Letter Sequence Other |
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MONTHYEARML19260C8731980-01-30030 January 1980 Forwards Preliminary Design Description & Criteria for Proposed Reactor Coolant High Point Vent Sys for Facility,In Response to 790913 & 1030 Ltrs.Projects Installation of Pressurizer & Hot Leg Vents During Spring 1981 Outage Project stage: Other ML19309E5041980-04-15015 April 1980 Advises That Installation of Proposed Reactor Vessel Head Vent Is Still Under Review.Design Requires Vent Path W/Two Isolation Valves in Series.Installation Scheduled for 1981 Refueling Outage Project stage: Other ML19347D0241981-02-27027 February 1981 Identifies Revision in Method of Flow Indication for Pressurizer & Hot Leg Vents.Solenoid Operated Valves W/Stem Operated Limit Switches Provide Open or Closed Position Switches for Indicating Lights in Control Room Project stage: Other ML20042C0181982-03-23023 March 1982 Advises of Delay Until 1983 Refueling Outage for Installation of Reactor Coolant High Point Vent Sys Per NUREG-0737 Item II.B.1.Delay Caused by Revised Design of Pressurizer Vent.Revision 2 to Design Criteria Encl Project stage: Other ML20054B8011982-04-13013 April 1982 Forwards Info Requested 820210 Re RCS High Point Vents, TMI Action Item II.B.1.Installation of Pressurizer Ventline Will Be Delayed Until 1983 Refueling Outage Project stage: Other ML20054B8041982-04-30030 April 1982 Suppl to Small Break Operating Guidelines Project stage: Other ML20077K8451983-03-14014 March 1983 Selected Operating Reactor Issues Program Ii,Rcs Vents, (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept Project stage: Other 1982-03-23
[Table View] |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm ML20107C3021995-10-16016 October 1995 Rev 8 to Odcm ML20199L1821995-09-0909 September 1995 Rev 3 to DB-OP-00000, Conduct of Operations ML20082V4071995-02-0303 February 1995 Offsite Dose Calculation Manual Rev 7 ML20072S8611994-06-22022 June 1994 Rev 6 to Davis-Besse Offsite Dose Calculation Manual ML20056F3071993-08-0808 August 1993 Rev 3 to Emergency Plan Off Normal (Epon) Occurrence Procedure HS-EP-02820, Earthquake. W/Rev 23 to Epon Occurrence Procedures Manual Table of Contents ML20035F2071993-02-15015 February 1993 Rev 0 to HS-EP-02850, Hazardous Chemical & Oil Spills ML20072S8401992-12-18018 December 1992 Rev 5 to Davis-Besse Process Control Program ML20072S8501992-12-18018 December 1992 Rev 5.2 to Davis-Besse Offsite Dose Calculation Manual, Reflecting Rev 5,Change 2 to ODCM ML20101R1721992-06-11011 June 1992 Rev 1 to Vol I of Inservice Insp Plan,Second 10-Yr Nuclear Interval Pump & Valve Inservice Testing Program ML20114C6321992-05-19019 May 1992 Change 1 to Rev 5 to ODCM ML20114C6301992-03-0606 March 1992 Rev 5 to ODCM ML20217C3661991-07-0808 July 1991 Rev 3 to Administrative Procedure NG-IS-00002, General Nuclear Security Requirements. Pages 7,9,10 & 15 Only ML20084U5911991-02-22022 February 1991 Rev 4 to ODCM ML20217C3481990-12-18018 December 1990 Rev 1 to Security Dept Procedure IS-DP-04007, Performance Test for Alco-Sensor ML20059D4181990-08-28028 August 1990 Second 10-Yr Interval Pump & Valve Inservice Testing Program ML20217C3001990-08-23023 August 1990 Rev 5 to Security Dept Procedure IS-AC-00011, Protected & Vital Area Badge Issuance & Control ML20217C3571990-08-0909 August 1990 Rev 3 to Security Implementing Procedure IS-AC-00516, Unescorted Access Requirements ML20217C3071990-07-27027 July 1990 Rev 2 to Security Dept Procedure IS-AC-00015, Fingerprint Processing & Controls ML20217C3201990-06-27027 June 1990 Rev 1 to Security Dept Procedure IS-AC-00018, Drug & Alcohol Testing Process ML20217C3811990-06-22022 June 1990 Rev 4 to Nuclear Group Procedure NG-IS-00004, Fitness for Duty Program ML20217C4001990-04-0202 April 1990 Corporate Ref Manual - Nuclear NU-102, Fitness for Duty ML20217C3401990-01-12012 January 1990 Rev 1 to Security Dept Procedure IS-DP-00101, Bac Simulation ML20217C3281989-11-0909 November 1989 Rev 1 to Security Dept Procedure IS-DP-00100, Bac Exams ML20217C3141989-10-25025 October 1989 Rev 2 to Security Dept Procedure IS-AC-00017, Denied Access List Control ML20217C3941989-08-0101 August 1989 Corporate Ref Manual - Human Resource HR-604, Drug & Alcohol Policy ML20244A8421989-05-31031 May 1989 Pressurizer Surge Line Thermal Stratification Phase I Program ML20213A0361987-03-31031 March 1987 Rev 1 to Davis Besse Emergency Procedure Verification & Validation Program ML20213A0311987-03-31031 March 1987 Rev 2 to Vol IV of Procedure Writers Manual:Operation Procedures Guidelines ML20212D1621987-01-27027 January 1987 Rev 1 to Maint Procedure MP 1411.06, Preventive Maint for Type Smb & Smc Valve Operators ML20198D2551986-12-27027 December 1986 Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & SMB-00. Temporary Mod Request T-9969,indicating Rewiring of Fcr 85-302 MU-11 to Torque Out in Open Direction,Encl ML20212B5721986-12-15015 December 1986 Rev 0 to Security Training & Qualification Plan, Superseding Rev 24 to App B of ISP AD1808.00.W/o Revised Pages ML20212C9481986-11-21021 November 1986 Rev 8 to Maint Procedure Mpo 1410.32, Testing of Motor- Operated Valves Using Movats ML20212D3131986-10-28028 October 1986 Change 3 to Temporary Mods T10161 & T10144 to Rev 0 to Maint Procedure MP 1411.07, Maint & Repair of Limitorque Valve Opr Smc 04, Incorporating Fcr 86-0092,Rev a Re Removal & Installation of Limiter Plate ML20212D1091986-10-21021 October 1986 Change 1 to Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & Smb 00, Addressing Need for Procedure to Address Replacement of Defectrive Parts ML20212D1471986-10-0303 October 1986 Rev 1 to Maint Procedure MP 1411.05, Maint & Repair of Limitorque Valve Operators Types SMB-0 Through SMB-4 ML20212C9181986-09-22022 September 1986 Rev 1 to Procedure NEP-092, Establishing D/P Limits & Tests for Q Motor Operated Valves ML20203M0201986-08-21021 August 1986 Specs for Mist Continuous - Venting Tests ML20210V1131986-08-20020 August 1986 Rev 0 to Emergency Plan Implementing Procedure EP-2320, Emergency Technical Assessment ML20206P6511986-06-30030 June 1986 GE Owners Group Action Plan as Result of Davis-Besse Event, June 1986 ML20198D2361986-05-0202 May 1986 Rev 5 to Maint Procedure MP 1410.32, Testing of Motor- Operated Valves Using Movats ML20141J5231986-04-18018 April 1986 Human Engineering Discrepancy Review & Closeout Process for Davis-Besse Dcrdr Program ML20205M6981986-04-0707 April 1986 Rev 0 to Nuclear Engineering Procedure NEP-092, Establish Differential Pressure Limits & Tests for Motor-Operated Valves ML20205M7031986-03-25025 March 1986 Rev 0 to Nuclear Engineering Procedure NEP-091, Motor- Operated Valve (MOV) Data Evaluation ML20141N1501986-02-26026 February 1986 Procedure Fcr 85-227, Main Feedwater Block Valve Interlock ML20141N1561986-02-26026 February 1986 Procedure Fcr 85-200, Main Feedwater Pumps Rapid Feedwater Reduction Speed Setpoint 1998-08-28
[Table view] |
Text
'
Docket No. 50-346 Revised by Toledo Edison License No. NPF-3 April, 1982 Serial No. 804 April 13, 1982 E 25i [l h (%
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a SUPPLEMENT TO DAVIS-BESSE UNIT 1 t
SMALL BREAK OPERATING GUIDELINES Document #69-1106003-00 l
B&W Document ID No.
l 77,-1130302-00 f
I Prepared by i
Babcock & Wilcox Company Nuclear Power Generation Division I
Lynchburg, Virginia 8204190213 820413 PDR ADOCK 05000346 P
PDR
Supplement to Davis-Besse Unit 1 Small Break Operating Guidelines Doc. 69-1106003-00 4
l Inadequate Core Cooling Use of High Point Vents Conditions:
1.
Inadequate core cooling is occurring, M
i 2.
Core exit thermocouple temperature is greater than curve 1 of figure 3 (Tclad 2 1400*F).
Required Actions for Use of High Point Vents:
I 1.0 Open hot leg high point vent valves, RC-4608A, RC-4608B, RC-4610A, and RC-4610B.
1.1 If the RCS depressurizes to less than 150 psig:
a.
Close high point vent valves, RC-4608A, RC-4608B, RC-4610A, and RC-4610B.
b.
Go to " Appendix A - LPI Cooling" of the Small Break Operating Guidelines.
1.2 When subcooling margin is obtained, close high point vent valves, RC-4608A, RC-4608B, RC-4610A, and RC-4610B.
1.3 If RC pressure remains above 150 psig, continue cooldown.
Follow Section 2.0 of this supplement if further use of vents is required.
i b
i i !
1.0-1.3
~
INADEQUATE CORE COOLING USE OF HIGH POINT VENTS 1.0 OPEN HPV VALVES RC-4608 A&B, RC-4610 A&B v
1.1 RCS DEPRESSURlZES T ypg LESS THAN 150 PSIG 1r A.
CLOSE HIGH POINT VENT g) 1.2 VALVES. RC-4608A&B, 3r WHEN SUBC00 LING MARGIN OBTAINED.
RC-4610A&B
.CLOSE HPV VALVES RC-4608A&8 &
B.
GO TO APPENDIY a 0F SB00 RC-4610A&B 1.3 IF RC PRESSURE REMAINS l
ABOVE 150 PSIG, CONTINUE C00LOOWN
Post Accident Refill Use of Hot Leg High Point Vents Conditions:
1.
Saturated conditions have occurred in the RCS, AND 2.
HPI is maintaining RC pressure greater than the required pressure for LPI operation, AND 3.
RC pumps are not available, AND 4.
Natural circulation has not been established or has stopped (e.g., RCS refill).
j Required Actions for Use of High Point Vents:
l 2.0 Open all hot leg high point vent valves, RC-4608A, RC-4608B, RC-4610A and RC-4610B.
2.1 If the RCS depressurizes to less than 150 psig:
Close all hot leg vent valves, RC-4608A, RC-4608B, RC-4610A and RC-4610B.
a.
b.
Go to " Appendix A - LPI Cooling" of the Small Break Operating Guidelines.
2.2 When natural or forced circulation is established as indicated by:
a.
T nd core exit thermocouple (average of 5 highest) becoming subcooled by hot subcooling margin and decreasing.
AND t
b.
Core exit thermocouples temperature decreases when secondary pressure is decreased.
Close all hot leg high point vent valves, RC-4608A, RC-4608B, RC-4610A and RC-4610B.
NOTE:
If natural circulation is not established, the Small Break Operating Guide-lines will direct further actions.
l l !
2.3 Go to Step 3.0 if forced flow is not established and a bubble has forced in the vessel head as indicated by a loss of pressure control, otherwise continue with plant cooldown.
6 I
I i
_3 l
l A
2.0 2.3 OST ACCIDENT REEILL USE OF HOT LEG HIGH POINT VENTS 2.0 y
OPEN All HOT LEG HIGH POINT VENT VALVES, RC-4608A, RC 46088, RC-4610A &
RC-4610 B r
RCS EPRESSURIZES TO YES LESS THAN 150 PSIG v
A.
CLOSE ALL HOT LEG VENT NO
- 2. 2 VALVES RC-4608A,RC-46088,
,F RC-4610A & RC-46108 WHEN NATURAL CIRCULATION. or forced circulation is established, close hot B'
GO TO APPEN0lX "A" 0F SB0G leg vent valves RC-4608A, RC-4608B, RC-4610A.& RC-4610B
- 2. 3 y
BUBBLE EXISTS IN THE RV HEAD AS CONTINUE WITH PLANT DETERMINED BY THE LOSS OF PRESSURE NO CONTROL YES ir GO TO STEP 3.0
Use of High Point Vents to Cooldown the RCS With Steam or Gas in the Reactor Vessel (RV) Head Conditions:
Steam has accumulated in the RV head as indicated by a loss of pressure control (i.e., RC pressure does not decrease significantly despite spraying the pressurizer or opening PORV).
Required Actions to Cooldown:
3.0 Establish subcooling margin on T and T indication with MU or HPI flow.
hot cold 3.1 If pressurizer level indicates off-scale high or unreliable, then go to Step 4.0, otherwise continue.
If in any of the following steps, pressurizer level indicates off-scale high or unreliable, go to Step 4.0.
3.2 Open hot leg high point vents and pressurizer vents, RC-4608A, RC-4608B, RC-4610A, RC-46108, MOV-239A and MOV-200.
3.3 Attempt to restore normal pressurizer level (>100") with MU or HPI flow.
3.4 Throttle HPI flow to depressurize the RCS at a rate to maintain natural circulation flow and subcooling margin.
3.5 If natural circulation stops a.
Close pressurizer vents (MOV-239A and MOV-200).
b.
Stop depressurization.
When natural circulation is regained, open pressurizer vents (MOV-239A, MOV-200),
c.
repeat Step 3.4 and depressurize at a slower rate..
f l
3.0 3.6 COOLDOWN RCS WITH STEAM OR GAS IN l
THE RV HEAD 3.0 y
ESTABLISH-SUBC00 LING MARGl DN T AND T INDICATION H
C WITH HPl FLOW r
3.1 PZR LEVEL INDICATES YES 0FF-SCALE HIGH OR GO TO STEP 4.0 UNRELIABLE N0 3.2 v
OPEN HOT LEG HIGH POINT VENTS.AND PZR VENTS RC-460B A, RC-46088, RC-4610A, RC 46108, MOV-239A &
MOV-700 3.3 y
ATTEMPTTORESTORgRMALPZR LEVEL (>100") WITH API FLOW r
3.4 y
THROTTLE HPI FLOW TO DEPRESSURIZE THE RCS AT A RATE TO MAINTAIN NATURAL CIRCULATION AND SUBC00 LING MARGIN A. CLOSE.MOV-239 A &
l MOV-200
- 8. STOP.0EPRESSURIZATION 3.5 NATURAL C. REGAIN NATURAL YES CIRCULATION OPEN MOV-CIRCULATION y
239A & MOV-200. THEN l
STOPS REPEAT STEP 3.4 AT A DECREASE 0 NO
.Bl=E PR Esn.Y212W ~lo c0 i
FlATE 3
\\
3.6 If subcooling margin cannot be maintained a.
Close pressurizer vents (MOV-239A and MOV-200).
1 b.
Stop the depressurization.
c.
When subcooling margin is re-established, open pressurizer vents (MOV-239A, MOV-200), and repeat Step 3.4.
3.7 Continue depressurization.
When forced circulation is established, using RC pumps or the DER pumps, close MOV-239A, MOV-200, RC-4608A, RC-4608B, RC-4610A and RC-4610B.
The preferable mode of using the DHR pumps is through valves DH11 & DH12. Other alternative is the recirculation from the sump.
3.8 Continue with plant cooldown.
1 i
l 4
i 1.
L 3.6-3.B m
- 3. 6 l
NO SUBC00 LING MARGIN 1r I_
A.
CLOSE PRESSURIZER VENTS YES (MOV 239A AND MOV-200)
[
- 3. 7 Y
B.
STOP THE DEPRESSURIZATION
~
CONTINUE DEPRESSURlZATION.
C.
RE ESTABLISit j
WHEN FORCED CIRCULATION IS ESTABLISHED SUBC00 LING MARGIN THEN OPEN CLOSE MOV-239A. MOV-200, RC-4608A.
MOV-200 AND MOV-239A ANO RC-4608B, RC-4610 A ANO RC-4610B b
REPEAT STEP 3.4 m
(
3.B
,r CONTINUE PLANT C00LOOWN 1
1 Use of High Point Vents to Cooldown the RCS Without Pressurizer Level Indication and With Bubble in RV Head Conditions:
1.
RCS pressure stabilized after the loops have been refilled AND 2.
Pressurizer level indication is not reliable QR 3.
Pressurizer level indication is off-scale high.
Required Actions to Cooldown:
4.0 Open hot leg high point vent valves RC-4608A, RC-4608B, RC-4610A and RC-4610B.
4.1 Throttle HPI/MU flow to depressurize the RCS at a rate to maintain natural circulation flow and subcooling margin.
If at any point natural circulation is lost, open the hot leg high point vents immediately.
4.2 Continue depressurization.
When forced circulation is established, using RC pumps or the DHR pumps, close RC-4608A, RC-4608B, RC-4610A and RC-4610B.
4.3 Continue with plant cooldown.
L
(
4.0-4.3 I]
u--
0
~
COOLDOWN OF THE RC l
WITHOUT PZR LEVEL
~
INDICATION AND WITH BUBBLE IN RV HEA 4.0 v
~
OPEN HOT LEG HIGH POINT VENTS RC-4608 A, RC-46088, RC-4610 A,
h RC-4610B 4.1
,t.idy h~
THE RCS AT A RATE TO MAINTAIN THROTTLE HPl/' FLOW TO DEPRESSURIZE h_-
NATURAL CIRCULATION AND SU8C00 LING M ARGt9 4.2 y
CONTINUE DEPRESSURIZATION.
WHEN FORCED CIRCULATION IS ESTABLISHED CLOSE RC-4608A, RC-46088, RC-4610A AND RC-46108
- 4. 3 y
CONTINUE PLANT C00LOOWN 1
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LO -LOCMED OPEN REACTOR COOLANT SYSTEM HIGH PolNT VENTING FOR DB-l
Docket No. 50-346 Licenza No. NPF-3 Serial No. 804 April 13, 1982 i
Emergency Procedure EP 1202.06 r
Loss of Reactor Coolant and Reactor Coolant Pressure r
i 1
!l 4
1 i
f l
8204190215 820413 l
PDR ADOCK 05000316 P
PDR j
-.