Letter Sequence Other |
---|
|
Results
Other: ML20141N147, ML20141N150, ML20141N153, ML20141N156, ML20141N160, ML20141N163, ML20141N168, ML20141N172, ML20141N176, ML20141N179, ML20141N180
|
MONTHYEARML20141N1721980-01-31031 January 1980 Rev 0 to Procedure RES-OPS-006.00, Operator Training: Draeger Gas Analyzer Use,Function & Applicable Procedure Review. Marked-up AB 1203.14.3 & Ch 4025.01.0 Encl Project stage: Other ML20141N1801985-12-31031 December 1985 Rev 0 to Procedure GOP-OLC-001.00, Operator Licensed Candidate Abnormal Operating Procedures,Loss of Nni Power AB 1203.41 Project stage: Other ML20141N1791985-12-31031 December 1985 Rev 0 to Procedure GOP-OLC-001.00, Operator License Candidate:Abnormal Operating Procedures,Loss of Ac Bus Power Sources AB 1203.28 Project stage: Other ML20141N1631985-12-31031 December 1985 Rev 1 to Procedure GOP-OLC-001.01, Operator Licensed Candidate:Procedures Normal,Abnormal & Emergency,Loss of Instrument Air Project stage: Other ML20141N1601985-12-31031 December 1985 Rev 0 to Procedure RES-OPS-007.00, Operator Training: Infrequent Operations Project stage: Other ML20141N1471985-12-31031 December 1985 Rev 0 to Procedure RES-OP-002,0 Operator Training:Rapid Feedwater Reduction Project stage: Other ML20141N1761986-01-31031 January 1986 Rev 0 to Procedure GOP-OLC-001.00, Operator License Candidate:Abnormal Operating Procedures,Serious Control Room Fire AB-1203.26 Project stage: Other ML20141N1681986-01-31031 January 1986 Rev 0 to Procedure RES-OPS-008.00, Operator Training: Starting of Primary H2O Storage Tank Transfer Pumps Project stage: Other ML20141N1561986-02-26026 February 1986 Procedure Fcr 85-200, Main Feedwater Pumps Rapid Feedwater Reduction Speed Setpoint Project stage: Other ML20141N1531986-02-26026 February 1986 Procedure Fcr 85-201, Steam Generator Level Setpoint Project stage: Other ML20141N1501986-02-26026 February 1986 Procedure Fcr 85-227, Main Feedwater Block Valve Interlock Project stage: Other ML20141N1441986-02-26026 February 1986 Forwards Training Matls in Response to 851030 Request for Addl Info Re Course of Action & Draft SER (NUREG-1177).Matl Meets Commitment Made in Rev 4 of Course of Action Project stage: Draft Request ML20212G6021986-08-0404 August 1986 Safety Evaluation Accepting Util Response to NRC Request for Addl Info Re Question 29 Concerning Training for Infrequent, Critical & Difficult Tasks Project stage: Approval ML20212G5341986-08-0404 August 1986 Forwards SER W/Recommendations Re Util 851116 Response & 860226 Submittal in Response to NRC 851029 Request for Addl Info on Question 29 Concerning Training for Infrequent, Critical & Difficult Tasks Project stage: Approval 1986-01-31
[Table View] |
|
---|
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 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 ML20213A0311987-03-31031 March 1987 Rev 2 to Vol IV of Procedure Writers Manual:Operation Procedures Guidelines ML20213A0361987-03-31031 March 1987 Rev 1 to Davis Besse Emergency Procedure Verification & Validation Program 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 ML20141N1531986-02-26026 February 1986 Procedure Fcr 85-201, Steam Generator Level Setpoint 1998-08-28
[Table view] |
Text
. .- _ - - - __ ._. -. _ ._ .-. .
[ Sericl No. 1242 Attcchmelt 2 LESSON PLAN REVISION /REVliW HISTORY l eo nsi r
LESSON PLAN t LESSON PLAN Nuvee 4 P1O [6EhWa T!r2 'D* O u e n e
??s - C/S-ce2.0 o '
acy;=l,o; ou. .. ,,c~Aro., !
oo fn1 6 M r A O W E' ls/ d
_Ild' ,A_ls 7
b
._ +
l L
I 4
t
\
! ! }
i
~
l I j i t
I l [
i .
l i
[
l :
t i'
t G603040415 860226 -
PDR ADOCK 05000346 V PDR
~_____-________-_-_--______-_-_-___________
RES-OPS-002.00 Program Title OPERATOR TitAINING Course
Title:
1985-1986 Restart Training Les_sen
Title:
" RAPID FEEDWATER REDUCTION Accrox. Times 1 Revision No.: 00 Date: 8512 Resource Materials for the Instructor Jon Aids:
N/A Audio / Visual Equipment Needed:
CVETHEAD PROJECTOR List of Transparancies:
RES-OPS-00 2.1 THRU RE5-OPS-002.4 Tools / Equipment:
N/A Safety Requirements:
N/A Instructional setting:
CLASSROOM Student Materials:
PEN OR PENCIL, PAPER, HANDOUTS Special Considerations:
N/A Instructor
References:
SP 1105.05, USAR - SECTION 7.7, INSTAUCTIONS BOOK FOR INTEGRATED CONTROL SYSTEM, TOLEDO EDISON DRAWING 8 26206-26228, TCR-200 REV. A Student
References:
SP 1105.04, USAR - SECTION 7.7
OBJECTIVES RES-OPS-002.00 O BJ ECTIVE . O NECTIVE TEXT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
NUMBER 0 OPERATE AND MONITOR THE RAPID FEEDWATER REDUCTION PORTION OF THE INTEGRATED CONTROL SYSTEM.
00 THE FOLI4 WING ENABLING OMECTIVES ASSOCIATED WITH THIS 'JSSON PLAN ARE DESIGNED TO SUPPORT THE
" KNOWLEDGE" REQUIREMENTS FOR THE ABOVE TERMINAL OMECTIVE.
000 THE STUDENT, WITHOUT REFERENCES UNLESS OTHERWISE SPECIFIED), ACCORDING TO APPROVED PROCEDURES, WILL BE ABLE TO:
- 01 STATE THE PURPOSE OF RAPID FEEDWATER REDUCTION.
02 IDENTIFY THE CONDITIONS THAT NOULD RESULT IN A RAPID FEEDWATER REDUCTION ACTUATION.
03 DESCRIBE THE FEEDWATER RESPONSE DURING A RAPID FEEDWATER REDUCTION ACTUATION. '
t 04 DESCRIBE HOW A RAPID FEEDWATER REDUCTION ACTUATION IS TERMINATED.
4 l
)
i l
l
RAPID FEEDWATER REDUCTION RES-OPS-002.00
1.0 INTRODUCTION
A. The' Rapid Feedwater Reduction portion of the Integrated Control System is responsible for ensuring proper feedwater response during a reactor trip from power.
2.0 PRESENTATION The Rapid Feedwater Reduction (RFR) controls the A.
speed of the Main Feedwater Pumps and the position of the Main and Starteup Feedwater Control Valves following a reactor trip from power, to ensure proper Feedwater response.
B. Description
- 1. Conditions necessary to initiate a rapid i
feedwater reduction i
- a. At least one MFP not tripped 4
- b. All control valves in auto j c. RFR defeat switch in "on" position j d. Reactor Trip '
i 2. Initiation Circuitry
, TP 2
- a. When il or #2 MFP are reset then either contasct 86-1/AFWPT or 86-1/BFWPT will be closed.
)
- b. When the RFR defeat switch is on then switch RFR/DEF will be closed.
! c. When all four (4) Feedwater control 1
valves are in auto then contacts i
62X/AFWN, 62X/AFWS, 62X/5FWS, and i
s 62X/BFWN are closed.
- d. A reactor trip then closes contacts l 86/RT and 86-1/RT.
j e. When the above contacts are closed the 4
) -
1-1 1
[
1 i
RAPID FEEDWATER REDUCTION RES-OPS-002.00 following relays are energized 86/RFR, t
86/R?R-1, 86/RFR-2, and 86/RFR-3. '
)
4
- f. When 86/RFR-2 is energized it closes 4
contact 86/RFR-2 which seals in the actuation signal even if the valves are j then taken out of auto.
- 3. Main and GU control valve actuating circuitry TP 3
- a. When 86/RFR is energized it closes 2
contact 86/RFR
) b. As'long as no OTSG low level exists and
<2.5 minutes have elapsed since the i trip, relays 86/0LCA, 86/otcA-1, 86/0LCB, and OLCB-1 will be energized
- 1) This causes contacts to position such that the transfer devices T15 and T14 select a target position l for their input i i l 2)~ This provides a closed signal to the TP 4 i
main control valves and about a 17%
i open signal to the startup control;
) valves.
- 4. Main Feed pump actuating circuitry l
l a. When 86/RFR and 86/RFR-2 are energiz6d it TP 4 i
causes contacts to position such that l the transfer device T-11 is selected to j a target speed of about 4600 RPM.
l l' b. It also selects a zero modifying signal l
! instead of valve D/P as long as no low
)
3 level limit exists. .
j 5. Low Level Control Circuitry j a. Once low level limits are reached the i
27RR/LLA and 27RR/LLB contacts change -
l position. TP 3
}
i
- 1) This deanergises relays 86/oLCA, 86/oLCA-1, 86/OLCB, and 86/0LCB-1 I,
2-I i
i
}
, --.,.. - _ - ~. ,. , - - , . , , - . - - , - , - _ -.--,,,,,-,,_,n-
RAPID FEEDWATER REDUCTION RES-OPS-002.00 which causes transfer devices T14 l and T15 to transfer back to the feedwater demand signal which is on level control
- 2) This also energizes relays 86/ALCP, and 86/BLCP which cause T13 to select level control instead of a zero error signal. TP 4 a) This results in feedpumps being targeted at - 4600 rpm and then that signal being modified by level control
- error
- 6. 2.5 minute time control circuit
- a. If no low level has occurred before 2.5 minutes has elapsed then Relay 62/LLTB i will open the 62'LLIa f 111 we... tr.e 1
i contacts doenergizing relays 86/0LCA, 86/OLCB, and 86/OLCB-1 TP 3
- 1) This causes transfer device T14 and i
T15 to transfer back to the feedwater TP 4 demand signal.
- 2) This results in the valves being once again controlled by feedwater
.; demand.
- 3) This time delay has no effect on i the main feedwater pumps.
- 7. Signal Lag Modules j a. Main Feed Pumps
! 1) A signal lag module set at a time constant of - 18 seconds exists in the RFR feed pump circuit.
- 2) When RFR is actuated instead of a step TP 4 change in MFPT speed to its target position the time lag module filters the signal to provide a 3-1 l
- - - - - - - - - - ------- .-,- ,,,n-
1 RAPID FEEDWATER REDUCTION RES-OPS-002.00 speed change in a smooth controlled fashion.
- b. FW Control Valves
- 1) A signal lag module set at a time constant of - 4.5 seconds exists in the RFR control valve circuit.
- 32) When RFR is actuated the Main and TP 4 Startup control vslves change position in a smooth, controlled
' fashion from their pretrip position to their post-trip, target position.
3.0
SUMMARY
A. Proper actuation of RFR is indicated by both main FW valves going shut and both startup FW valves closing to about 174. The MFP's will target their speed to - 4600 rpm.
B. RFR will remain activated for - 2.5 minutes or until low level limits have been reached, which ever occurs first.
- 1. If low level limits have been reached on one (1) loep and not,the other while RFR is still activated, the loop / reaching low level limits will go on level control and the other will remain on RFR until low level limits have been obtained or 2.5 minutes have expired at t
which time it will go on level control.
4.O EVALUATION '
5.0 ASSIGNMENT A. None required for this lesson.
4-1 YV
- . ., .-- __ .... . .- - . .-_.-,.-