY LEAKAGE:
- a. Perform appropriate action (s) from table below:
PRZR LEVEL RUPTURED SG(s) LEVEL INCREASING DECREASING OFFSCALE HIGH LESS THAN 15 % o Increase RCS Increase RCS o increase RCS
( 35 % FOR makeup now makeup now makeup now ADVERSE CONTAINhiEST ) o Depressurize RCS o hiaintain RCS and using Step 6 b ruptured SG(s) pressures equal l
l BEnVEEN 15 % Depressurize RCS Turn on PRZR Maintain RCS j AND 50 % using Step 6 b heaters and ruptured ,
( 35 % AND 50 % SG(s) pressures !
FOR ADVERSE equal CONTAINhiEST )
BE'nVEEN 50 % o Depressurize RCS Turn on PRZR Maintain RCS AND 76 % using Step J b heaters and ruptured .
( 50 % AND 69 % SG(s) pressures FOR ADVERSE o Decrease RCS equal CONTAINMENT) makeup now GREATER THAN Decrease RCS Tum on PRZR Maintain RCS
'M % makeup now heaters and ruptured iFOR SG(s) pressures i ASE equal I Co.fAINMEhT )
i
- b. Use normal PRZR spray to b. IE letdown is in service, i accomplish action specified in THEN use auxiliary spray.
IE letdown NQIin service, T11EN use one PRZR PORV. ,
Page 5 of 12 I
JUN 319gg
, NtStBER TTlu REY. ISSUE /DAE ES-3.2 {
POST SGTR COOLDOWN USING BLOWDOWN Rev.3 i
(
STEP ACT10N/ EXPECTED RESPONSE RESPONSE NOT OBTALNED l
1 7 CHECK IF SOLID PLANT CONDITIONS SHOlfLD BE ESTABLISHED:
- a. Check PRZR steam phase temperature - a. Continue RCS cooldown and LESS THAN 450' F depressurization, WHEN PRZR temperature is less than 450' F.
THEN do step 7 b.
- b. Increase PRZR level to 100 % i l
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i JUN 3 1988
, NUMBER TTH.E REV. ISSUE /DATE i ES 3.2 POST SGTR COOLDOWN USING BLOWDOWN Rev.3 l
, i STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINTD 1
NOTE: o THE SI SYSTEbf AfUST BE DISABLED BEFORE RCS l TEbfPERATURE IS REDUCED BELOW 315
o IF RUPTURED SG(s) PRESSURE IS GREATER THAN 325 PSIG, ESTABilSH BLOWDOWN FROh! STEAbi GENERATOR TO l, REDUCE STEAbf GENERATOR AND RCS PRESSUE.
l 1
8 PERFORM COLD SHUTDOWN ALIGh3 TEST:
- a. Check core exit thermocouples - a. Continue RCS cooldown.
LESS THAN 350' F WHEN core exit thermocouples are less than 350' F.,
- b. Align core cooling equipment IN ACCORDANCE WITH NOP 2.3 4, 2 HOT STANDBY StODE 3 TO COLD SliUIDOWN htODE 5 Ah12 i NOP 2.121, '
CORE COOLINO SYSTEht LINEUP FOR SHUTDOWN AND AT POWER OPERATION
- c. Check iflow temperature over c. WHEN all conditions are satisfied, a pressure protection relief valves THEN do step 8 d.
4 should be placed in service:
- 1. Check PRZRlevel SOLID i 2. Check RCS temperature -
j !.ESS TilAN 325' F l 3. Check PRZR temperature - 4
, LESS 111AN 430* F
! 4. Check RCS pressure -
) LESS THAN 325 PSIO
- d. Place low temperature over pressure protection relief valves in sersice IN ACCORDANCE WTI11 NOo 2.3 4, ilOT STANDBY htODE 3 TO COLD SHUTDOWN hiODE 5 {
Page 7 of 12
JUN 3 1988 t
. NUMBER TTIM REV. ISSUE /DATE !
ES.3.2 POST.SGTR COOLDOWN USING BLOWDOWN Rev.3 i
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 7
9 CHECK IF RCS C00LDOWN I SHOULD BE STOPPED: l l
- a. Chxk RCS temperature - '
- a. RETURN IQ Step 3.
LESS THAN 300* F (277' F FOR ADVERSE CONTAINhtEST)
- b. Stop RCS cooldown 10 CHECK RUlrTURED SG(s) REFILL RUPTURED SG(s) TO 69 % L WIDE RANGE LEVEL USING AUX FEEDWATER FLOW. '
GREATER THAN 63 %
(67 % FOR ADVERSE E EITHER ONE OFTHE CONTAINhtENT) FOLLOWING CONDITIONS OCCUR, THEN STOP FEEDWATER FLOW TO THE RUlrrURED SG(s):
o Ruptured SG pressure (s) decreases in an uncontrolled manner o Ruptured SG pressure (s) increases i
to 935 PSIG.
i i NOTE: BLOWDOWN FROM RUPTURED SG(s) MAY BE STOPPED WHEN RHR IS IN SERVICE. ;
j l 11 ESTABLISH BLOWDOWN FROM L
- RUI'TURED SG(s):
- a. Perform the following: a. E blowdown from rupture SG(s)
- can NQI be established, -
! 1. Isolate intact SG(s) from the 111EN QQID either ue of the ,
blowdown tank following:
- 2. Lineup blowdown tank drains o ES 3.1, to the blowdown cooler POST-SGTR COOLDOWN IN ACCORDANCE WTDI USING EACKFILL, Step 1 NOP 2.1414, STEAhi GENERATOR BLOWOFF M i 1
TANK OPERATION l j o ES 3.3,
< POST SGTR COOLDOWN USING STEAhi DUhiP, Step 1. j i
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JUN 3 1988
. NUMBER TTlu REY. ISSUE /DAE ES 3.2 PO^T SGTR COOLDOWN USING BLOWDOWN Rev.3 )
t i
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l
12 CONTROL RCS MAKEUP AND ,
i LE1DOWN FLOW TO hiAINTAIN RCS PRESSURE ,
NOTE: THE UPPER HEAD REGION MAY VOID DURING RCS <
l DEPRESSURIZATION IF RCPs ARE NOT RUNNING. THIS MAY RESULT IN A RAPIDLY INCREASING PRZR LEVEL. l i
13 DEPRESSURIZE RCS TO MINIhilZE RCS TO SECONDARY LEAKAGE: f
- a. Adjust charging and letdown a. Use alternate letdown to reduce ,
flow to reduce RCS pressure RCS pressure. l
- b. Maintain RCS pressure at ;
ruptured SG(s) pressure
- c. Maintain RCS subcooling based on
[
core exit thermocouples - 1 i i GREA'ER DIAN 32' F l
. (SEE OPPOSTm PAGE ,
FOR ADVERSE COSTAINMENT) l' l
14 CIIECK IF RCPs MUST BE I SHUTDOWN: , i J
l a. Check the following: a. GQIQ Step 15. i i
i o Number 1 seal differential- !
i LESS THAN 275 PSIG i 2 l '-
o Number I sealleakoff flow - i LESS THAN 0.2 GPM i i
- b. Stop affected RCP(s) l j l ,
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JUN 31983
, NUMBER TTTIE REV. ISSLTJDATE !
ES 3.2 POST SGTR COOLDOWN USING BLOWDOWN Rev.3 i l
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- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 CliECK IF RHR SYSTEM CAN BE PLACED IN SERVICE
- a. Check the following: a. RETURN I_Q Step 10.
I
- o. Check RCS temperature - i LESS DIAN 300' F l l (277' F FOR ADVERSE -
CONTAINMENT)
- o. Check RCS pressure - 4 LESS THAN 300 PSIG I (t 310 PSIG FOR ADVERSE CONTAINMENT)
- b. Place RHR in service IN ACCORDANCE WTTH r 1
NOP 2.91. '
RHR SYSTEM PLACING SYSTEM '
IN SERVICE 2 ,
16 CONTINUE RCS COOLDOWN TO i COLD SHUTDOWN: .
I .
- a. Maintain cooldown rate in RCS i cold lelts - t LESS 'RAN 100' F / HR i 3
, b. Use RHR system ifin service
- c. Dump steam to the condenser c. Manually OR locally dump steam .
1 j from intact SG(s) from intact SG(s): ,
l j o Use atmospheric vent valve. j IE no intact SG available. !
l t THEN perform one of the following: l l
o Use faulted SG i OfL i
o QQIQ ECA 3.1. ,
i SGTR WID{ LOSS OF l l REACTOR COOLAST- .
SUBCOOLED RECOVERY -
) DESIRED, Step 1. i I l !
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h JUN 3 1988
, NUMBER TTIM REY. ISSLT/DAR }
ES 3.2 POST SGTR COOLDOWN USING BLOWDOWN Rev.3 I
' r
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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAENTD 17 CHECK RCS TEMPERATURE RETURNIQ STEP 10.
LESS THAN 200* F ,!
18 EVALUATE LONG1ERM PLAST STATUS:
- a. Maintain cold shutdown condidons j l
- b. Consult plant engineering staff l !
END j l 1
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JUN 3 1988 NUMBER uld REY. lSSl'EDAR ES 3.2 {
POST SGTR COOLDOWN USING BLOWDOWN Rev.3 l-i l
A*ITAC11htENT A His procedure is to be used to cooldown an affected loop if it had been properly isolated j in E 3, STEAh! GENERATOR TUBE RUP'nJRE.
I '
INITIAL CONDITIONS
- 1. Loop Tc and n isolation valves are closed and loop bypass valve is open.
- 2. Loop drain htOV is open and loop pressure is being maintained by drain header throttle valve, Dil htOV 310.
- 3. Seal water is being supplied to the RCP and the RCP is shutdown.
PROCEDURE
- 1. Lineup the B AhtT to the suction of the metering pump and lineup the metering pump discharge to the fill header only.
- 2. Perform the following: ,
o Close A and B charging pump discharge isolaG.m valves to the fill header, j I o Open affected loop manual drain valve and close the affected loop drain htOV. ,
o Lineup the drain header to the PDT. t
- 3. Open affected loop fill header htOV and then borate the affected loop to the cold shutdown boron concentration. When boration completed, lineup the metering pump suction to the RWST and flush approximately 200 gallons through the lines to the affected loop.
- 4. Perferm the following: l
- a. Isolate unaffected SGs from the blowdown tank. Lineup the affected SG(s) to the blowdown tank. l
- b. Lineu ) the blowdown tank drains through the blowdown cooler IN ACCORDANCE !
WIE NOP 2.14-14, STEAh! GENERATOR BLOWOFF TANK OPERAT10N. j
- 5. Feed affected SG(s) as necessary to maintain wide range SG level (s) !
between 59 % and 69 %.
1
- 6. hiaintain affected loop temperature and pressure within limits of Technical Specifications Section 3.4, FIGURE 3.4 9 during loop cooldown. Periodically sample affected loop to insure boron concentration is withm specification. ;
- 7. When affected loop pressure is less than 100 PSIG, close seal water retum htOV from affected RCP. ;
- 8. When the loop is cooled down and depressurized. isolate seal water supply to affected i RCP. Prepare to drain the affected loop IN ACCORDANCE WTni NOP 2.4 5, ,
DRAINING AN ISOLATED LOOP.
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