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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 ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump 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 ML20069L8241994-03-30030 March 1994 Rev 8 to ISI-P-008, Inservice Test Program for Vogtle Electric Generating Plant Unit 1 ML20069L8311994-03-30030 March 1994 Rev 5 to ISI-P-016, Inservice Test Program for Vogtle Electric Generating Plant Unit 2 ML20082V2871994-01-0101 January 1994 Offsite Dose Calculation Manual, Rev 9 ML20064C7431993-11-0505 November 1993 Rev 6 to ISI-P-006, ISI Program for Vogtle Electric Generating Plant Unit 1 ML20064C7471993-11-0505 November 1993 Rev 6 to ISI-P-014, ISI Program for Vogtle Electric Generating Plant Unit 2 ML20094K1781992-03-0404 March 1992 Rev 3 to Vogtle Electric Generating Plant Process Control Program 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 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 ML20043H3091990-06-15015 June 1990 Rev 3 to ISI-P-014, Inservice Insp Program. ML20091L8131990-05-22022 May 1990 Outdated Rev 0 to Training Lesson Plan RQ-LP-63107-00, Requal Current Events 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. ML20129G8451990-04-0505 April 1990 Rev 19 to Procedure 14980-1, Diesel Generator Operability Test ML20129F7161990-03-29029 March 1990 Rev 2 to Procedure T-FND-90-15, Method Visual ML20091L8331989-05-19019 May 1989 Rev 0 to Corporate Guidelines 1.1.2, Positive Discipline ML20246N6241989-05-10010 May 1989 Rev 3 to Vogtle Electric Generating Plant Unit 1 Inservice Insp Program ML20078A5401988-11-15015 November 1988 Updated Vogtle Electric Generating Plant Unit 2 Readiness Review Module 3A Initial Test Program - Preoperational Test Phase ML20195J9191988-11-11011 November 1988 Rev 4 to ISI-P-010, Preservice Insp Program Vogtle Electric Generating Plant Unit 2 ML20196B1551988-10-25025 October 1988 Rev 0 to ISI-P-014, Inservice Insp Program ML20195B3901988-10-18018 October 1988 Aw Vogtle Simulator Certification Plan ML20091L8931988-10-0303 October 1988 Voided Rev 9 to Procedure 10000-C, Conduct of Operations ML20155C0751988-09-15015 September 1988 Rev 0 to Abnormal Operating Procedures 18038-2, Operation from Remote Shutdown Panels ML20091L8821988-09-0808 September 1988 Voided Rev 10 to Procedure 35110-C, Chemistry Control of Rcs ML20155C0871988-08-19019 August 1988 Rev 9 to Procedure 12006-C, Unit Cooldown to Cold Shutdown ML20151G1851988-07-18018 July 1988 Rev 1 to ISI-P-006, Inservice Insp Program ML20151G1881988-07-18018 July 1988 Rev 2 to ISI-P-006, Inservice Insp Program ML20078A6221988-07-12012 July 1988 Readiness Review Program Module 20 - Instrumentation & Controls ML20078A5931988-06-28028 June 1988 Readiness Review Program Module 13B - Coatings ML20078A5831988-06-22022 June 1988 Readiness Review Program Module 12 - Electrical Cables & Terminations ML20091L7821988-06-0707 June 1988 Rev 0 to Procedure 49006-C, Health Physics & Chemistry Dept Outage Activities Implementing Procedure ML20078A5461988-05-12012 May 1988 Rev 1 to Vogtle Electric Generating Plant Unit 2 Readiness Review Module 3A Initial Test Program - Preoperational Test Phase ML20078A5751988-04-13013 April 1988 Readiness Review Program Module 11 - Pipe Stress & Supports ML20151R0331988-04-13013 April 1988 Rev 3 to Inservice Test Program ISI-P-008, Summary of Changes ML20078A6311988-03-16016 March 1988 App F, Inspector Qualification of Vogtle Electric Generating Plant Unit 2 Readiness Review Program ML20148K4301988-03-0202 March 1988 Inservice Test Program 1998-05-25
[Table view] |
Text
e if Georgia Power
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. i TRAINING LESSON PLAN i, ,
TITLE. EMERGENCY CORE COOLING SYSTEFI3/4.S' NUMBER: 'L -LP-39209-00 PROGRAM: LICENSED OPERATOR TRAINING 0 REVISION:
AUTHOR: C. STUHAAN 8/7/86 i n n DATE:
APPROVED: [ M 'p DATE: f/hg 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 PURPOSE STATEMENT:
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. 1 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
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REFERENCES:
TECHNICAL SPECIFICATIONS SECTION 3/4.5 EMERGENCY CORE C00L1FG SYSTEMS f
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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'i 3-C - Monthly
- 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
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LO-LP-39209-00 l
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
1 F' ..
LO-LP-39209-00 LESSON OUTLINE:
ll1. 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 can be relieved by a single PORV. "#8 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
b) 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.
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