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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G6571999-10-13013 October 1999 Proposed Tech Specs Pages,Revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2 ML20217B1221999-10-0404 October 1999 Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program ML20212F4891999-09-22022 September 1999 Proposed Rev to TS SR 3.8.1.13,to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5511999-08-30030 August 1999 Proposed Tech Specs,Raising Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7281999-08-26026 August 1999 Proposed Tech Specs Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be in IAW with Versions of LCO 3.0.4 & SR 3.0.4 as Noted in Rev 1 to NUREG-1431 ML20211E9111999-08-24024 August 1999 Proposed Tech Specs,Relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3181999-05-18018 May 1999 Proposed Tech Specs SRs 3.8.1.3 & 3.8.1.13 Reducing Loading Requirements for DGs ML20205S3791999-04-19019 April 1999 Proposed Tech Specs Revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS Instrumentation ML20205Q7901999-04-13013 April 1999 Proposed Tech Specs,Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as Appear in Rev 1 to NUREG-1431 ML20154M9961998-10-15015 October 1998 Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete ML20151U2011998-09-0303 September 1998 Proposed Tech Specs Pages for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Source Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236R4661998-07-13013 July 1998 Proposed Tech Specs Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protected Channels ML20154Q8611998-06-30030 June 1998 Proposed Tech Specs Bases Since Implementation of Improved TS on 970123 Through Aug 1998 ML20206N3131998-06-30030 June 1998 Proposed Tech Specs Re Replacement of Nuclear Instrumentation Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236F1631998-06-26026 June 1998 Proposed Tech Specs Revising LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20247K5041998-05-15015 May 1998 Proposed Tech Specs Pages Revising New Program 5.5.18 to Extent That Items B,C & D. Refer to LCO Action Statement & Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9471998-05-0808 May 1998 Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years ML20216J4971998-04-16016 April 1998 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & ESFAS Instrumentation ML20199E5351998-01-27027 January 1998 Complete Replacement of All Typed Pages of TS Changes Submitted in Ltr LCV-0849-E ML20199A4131998-01-22022 January 1998 Proposed Tech Specs Adding Conditions for DG for Extended DG Completion Time of Fourteen Days ML20198P6961998-01-16016 January 1998 Revised Spent Fuel Pool Boron Dilution Analysis ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20199G3901997-11-20020 November 1997 Proposed Tech Specs Facilitating Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20199J6651997-11-20020 November 1997 Proposed Tech Specs Pages Changing Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Revising Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20211N2451997-10-10010 October 1997 Proposed Typed Tech Specs Pages,Revising Credit for Boron & Enrichment Increase for Fuel Storage ML20217H9051997-08-0808 August 1997 Proposed Tech Specs Pages Re Credit for Boron & Enrichment Increase for Fuel storage.W/marked-up Pages ML20141A8541997-06-13013 June 1997 Proposed Tech Specs Revising LCO 3.4.10 to Reduce Nominal Set Pressure by 1% to 2460 & Increase Tolerance to +2% ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20133L3081997-01-10010 January 1997 Proposed Tech Specs Table 3.3.1-1 Re Amends 96 & 74 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20132C4711996-12-12012 December 1996 Proposed Tech Specs Re Physical Security & Contingency Plan ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20117N5851996-09-13013 September 1996 Proposed Tech Specs 3.8.1 Re AC Electrical Sources ML20129A6461996-09-11011 September 1996 Proposed Tech Specs,Providing Updated Documentation for License Amends Application for Southern Nuclear to Become Licensed Operator ML20117C4151996-08-23023 August 1996 Proposed Tech Specs to Convert Units 1 & 2 Based on NUREG 1431 ML20117N6361996-06-17017 June 1996 Proposed Tech Specs,Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20117N6471996-06-17017 June 1996 Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20111A5501996-05-0606 May 1996 Proposed Tech Specs,Incorporating Extended DG AOT to 14 Days from Discovery of Failure to Meet Lco,Provided Standby Auxiliary Transformer Available ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20101D4151996-03-0505 March 1996 Proposed Tech Specs Re Conversion Based on NUREG-1431 ML20100G0371996-02-19019 February 1996 Proposed Tech Specs Based on NUREG-1431 ML20097A3171996-01-30030 January 1996 Proposed Improved TS Based on NUREG-1431 ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20095J2501995-12-22022 December 1995 Proposed Tech Specs,Allowing Use of Option B of 10CFR50,App J for Type B & C Testing ML20094N4071995-11-20020 November 1995 Proposed Tech Specs,Converting Existing TS to Format & Content of NUREG-1431 ML20093K2281995-10-16016 October 1995 Proposed Tech Specs,Adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J & Using Guidance of RG 1.163,Rev 0 ML20098C1471995-10-0202 October 1995 Proposed Tech Specs,Allowing Next Type a Test to Be Rescheduled 1999-09-22
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20078A3771994-05-12012 May 1994 Vols 1 & 2 of Vogtle Electric Generating Plant Unit 1 Readiness Review Module 4 Mechanical Equipment & Piping Program ML20069L8311994-03-30030 March 1994 Rev 5 to ISI-P-016, Inservice Test Program for Vogtle Electric Generating Plant Unit 2 ML20069L8241994-03-30030 March 1994 Rev 8 to ISI-P-008, Inservice Test Program for Vogtle Electric Generating Plant Unit 1 ML20082V2871994-01-0101 January 1994 Offsite Dose Calculation Manual, Rev 9 ML20064C7471993-11-0505 November 1993 Rev 6 to ISI-P-014, ISI Program for Vogtle Electric Generating Plant Unit 2 ML20064C7431993-11-0505 November 1993 Rev 6 to ISI-P-006, ISI Program for Vogtle Electric Generating Plant Unit 1 ML20035F5601993-04-0505 April 1993 Rev 5 to Inservice Insp Plan (ISI-P-014) for Vogtle Electric Generating Plant,Unit 2 ML20035F0721993-03-22022 March 1993 Rev 7 to Inservice Test Program (ISI-P-008) for Vogtle Electric Generating Plant,Unit 1 ML20094K1781992-03-0404 March 1992 Rev 3 to Vogtle Electric Generating Plant Process Control Program ML20092G7441992-02-20020 February 1992 Undated Draft Site Safety Manual. Supporting Documentation Encl ML20094K1721991-12-31031 December 1991 Draft, ODCM for Vogtle Electric Generating Plant ML20086Q7231991-12-0404 December 1991 Rev 7 to Procedure 91202-C, Activation & Operation of Operations Support Ctr ML20129J2961991-09-13013 September 1991 Rev 3 to Procedure 23985-1, RCS Temporary Water Level Sys ML20091L7891991-07-0303 July 1991 Rev 5 to Procedure 29537-C, Outage Scheduling ML20079G4971991-06-10010 June 1991 Rev 5 to ISI-P-006, Inservice Insp Program for Vogtle Unit 1 ML20079G5071991-06-10010 June 1991 Rev 4 to ISI-P-014, Inservice Insp Program for Vogtle Unit 2 ML20091L7991991-04-22022 April 1991 Rev 6 to Training Lesson Plan LO-LP-39201-06-C, Introduction to Ts ML20091L7771991-04-17017 April 1991 Rev 21 to Procedure 10000-C, Conduct of Operations ML20129H6151991-03-20020 March 1991 Rev 7 to Procedure 10004-C, Shift Relief. Supporting Documentation Encl ML20129J0311990-09-18018 September 1990 Rev 4 to Procedure PTDB-1 Tab 8.0, Pictorial Aids. Supporting Documentation Encl ML20043H3091990-06-15015 June 1990 Rev 3 to ISI-P-014, Inservice Insp Program ML20043B6321990-05-22022 May 1990 Rev 5 to ISI-P-008, Inservice Testing Program ML20043B6381990-05-22022 May 1990 Rev 2 to ISI-P-016, Inservice Testing Program ML20091L8131990-05-22022 May 1990 Outdated Rev 0 to Training Lesson Plan RQ-LP-63107-00, Requal Current Events ML20113G6141990-05-15015 May 1990 Rev 0 to VEGP-22981-C, Calcon Pneumatic Temp Sensor Calibr 1TSH-19110-1TSH-19119,1TSH-19146,1TSH-19153,2TSH-19110- 2TSH-19119,2TSH-19146 & 2TSH-19153. Supporting Documentation Encl ML20034C1061990-04-26026 April 1990 Rev 4 to Inservice Insp Program First 10-Yr Interval ML20129H9081990-04-16016 April 1990 Rev 3 to Procedure PTDB-1 Tab 8.0, Pictorial Aids. Supporting Documentation Encl ML20129G8451990-04-0505 April 1990 Rev 19 to Procedure 14980-1, Diesel Generator Operability Test ML20113G3421990-04-0404 April 1990 Procedure T-ENG-90-016, DG1A J.W. Temp Monitoring & Recording ML20129F7161990-03-29029 March 1990 Rev 2 to Procedure T-FND-90-15, Method Visual ML20092F9691990-03-28028 March 1990 Rev 0 to T-ENG-90-15, Unit One Train a DCP 88-V1N0070 Sequencer Functional Test. Supporting Documentation Encl ML20092F8621990-03-28028 March 1990 Rev 1 to Procedure T-ENG-90-11, A-Train Undervoltage Test ML20092F7521990-03-27027 March 1990 Rev 20 to 13145-1, Diesel Generators ML20092F8741990-03-26026 March 1990 Rev 3 to Procedure VEGP 00053-C, B-Train Undervoltage Test ML20092F8481990-03-25025 March 1990 Rev 2 to Generator & Engine Control Panel Functional Test Procedure 27563-C, Power & Signal Removal/Replacement Data Sheet ML20092H0391990-03-23023 March 1990 Rev 16 to VEGP-10000-C, Conduct of Operations ML20092F5271990-03-21021 March 1990 Data Sheet 1 to Rev 12 to VEGP-10006-C, Reactor Trip Rept. Supporting Documentation Encl ML20092F7341990-03-19019 March 1990 Rev 16 to Procedure 25717-C, Torquing Electrical Type Connections ML20092G9111990-03-16016 March 1990 Abnormal Operating Procedure to Rev 7 to VEGP-18028-C, Loss of Instrument Air ML20092F6901990-03-16016 March 1990 Rev 7 to Procedure 18019-C, Abnormal Operating Procedure, Loss of Rhr ML20092F6361990-03-12012 March 1990 Temporary Change Notice to Rev 14 to Procedure 12007-C, Refueling Entry 1998-05-25
[Table view] |
Text
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VOGTLE ELECTRIC GENERATING PLANT g
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TRAINING LESSON PLAN i,
TITLE.
EMERGENCY CORE COOLING SYSTEFI3/4.S' NUMBER:
'L -LP-39209-00 PROGRAM:
LICENSED OPERATOR TRAINING REVISION:
0 AUTHOR:
C. STUHAAN DATE:
8/7/86 i
n n
f/hg APPROVED:
[ M 'p DATE:
INSTRUCTORGUIDELINES8 1.
WHITE BOARD W1TH MARKERS 2.
OVERHEAD PROJECTOR 3.
TRANSPARENCY:
a.
LO-TP-39209-001 PURPOSE STATEMENT AND LIST OF 03JECTIVES.
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LO-LP-39209-00 l.
PURPOSE STATEMENT:
TO TEACH THE STUDENT THE APPLICABILITY AND ACTIONS OF LIMITING CONDITION FOR OPERATION SECTION 3/4.5, EMERGENCY CORE COOLING SYSTEMS.
II.
LIST OF OBJECTIVES:
1.
The student will be able to determine if in violation of an LCO if given a list of equipment and a given applicability condition.
2.
The student will be able to give the required action statement from memory if the time limit for action is one hour or less.
3.
The student will be able to look up the required action if given the applicable LCO if action required in more than one hour.
Additional for SRO 4.
The student will be able to explain the bases for each of the LCO's.
2
' ~' '~
REFERENCES:
TECHNICAL SPECIFICATIONS SECTION 3/4.5 EMERGENCY CORE C00L1FG SYSTEMS f
i e
i i
3
r LO-LP-39209-00 ll1.
LESSON OUTLINE:
NOTES A.
Accumulators 1.
T/S 3/4.5.1 - Accumulators LO-TP-39209-00-001 Obj ectives a.
Each accumulator shall be OPERABLE with:
Verified by Proc.
(OPS SURV) 1)
The isolation valve open 14000-C - Shiftly 142' 3-C - Monthly i
2)
Volume between 36.1% and 63.9%
14465-C - MOV Verif.
3)
Boron concentration between 1900 ppm and 2100 ppm a)
Chemistry check CB*"
I b)
Volume increases (
1% tank volume.)
4)
N C Ver Pressure - 564 psig and 637 psig 2
b.
Applicable in Modes 1, 2, and 3*
- Pzr Press, above 1000 psig c.
Action:
1)
Accumulator inoperable.(not due to closed isolation valve), restore operable in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or a)
Hot Standby in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> b)
Reduce Pzr Press 100 psig d.
Bases 1)
Ensures sufficient volume of borated water l
a)
Immediately forced into core through cold legs b)
If RCS pressure drops below accumu-l lators 2)
Provides initial cooling during large LOCA 3)
Limits on Pressure, Volume and Boron Concen-tration a)
Assumptions in analysis are met l
4 i
c-LO-LP-39209-00 lil.
LESSON OUTLINE:
NOTES 4)
Isolation valves are considered " Operating Bypasses" a)
Required to be removed when permis-i sive conditions not met b)
They also fail to meet single failure criteria c)
Power must be removed from valves.
5)
Limits for operation other than isolation valve closed a)
Minimize time exposure to LOCA b)
Concurrent with another accumulator failure (1) Could result in unacceptable PCT's 6)
Inoperable accumulator because closed iso-lation valve
~
a)
Full capability of one accumulator not available b)
Prompt action is required B.
ECCS Subsystems - Tavs ___ 350*F Verified operable via many surveil-1.
T/S 3/4.5-2 lances OPS / CHEM /
ENG. etc.
a.
Two ECCS subsystems shall be operable. Each comprised of:
1)
CCP 2)
SI Pump 3)
RHR Heat Exchanger 4)
RHR Pump 5)
Operable flowpath from RWST on SI signal and semi-auto transfer to CTB oump during recire phase b.
Applicable in Modes 1, 2, and 3 Exception to SI pump for T/S 3.5.3.2 5
P.
LO-LP-39209-00 111.
LESSON OUTLINE:
NOTES c.
Action 1)
With i ECCS subsystem inop. restore operable in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or Hot standby in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Hot shutdown in following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 2)
If SI actuated a special report requires in 90 days d.
Bases - Two subsystems above 350*F 1)
Sufficient core cooling for LOCA a)
Assuming loss of one subsystem 2)
Operating with accumulators a)
Limits PCT to within acceptable (2200*F) b)
For all, break sizes c)
Provides long term cooling C.
ECCS Subsystems - Tavg 350*F 1.
T/S 3/4.5.3.1 a.
ECCS subsystem operable required 1)
CCP 2)
RHR Heat Exchanger 3)
RHR Pump and 4)
Operable flowpath from RWST that can be manually realigned to take suction from CTB emer sump during recire phase.
b.
Applicable in Mode 4.
c.
Action 1)
No ECCS subsystem operable due to CCP inoperable or flowpath from RWST unavailable.
a)
Restore 1 ECCS subsystem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or cold shutdown in next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> 6
F'..
1 LO-LP-39209-00 ll1.
LESSON OUTLINE:
NOTES 2)
ECCS train inoperable due to RHR Heat Exchanger or RHR pump 00S.
a)
Restore operable or maintain RCS Tavg 350*F via alternate heat removal methods.
3)
If SI actuated prepare special report to the commission within 90 days d.
Bases - One ECCS subsystem below 350*F 1)
Do not require single failure consider-ation a)
Stable reactivity condition of core b)
Limited core cooling requirements 2)
Limits on maximum of one CCP and SIP less than 350*F a)
Mass addition transient relieved by one PORV 3)
Surveillance requirements on components These bases apply to 3.5.2 and 3.5.3 a)
Ensure that assumption in analysis are met (1) And subsystem operability maintained 4)
Surveillances on throttle position stops and flow balancing a)
Ensure proper ECCS flows for LOCA b)
Maintenance of proper flow resistance and pressure drops necessary to:
(1) Prevent runout conditions (2) Provide same flev eplit :: in analysis (3) Maintain flow above that in analysis (4) Assure seal injection flow less than assumed in analysis 7
LO-LP-39209-00 111.
LESSON OUTLINE:
NOTES D.
ECCS - Tavg 350'F - Safety Injection Pumps 1.
T/S 3/4.5.3.2 - Safety Injection Pumps a.
All SI pumps shall be inoperable b.
Applicable in Modes 4, 5, and 6 with Rx vessel head on c.
Action 1)
With a SI pump operable, make all SI pumps INOP in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> d.
Bases 1)
Ensure mass addition pressure transient T
below 350*F
"#8 can be relieved by a single PORV.
E.
Refueling Water Storage Tank 1.
T/S 3/4.5.4 a.
RWST will be oper,able with 1)
Volume of 631, 478 minimum 2)
Boron concentration between 2000 ppm and 2100 ppm 3)
Minimum temp - 50*F and 4)
Max temp 120*F l
5)
RWST SLUDGE mixing valves capable or closing on low-low RWST level l
b.
Applicable in Modes 1, 2, 3 and 4 c.
Action:
l l
1)
With RWST INOP (Exclude sludge valves)
{
restore operable in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or hot standby in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown in following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l l
2)
With sludge mixing valves inop. restore within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or isolate system with manual valves or deenergize solenoid pilot valve.
l l
LO-LP-39209-00 111.
LESSON OUTLINE:
NOTES d.
Bases 1)
Ensures sufficient negative reactivity inserted into core a)
To counteract positive insertion from
Cooldown can be caused by:
(1) Inadvertent depressurization (2) LOCA (3) Steam Line rupture 2)
In the event of LOCA a)
Limits on volume and boron con-centration (1) Sufficient water for recirculation (2) Remain suberitical cold after mixing with RCS volumes. All rods in but one 3)
Takes into account unusable volume 4)
Limits on volume and boron concentration a)
Ensure pH value between 8.5 and 10.5 (1) Minimizes evolution of iodine (2) Minimizes effect of chloride or caustic stress corrosion E.
Summary 1.
Accumulators 2.
ECC'S Subsystems - Tave ___350*F 3.
ECCS Subsystems - Tave 350*F a.
Safety Injection Pumps 4.
RWST 9
Fr.
LO-LP-39209-00 lli.
LESSON OUTLINE:
NOTES F.
Exercises 1.
Case 1 - Plant is operating at 100% power 1153 MW load - Tavg - 588'F.
Crew a is conducting routin$
surveillance required during their shif t.
Chemistry reports results of accumulator liquid boron samples for the monthly surveillance.
The results are as follows:
Accumulator #1 1957 ppm Accumulator #2 1890 ppm Accumulator #3 1940 ppm Accumulator #4 1950 ppm Are these concentrations alright to operate with?
Is a Tech Spec affected and if so what action is required.
Answer:
1.
No.
All samples ' appear very low with accumulator #2 low out of spec.
2.
Tech Spec 3.5.1 is affected. If boron con-centration can't be recovered in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a shutdown and plant pressure reduction is called for.
2.
Case 2 - Plant is starting up following a refueling is in Mode 4 going to Mode 3.
During the SS/STA review of clearance and tagging logs it is noticed that SI pump 'A' is stilled tagged out to perform a routine oil change pm.
Can the osos authorize the mode change from Mode 4 to Mode 3? What Tech Spec (s) are affected?
Answer:
1.
Yes. A mode change can be made safety injection pumps can be inoperable going into Mode 3 but not with temp exceeding 375'F.
2.
T/S affected 3.5.2 (See Note asterisk for Mode 3, bottom or page 3/4 5-3) this is working in conjunction with T.S. 3.5.3.2 10
LO-LP-39209-00 ill.
LESSON OUTLINE:
NOTES Note Pumps must be restored within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of Mode 3 entry or prior to Tave exceeding 375'F, whichever occurs first.
e 9
I l
11