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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 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
,
Stephen E. : ace 3-31-87 87-l2 Form Approved by Stat wn Superintendent Effective Ooci 50RC Mtg. No.
STATION PROCEDURE COVER SHEET .
(,) A. IDENTIFICATION Number E0P 35 ES-3.3 Rev. 2 1 Title POST-SGTR C00LOOWN USING STEAM DUMP Prepared By R. F. MxRTIN B. REVIEW I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATURE DATE DEPARTMENT HEAD (,[4&P
- y. ~,
C. SPECIFIC UNREVIEWED SAFE 1Y QUESTION EVALUATION REQUIRED:-
Modifies intent of procedure and changes operation of systems as described in design documents. YES [ ] NO[Q' (If yes, perform written USQ determination and Safety Evaluation, and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)
Q ENVIRONMENTAL REVIEW REQUIRED (Adverse environmental impact) YES [ ] NO [T
- 0. SPECIFIC SAFETY EVALUATION REQUIRED Affects response of safety systems, performance of systems which may have been credited in the safety analysis or non-credited systems wh;ch may indirectly affect safety system response. YES [ ] N0 [ }
(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 [M F. PROCEDURE REQUIRES /SORC REVIEW (In addition to revi%, ite.ms with a YES response '
must be documented in the P /50RC meeting minutes.) YES f] NO [ ]
G. 50RC APPROVAL SORC Meeting Number 1-V~J-2d7 H. APPROVAL AND IMPLEMENTATION The attach' + dure ereby approved, and effective on the date below:
/p ,,
$ - n * )~f
~5tation/ service / Unit SuperTntendent cffective Date SF 301 Rev. 9 Page 1 of 1 0010260?O0 001007 PDR ADOCK 0500021J P ppg
- . _ _ _ _ ..____._._________._.____._.___..____._...-.____.._..=_m..___ . . _ _ . .
-l E0P 35 ES-3.3 Page 1 i Rev. 2 .'
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. POST-SGTR C00LD0kW USING STEAM DUMP ECP 35 ES-3.3 Page 2 l Rev. 2 ,i l'
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A. PURPOSE This procedus'e provides actions to cool down and depressurize the plant to cold shutdown conditiens following a steam generator tube rupture. This recovery method depressurizes the ruptured SG(s) by dumping steam.
B. ENTRY CONDITIONS ,
This procedure was written for Modes 1, 2 and 3 assuming RHR System is not in service. Using this procedure when not in these modes requires a step by step evaluation to determine if the required action is still applicable to current plattt conditions. ;
- 1. This procedure is entered from
- a. E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 39, if
- Director of Station Emergency Organization (DSE0) selects steam dump method.
- b. E0P 35 ES-3.2, POST-SGTR C00LD0kW USING BLOWD0kN, Step 9,
- 1 when blowd.own is not available and Director of Station Emergency Organization (DSEO) selects steam dump method. ,
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POSI-5GIR COOLDOWN USING SIEAM DUMP EUP 35 ES 3.3 Page 3 Rev. 2 i )
Q ,i STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION
- 1. Steam should not be released from any ruptured SG if water may exist in its steamline.
- 2. An offsite dose evaluation should be completed prior to using this procedure.
N0YE Foldout page should be open.
1 Turn ON PZR lleaters As Necessary To Saturate PZR Water At Ruptured SG(s) Pressure 2 Check if SI Accumulators Should Be Isolated
,_s a. Check RCS subcooling a. Go to E0P 35 ECA-3.1,
( ') based on core exit TCs SGTR WITH LOSS OF
\s / > 30 F (90 F FOR REACTOR COOLANT -
ADVERSE CONTAIN' MENT) SUBC00 LED RECOVERY AND DESIRED, Step 1.
PZR level > 7.0% (50% FOR ADVERSE CONTAINMENT)
- b. Restore power to isolation valvas - AVAILABLE (32-2R-RSF, 32-2W-R3J, 32-2R-F4M, 32-2W-F4M)
- c. CLOSE all SI accumulator c. Vent any unisolated isolation valves accumulators.
- d. Remove power from isolation valves O
O 2hkv4.1 3 44
POST-SGTC COOLDOWN USING STE AM DUMP EUP 35 ES-3.3 Page 4 Rev. 2
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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Dilution of RCS boron concentration may occur on transfer of secondary water into the RCS.
3 Verify Adequate Shutdown Margin
- a. Sample RCS
- b. Shutdown margin - ADEQUATE b. Borate as necessary.
CAUTION CST water source for AFW pumps will be necessary if DWST level decreases to < 80,000 gal.
NOTE (g) If the SG 1evels are out of the narrow range, N- ' the wide range SG level indication should be used to anticipate approach to the narrow range and also as an early aid in identifying previously undetected steam generator tube failures.
4 Checa Intact SG Levels
- a. Narrow range level a. Maintain total feed flow
> 4.0% (34% FOR ADVERSE > 525 gpm until narrow CONTAINMENT) range level > 4.0% (34%
FOR ADVERSE CONTAINMENT) in at least one SG.
- b. Control feed flow to b. IF narrow range level in maintain narrow range any intact SG continues level between 4.0% to increase in an (34% FOR ADVERSE uncontrolled manrier , THEN CONTAINMENT) and 50% go to E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
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rubi-dVIK LUULUUWS UbihU ditAM DUMP EOF 35 ES-3.3 Page 5 Rev. 2 ;
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STEP ACTION / EXPECTED RESPONSE RESPONSC NOT OBTAINED l l
NOTE
- 1. Since ruptured SG(s) may continue to depressurize to less than the minimum RCS pressare necessary for '
continued RCP operation, cooldown to cold shutdown should be completed as quickly as possible, not to e~ceed 100 F/hr.
- 2. The Main S_ nam Isolation Valves Cooldown mode should be actuated for intact SG(s) when RCS temperature indicates approximately 400*F to preclude inadvertent closure of these valves.
5 Initiate RCS Cooldown To 350*F
- a. Maintain cooldown rate in RCS cold legs
< 100*F/HR
- b. Dump steam to conuenser b. Manually OR locally dump
()
from intact SG(s) steam to a mosphere.
's_,,/ IF no intact SG available, THEN use a faulted SG OR go to E0P 35 ECA-3.1, SGTR WITil LOSS OR REACTOR COOLANT -
SUBC00 LED RECOVERY DESIRED, Step 1.
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q t >- i 2( - POST-SGTR COOLDOWN USING STEAM DUMP E0P 35 ES-3.3 Page 6 }
Rev. 2 3
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CAUTICN {
j RCS and rupture SG(s) preasures srust be maintained less than the ruptured SG(s) ataospheric dump setpoint.
,6 Control RCS Pressure And Makeup Flow To Minimize RCS-To-Secondary Lealage
- a. Perform appropriate action (s) from table RUPTURED SG(s) INCREASING DECREASING OFFSCALE VEL HIGH PZR LEVZL
<!7% -
Increase RCS Increase RCS Increase RCS j, (50% FOR ADVERSE Makeup Flow Makeup Flow Makeup Flow
- CONTAINMENT)
AND AND i
i Depressurize Maintain RCS RCS Using And Ruptured Step 6b SG(s) Pressures Equal BETWEEN Depressurize Turn On Maintain RCS 17% (50% RCS Using PZR And Ruptured FOR ADVERSE Step 6b Heaters SG(s) Pressures CONTAINMENT) and 50% Equal BETWEEN 50% AND Depressurize Turn On Maintain RCS 73% (50% FOR ADVERSE RCS Using PZR And Ruptured l CONTAINMENT) Step 6b Heaters SG(s) Pressurew Equal f A_N,_D,,
i Decrease RCS Makeup Flow '
l 473% (50% FOR ADVERSE Decrease RCS Turn on Maintain RCS l CONTAINMENT) Makeup Flow PZR And Ruptured i Heaters SG(s) Pressures
- Equal 1
l b. Use normal PZR spray b. IF letdown is in service,
- per Step 6a. TITEN use auxiliary spray.
IF NOT, THEN use one PZR PORV.
oexes.: t 64 i
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. rusi-duin toutuuw;. c31.30 ditAn uuar tue 35 ts-3.3 vage i Rev. 2 c.
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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -
7 Check if RCS Cooldown should be stopped ,
- a. RCS Temperatures a. Return to Step 3.
< 350'F (350*F FOR * '
ADVERSE CONTAINMENT)
- b. Stop RCS cooldown NOTE If the following step, it is intended that the operator allow the ruptured SG to drain to a low narrow level and then refill it to a high narrow range level rather than continueusly feeding the ruptured SG to control level.
8 ; beck Ruptured SG(s) Refill ruptured SG to 82%
Narrow Range Level (60% FOR ADVERSE
> 4.0% (34% FOR ADVERSE CONTAINMENT) using feed flow.
CONTAINMENT) IF ruptured SG pressure d-creases in an uncontrolled ma T.n 0_R ruptured SG pressure ince asas to 1100 psig, THEN stop feed flow to ruptured SG.
fJ}
CAUTION Ruptured SG(s) pressure may decrease rapidly when steam is released. g NOTE Steam release from ruptured SG(s) may be stopped when RHR System is in service.
,9 Lump Steam From Ruptured Dump steam using ruptured SG(s) To Condenser SG(s) .Rmospheric dump.
10 Control RCS Makeup And Letdown To Maintain PZR Level
- a. PZR level > 17% (50% a. Increase RCS makeup FOR ADVERSE CONTAINMENT) flow as necessary. Go to Step 11.
- b. p2R level < 73% (50% b. Decrease RCS makeup
'~' flos as necessary.
FOR ADVERSE CONTAISMENT)
Go to Step 12.
cevna 3 e4
POSI-SGTR COOLDOWN USING STEAM DUMP E0P 35 ES-3.3 Page 8 Rev. 2
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STEP ACTION / EXPECTED RESPONSE PESPONSE NOT b5?AINED NOTE The' upper head region may void during RCS depressurization if RCPs are not rur.ning . This may result in a ranidly increasing PZR level.
11 Depressurize RCS To Minimize RCS-To-Secondary Leakage
- a. Use normal PZR spray a. If letdown is in service, THEN use auxiliary spray.
IF NOT, THEN use one PZR PORV.
- b. Turn ON PZR heaters as necessary
- c. Maint 'n RCS pressure at ruptu. SG(s) pressure
- d. Maintait ;S subcooling based on m ore exit TCs (s'--) > 30*F (90*F FOR ADVERGE CONTAINt1ENT) 12 Check If RCPs Must Be Stopped
- a. check the following a. Go to Step 13.
- 1) Number 1 seal differential pressure
( 210 psid OR
- 2) Number 1 23 q flow < .. y
- b. STOP affected RCP(=)
v cevo a a en m.
POSI-SGTR COOLDOWN USING STEN! DialP E0P 35 ES-3.3 Page 9 Rev. 2
( )
ACTIONiEXPECTED RESPONSE RESPONSE NOT OBTAINED
_ STt? l 13 Check If RHR System Can Be Placed In Cooldown Mode
- a. Check RCS temperature a. Go to Step e.
< 350'F A_ND RCS preasure < 390 psia
- b. Place Rl[R system in cooldown mode using CP 3208 PLANT C00LDOWN
- c. Stop dumping steam from the l ruptured SG(s) 14 Continue RCS Cooldown To Col: Shutdown
- a. Flaintain cooldswn rate in RCS cold legs
< 100 F/llR
- b. Use RHR System
^' c. s'. cam to condenser
[ Dump c. Planually OR locally Q) f rom intaa SG(s) dump steam to atmosphere E no intact SG available and RHR NOT in service, TifEN use a faulted SG OR go to E0P 35 ECA-3.1, SGiR WITH LOSS OF REACTOR C00LAh T - SUBC00 LED RECOVERY DESIRED, Step 1.
15 Check RCS Temperatures Return to Step 8.
A@ RVLt!S llead TC's < 200*F 16 'laintain cold shutdown condttions '
-FINAL-(O) s
'Ns'
(
OP$ty) 1 3 44
FOLDOUT FOR E-3 SERIES PROCEDURE
- 1. SI REINITIATION CRITERIA Manually operate ECCS pumps as necessary and go to E0P 35 ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED RECOVERY DESliED, r Step 1, if EITHER condition listed below occurs
- a. RCS subcooling based on core exit TCs < 30'F (90'F FOR ADVERSE ;
CONTAlh?iENT) l
-OR- ,
- b. PZR level - CANNOT BE MAINTAINED > 7.0% (50% FOR ADVERSE ,
CONTAIh?!ENT)
- 2. RED PATH
SUMMARY
- a. SUBCRITICALITY - Nuclear power > 5% .
- b. CORE COOLING - Core exit TCs > 1200*F l
- c. HEAT SINK - Narrow range level in all SGs < 4% (34% FOR ADVERSE l 4 CONTAINMENT) AND total feedwater flow < 525 gpm !
- d. INTEGRITY - Cold leg temperature decrease > 100*T in last 60 7 minutes AND RCS cold leg temperature < 252'F '
- e. CONTAINMENT - Containment pressure > 60 psia ,
- 3. SECONDARY INTEGRITY CRITERIA Go to E0P 35 E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1 if any ;
SG pressure is decreasing in an uncontrolled manner OR has O completely depre'ssurized, and has not been isolated, unless ne ded for RCS cooldown. ;
- 4. COLD LEG RECIRCULATION SWITCHOVER CRITERION Go to E0P 35 ES-1.3, TRANSFER TO COLD LEG RECIRCULOTION, Step 1. if RWST level decreases to < 520,000 gallons.
- 5. AFV SUPPLY SWITC110VER CRITERION l Switch to alternate AFV water supply if DWST 1cvel decreases to .
. < 80,000 gallons. l
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