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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
r* JUN 0 31988
- NUhGEP TTT12 REV. ISSUE /DATE i E bC. ': NATURAL CIRCULATION COOLDOWN WITH Rev. 4 STEAM VOID IN VESSEL (WITHOUT RVLIS)
(,
i A. PURPOSE l l
This procedure provides actions to cor.tinue plant cooldown and depressurization to cold !
shutdown, with no accident in progress, under conditions that allow for the potentia] formation of a void in the upper head r:gion without a vessel level system available to monitor void growth.
B. SYMPTOMS OR ENTRY CONDITIONS This procedure is entered from ES-0.2, NATURAL CIRCUL ATION COOLDOWN, ,
after completing the first thineen steps. i i
i l
1 i
Page 1 ef 13 8810250198 001007 PDR ADOCK 05000213 P PDR
l JUN 0 31989 NUMBER TTII.E REV. ISSUE /DATE .
ES.O.4 NATURAL CIRCULATION COOLDOWN WITH Rev.4 :
STEAM VOID IN VESSEL (WITHOUT RVLIS)
(
STEP ACTIO / EXPECTED RESPONSE RESPONSE NOT OBTAIhTD l
r 7 !
CAUTION: o IF SI ACTUATION OCCURS DURING THIS PROCEDURE, E 0, REACTOR TRIP OR SAFETY INJECTION, SHOULD BE PERFORSfED.
o THE FIRST THIRTEEN STEPS OF ES 0.2, NATURAL CIRCULATION COOLDOWN, SHOULD BE PERFORSfED BEFORE CONTINUING WITH THIS PROCEDURE. !
L J l
NOTE: o FOLDOUT PAGE SHOULD BE OPEN.
o RCPs SHOULD BE RUN IN ORDER OF PRIORITY TO PROVIDE NORAfAL PRZR SPRAY.
o IF CONDITIONS CAN BE ESTABLISHED FOR STARTING AN RCP DURING THIS PROCEDURE, STEP 1 SHOUL.D BE REPEATED.
1 TRY TO START AN RCP:
- a. Chec': PRZR level - a. Control charging and letdown GREATER THAN 75 % as necessary to increase PRZR level to greater than 75 %. I i
- b. Check RCS subcooling based b. Establish subcooling greater on core exit thermocouples - than 60* F by dumping steam.
GREATER THAN 60* F Page 2 of 13
JUN O 31988 NUMBER TITLE REV. ISSUE /DATE ES 0.4 NATURAL CIRCULATION COOLDOWN WITH Rev.4 i STEAM VOID IN VESSEL (WITHOUT RVLIS) l
(
ST1EP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 c. Establish conditions for starting an RCP: c. EQIQ Step 2
- 1. Close loop Tc isolation valve -
i i
- 2. Open loop bypass valve
- 3. Stan oilItft pump
- 4. Insure seal water and component '
cooling water supplied to RCP
- 5. Insure lower bearing temperature l is less than 170' F
- 6. Check RCS pressure j greater than 300 PSIG ,
- 7. Check open CH-TV-240, 7. Open CH TV-240, CH TV 241 CH-TV 241 and CH TV-334, and CH TV 334.
(scal water return trip valves)
- 8. Check o pen CC-TV-1411 8. Open CC TV 1411 (RCP oil cooler CCW return trip valve)
- 9. Open seal water return MOV
- d. Stan selected RCP d. IE RCP did EQ_I start, THEN perform the following: THEN perform the following:
- 1. Open loop Tc isolation valve 1. Open loop Tc isolation valve
- 2. Close loop bypass valve 2. Close loop bypass valve j QQIQ Step 2.
- e. Align PRZR spray valves
- f. GQIQ NOP 2.3 4, HOT STANDBY TO COLD j SHUTDOWN, Step 1 ,
i i NOTE: SATURATED CONDITIONS IN THE PRZR SHOULD BE ESTABUSHED BEFORE TRYING TO DECRESASE PRZR LEVEL.
2 ESTABLISH PRZR LEVEL TO ACCOMMODATE VOID GROWITI:
- a. Check PRZR level- a. Control charging and letdown BETNEEN 20 % AND 25 % as necessary to establish level.
I
- b. Place PRZR level controlin manual Page 3 of 13
JUN 0 3198e NUMBER TTR E REV. ISSUE /DAE I ES 0.4 NATURAL CIRCULATION COOLDOWN WITH Rev.4 !
STEAM VOID IN VESSEL (WITHOUT RVLIS) ;
l STEP ACTION /EXPECED RESPONSE RESPONSE NOT C JTAINED 3 DECREASE CORE EXIT THERhiOCOUPLES TO 500* F:
- a. hiaintain cooldown rate in RCS cold legs -
LESS THAN 50' F / HR
- b. hiaintain RCS pressure -
AT 1750 PSIG !
- c. hiaintain RCS temperature and pressure -
WITHIN LIhilTS OF TECHNICAL SPECIFICATIONS SECTION 3.4, FIGURE 3.4 9
- d. hiaintain stable PRZR level using charging
- e. Check core exit thermocouples - e. RE'lliR.N IQ Step 3 a.
LESS THAN 500' F
- f. Stop RCS cooldown l I
,* r--
CAUTION: INSURE St ACTUATION SIGNAL IS BLOCKED PRIOR TO DEPRESSURIZING THE RCS.
L J 4 DEPRESSURIZE RCS TO 1600 PSIG:
- a. Check letdown IN SERVICE a. Use one PRZR PORV.
QQIQ Step 4 c.
- b. Use auxiliary spray
- c. Check RCS pressure -
LESS THAN 1600 PSIG c. RETURN IQ Step 4 a.
- d. Stop RCS depressurizathn h
Page 4 of 13
JUN 0 31988 j NUMBER TITLE REV. ISSUE /DATE i ES 0.4 NATURAL CIRCULATION COOLDOWN WITH Rev.4 1 1
STEAM VOID IN VESSEL (WITHOUT RVLIS) ! l
(
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OB RAINED 5 DECREASE CORE EXIT :
UIERMOCOUPLESTO450 F: ;
- a. Maintain cooldown rate in RCS l cold legs - l LESS THAN 100* F / HR i
- b. Maintain RCS pressure - ,
AT 1600 PSIG I
- c. Maintain RCS temperature and ;
pressurc - ,
WITHIN LIMITS OF TECHNICAL i SPECIFICATlONS SECTION 3.4, FIGURE 3.4 9
- d. Maintain stable PRZR level using charging I
- e. Check core exit thermocouples - e. RETURN T_Q Step 5 a.
LESS DIAN 450* F
- f. Stop RCS cooldown !
l 6 EQUALIZE CHARGING AND i LEEOWN FLOWS: l
- a. Place charging and letdown
'ontrols in manual
- b. Control charging and seali *ection !'
flows to equalletdown and al leakoff flows 7 MAINTAIN RCP SEAL INJECTION FLOW: 5 l'
- a. 'Thronle seal supply valves !
(CH V 354A through D) to maintain labyrinth differential pressure between 5" and 10" of water pressure Page 5 of 13
JUN03iSSF l
. NUMBER TIT 12 REV. ISSLT/DATE !
ES 0.4 NATURAL CIRCULATION COOLDOWN WITH Rev.4 STEAM VOID IN VESSEL (WITIIOUT RVLIS) ;
(
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: THE UPPER HEAD REGION MAY VOID DURING DEPRESSURIZATION. THIS WILL RESULTIN A RAPIDLY INCREASING PRZR LEVEL.
i I l 8 DEPRESSURIZE RCS TO 800 PSIG: l l
- a. Checkletdown-IN SERVICE a. Use one PRZR PORV. l QQIQ Step 8 c. -
- b. Use auxiliary spray
- c. Depressurize RCS until either one of the following conditions is satisfied:
o RCS pressure -
LESS THAN 800 PSIG QR o PRZR level - i GREATER THAN 90 % <
- d. Stop RCS depressurization I
NOTE: IN ORDER TO CONTINUE OVERALL SYSTEM DEPRESSURIZATION, IT MAY BE NECESSARY TO CYCLE PRZR LEVEL (CYCLE PRESSURE) TO ENHANCE UPPER HEAD COOUNG.
9 CliECK PRZR LEVEL INCREASE RCS PRESSURE BY LESS THAN 90 % 100 PSIG USING PRZR HEATERS. .
RETURN IQ STEP 8.
I i
Page 6 of 13
JUN 0 31988 NUMBER TTTLE REV.13 SUE /DATE ES.O.4 NATURAL CIRCULATION COOLDOWN WITH Rev.4 STEAM VOID IN VESSEL (WITHOUT RVLIS)
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 DECREASE CORE EXIT EEPJ.10 COUPLES TO 400 F:
- a. Maintain cooldown rate in RCS cold legs -
LESS THAN 100* F / HR
- b. Maintain RCS pressure -
STABLE
- c. Maintain RCS temperature and pressure -
WITHIN LIMITS OF TECHNICAL SPECIFICATIONS SECTION 3.4, FIGURE 3.4 9
- d. Maintain stable PRZR level using charging
- e. Check core exit thermocouples - e. RETUILN IQ Step 10 a.
LESS THAN 400' F
- f. Stop RCS cooldown j 11 EQUALIZE CHARGING AhD !
LE1DOWN FLOWS: l
- a. Place charging and letdown !
controls in manual !
- b. Control charging and sealinjection flows to equal letdown and seal leakoff flows Page 7 of 13 fL
I JUN 0 31988
. NUMBER Tm.E REY. ISSUE /DAE ,
ES 0.4 NATURAL CIRCULATION COOLDOWN WITH Rev.4 !
STEAM VOID IN VESSEL (WITHOUT RVLIS) l
[
STEP ACTION /EXPECED RESPONSE RESPONSE NOT OBTAINED 12 DEPRESSURIZE RCS TO 600 PSIO:
I
- a. Check letdown -IN SERVICE a. Use one PRZR PORV.
EQIQ Step 12 c. l l
- b. Use auxiliary spray ;
- c. Depressurize RCS until either '
one of the following conditions is satisfied: f o RCS pressure - l LESS THAN 600 PSIG l QR o PRZR level -
GREATER THAN 90 %
i
- d. Stop RCS depressurization 13 CHECK PRZR LEVEL INCREASE RCS PRESSURE BY LESS THAN 90 % '00 PSIG USING PRZR HEATERS. !
RETURN IQ STEP 12. j i
l 1
l Page 8 of 13
JUN 0 31988 !
NUMBER TTTLE REV. ISSUE /DATE ,
ES.O.4 NATURAL CIRCULATION COOLDOWN WITH Rev.4 l STEAM VOID IN VESSEL (WITIIOUT RVLIS) l t
SEP ACTION / EXPECTED RESPONSE l RESPONSE NOT OBTANED ,
1 r , '
CAUTIONt THE SI SYSTEbf hfUST BE DISABLED BEFORE RCS TEbfPERATURE IS LESS THAN 315
L J 14 DISABLE THE SI SYSTEM:
- a. Check core exit thermocouples - a. Continue RCS cooldown.
LESS THAN 350 F WHEN core exit thermocouples are l less than 350' F.,
- b. Align core cooling equipment IN ACCORDANCE WTTH NOP 2.3 4, HOT STANDBY MODE 3 TO COLD SHUTDOWN MODE 5 AS2 NOP 2.121, CORE COOLING SYSTEM LINEUP FOR SHUTDOWN AND AT POWER I OPERATION !
I i
l i
i I
I I
I i
i Page 9 of 13
JUN 0 31988 l
NUMBER TITLE REV. ISSUE /DATE !
ES 0.4 NATURAL CIRCULATION COOLDOWN WITH Rev.4 !
STEAM VOID IN VESSEL (WITHOUT RVLIS) i
( -
STEP ACTION /EXPECIED RESPONSE RESPONSE NOT OBTAINED 1
15 DECREASE CORE EXIT '
l '
11IERMOCOUPLES TO 300* F
- a. Maintain cooldown rate in RCS cold legs -
LESS THAN 100* F / HR
- b. Maintain RCS pressuit - !'
STABLE
- c. Maintain RCS temperature and pressure -
WITHIN LIMITS OF TECHNICAL SPECIFICATIONS SECrlON 3.4, FIGURE 3.4 9
- d. Check core exit thermocouples - d. RETURNIQ Step 15 a.
LESS THAN 300' F
- f. Stop RCS cooldown 16 EQUALIZE CHARGING AND LE1DOWN FLOWS:
- a. Place charging and letdown i controls in manual j
- b. Contml charging and seal injection j flows to equalletdown and seal leakoff flows Page 10 of 13
JUN 0 31988 NUMBER THE REV. ISSUE /DATE I ES 0.4 NATURAL CIRCULATION COOLDOWN WITH Rev. 4 j STEAM VOID IN VESSEL (WITHOUT RVLIS) i
(
5TEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 DEPRESSURIZE RCS TO 300 PSIG: i
- a. Check letdown -IN SERVICE a. Use one PRZR PORV.
QQIQ Step 17 c. i l
- b. Use auxiliary spray
- c. Depressurize RCS until either one of the following conditions I
is satisfied o RCS pressure -
LESS THAN 300 PSIG OR o PRZR level-GREATER THAN 90 %
- d. Stop RCS depressurization 18 CHECK PRZR LEVEL INCREASE RCS PRESSURE BY LESS THAN 90 % 100 PSIG USING PRZR HEATERS. !
RETUR'.'IQ STEP 17. l 19 CHECK IF RHR SYSTEM CAN BE f PLACED IN SERVICE: I
- a. Check RCS te - a. RETURN IQ Step 15.
LESS THAN F l
- b. Check RCS pressure - b. BEIURNIQ Step 17.
LESS THAN 300 PSIG i
- c. Place RHR in service IN ACCORDANCE WITH NOP 2.91, RilR SYSTEM PLACING SYSTEM IN SERVICE 20 CONTINUE RCS COOLDOWN TO COLD SHUTDOWN l
1 Page 11 of 13
l JUN 0 31988 ,
I NUMBER TTT12 REV. ISSUE /DATE ]
ES 0.4 NATURAL CIRCULATION COOLDOWN WITH Rev.4 :
STEAM VOID IN VESSEL (WITIIOUT RVLIS) l t
S11P ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINTD r 1 i CAUTION: DEPRESSURIZING THE RCS BEFORE THE ENTIRE RCS IS LESS THAN 200* F MAY RESULTIN ADDITIONAL VOID FORMATION IN THE RCS. l L J l I
21 CONTINUE COOLDOWN OF f INACTIVE PORTION OF RCS: i
- a. Cool upper head region using l CRDM fans l
- b. Cool SG U tubes by dumping steam from all SGs 22 DETERMINE IF RCS DEPRESSURIZATION IS PERMITTED:
- a. Check entire RCS temperature - a. DO NOT DEPRESSURIZE RCS.
LESS THAN 200' F RETURNIQ Step 20.
l
- b. CD IQ NOP 2.3-4, >
HOT STANDBY MODE 3 TO COLD ;
SHUEOWN MODE 5 END l l
I t
l t
l l
U Page 12 of 13
JUN 0 31983 REV. ISSUE /DAE Rev 4 FOLDOUT ERR E-D SERIES PROCEDURES
- 1. ' RCEBIE CRITERIA IE BOTH of the following conditions exist.
THEN t2ip all RCPs:
- a. HPSI pump QR charging pump - AT LEAST ONE RUNNING
- b. RCS Pressure - LESS THAN 1150 PSIG (1380 PSIG FOR ADVERSE CONTAINhiENT).
2 IE any of the following conditions occur,
'IEENimmediately trip all RCPs:
o Loss of component cooling water to RCPs.
o Complete loss of control air.
o Complete loss of htCC 5 M semi vital power, o Loss of either banery Bus A QR battery Bus B.
( RCPs with de control power supplied from the effected battery bus must be tripped locally).
OR IE any RCP motor bearing temperature reaches 200' F.
THEN trip the effected RCP.
- 2. SI ACTUATION CRITERIA IE EITHER condition listed below occ rs, actuate SI, THEN O_Q Q IQ E 0, REACTOR TRIP OR S AFETY INJEC110N, Step 1.
o RCS subcooling based on core exit thermocouples LESS THAN 32' F.
o PRZR level CANNOT BE hiAINTAINED GREA'IER THAN 10%
(24% FOR ADVERSE CONTAINhiEST).
- 3. EER PATH SUhihfARY
- a. SUBCRITICALLY - Nuclear power greater than 5%.
- b. CORE COOLING - Core exit thermocouples greater than 1200* F.
- c. HEAT SINK - Wide range level in all SGs less than 63%
(67% for adverse containment)
M total feedwater flow less than 320 GPht.
- d. INTEGRITY - Cold leg temperature decreases greater than 100' F in last 60 minutes M RCS cold leg temperature less than 231' F.
- c. CONTAINhiEST- Containment pressure greater than 40 PSIG.
4 M SUPPLY h1AKEUP CRITERION Start makeup to DWST before level decreases to 54,000 gallons, i
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