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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
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VOGTLE ELECTRIC GENERATING PLANT 3 5 .* % **~~ .s TRAINING LESSON PLA$. % % 4 j ';..
TITLE: REFUELING OPERATIONS NUMBE6 'LO-LP-39213-00 PROGRAM: LICENSED OPERATOR TRAINING 0 REVISION:
AUTHOR: R. SLOUGH DATE: 8/1/86 APPROVED: Q4N j s DATE: g/g7pg INSTRUCTOR GUIDELINES:
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- l. PURPOSE STATEMENT:
TO TEACH THE STUDENT THE APPLICABILITY AND ACTIONS OF LIMITING CONDITION FOR OPERATION SECTION 3/4.9, REFUELING OPERATIONS.
- 11. 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 actions required in more than one hour.
- 4. The student should be able to paraphase the LCO's associated with refueling operations. .
Required for SRO only.
~ '
- 5. The student will be able to explain the bases for each of the LCO's.
I l
2
REFERENCES:
i I
TECHNICAL SPECIFICATIONS l
SECTION 3/4.9 REFUELING OPERATIONS l
l l
l l
3 l __. _-_____. _ ..
LO-LP-39213-00 ll1. LESSON OUTLINE: NOTES A. Boron Concentration T.S. 3/4.9.1
- 1. C, in RCS and refueling canal uniform and sufficient t5 ensure more restrictive of:
- a. k,gg _ .95, or
- b. _ 2000 ppe.
- 2. Applicable in Mode 6
- 3. Actions Immediate actions
- a. Suspend CORE ALTERATIONS and positive reactivi*.y changes
- b. Borate at _ 30 sps with _ 7000 ppe boron until LCO restored
- 4. Bases
- a. Ensures that 1)
Reactor remains suberitical during core alterations
- 2) Uniform boron in water with direct access to fuel
- b. Consistent with assumptions in accident analyses
- 1) Boron dilution incident .
l
- 2) Includes 1% delta K/K conservative analyses
- 3) Includes 50 ppe conservative analyses R.. Instrumsstation >
T.S. 3/4.9.2 i
- 1. Ttso,SE asaitors OPERABLE with visual indication in Control Boom and one with audible indication in Containment and Control Room.
- 2. Applicable in Mode 6.
l 3. If one inoperable, suspend core ALTERATIONS and Immediate action
! positive reactivity changes. If both inoperable.
l determine RCS 3C avery 12 h ars.
4 l _ - _ _ _ _ , - . . . _ - .
LO-LP-39213-00 Ill. LESSON OUTLINE: NOTES
- 4. Bases
- a. Ensures redundant monitoring capability
- 1) Detect changes in reactivity of core C. Decay Time T.S. 3/4.9.3
- 1. Reactor suberitical at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.
- 2. Applicable during movement of irradiated fuel within vessel.
- 3. Actions is to stop moving fuel. Issaediate action
- 4. Bases
- a. Ensures adequate decay time for short lived fission products
- 1) Consistent with accident analyses D. Containment Building Penetrations T.S. 3/4.9.4.
- 1. All penetrations must bs as follows:
- a. Equipment hatch closed, held by at least 4 bolts.
- b. At least I door in each airlock closed.
- c. All others providing direct access must be:
- 1) Closed by isolation valve, manual valve, ,
blind flange, or
- 2) Capeble of being closed by OPERABLE automatic containment ventilation isolation valve.
- 2. Applicable during CORE ALTERATIONS or movement of irradiated fuel within containment.
- 3. Action is to stop CORE ALTERATIONS, movement Immediate action of fuel withis containment.
5
- . , - , - , , . , , _ _ - , . , . , ,.--..-----,,,,.,,g
. -. -,,n.,- ..e-. , - - <,.
LO-LP-39213-00 lli. LESSON OUTLINE: NOTES
- 4. Bases
- a. Release to containment restricted from environment
- b. Sufficient to restrict release from fuel rupture
- 1) Lack of pressurization in refueling E. Communications T.S. 3/4.9.5
- 1. Direct communications between Control Room and refueling station
- 2. Applicable during CORE ALTERATIONS
- 3. Action is to suspend CORE ALTERATION Insiediate action
- 4. Bases
- a. Ensure facility staff informed during core alterations .
- 1) Significant c'hanges in facility status .
- 2) Changes in core reactivity conditions F. Refueling Machine T.S. 3/4.9.6
- 1. Refueling machine OPERABLE with:
- a. Design rated load on hoist of 3166 lbs (1966 lbs. on gripper)
- b. Overload setpoint Refer to T.S.
- 1) Primary - +250 vet, +350 dry
- 2) Seesadary - primary setpoint +150
- c. Load reduction - -150 wet or dry l 2. Anziliary hoist OPERABLE with:
- a. Mini - capacity of 3000 lbs.
- b. 1000 lb. load indicator 6
_-__.y--- ,.- , -. -. , - , , , -
LO-LP-39213-00 Ill. LESSON OUTLINE: NOTES
- 3. Applicable during movement of drive rods or fuel assemblies within the vessel
- 4. Action is to suspend use of the equipment. Insnediate action
- a. T.S. 3.0.3 is NA.
- 5. Bases
- a. Ensures
- 1) Used for movement of RCCA's and fuel assembly
- 2) Has capacity to lift RCCA's and fuel assembly
- 3) Core internals protected against excessive lifting force.
G. Crane Travel - Spent Fuel Storage Area T.S. 3/4.9.7
- 1. Heavy loads prohibited over fuel in pool. Define heavy. load
- 2. Applicable with irradiated fuel in pool.
- 3. Action is to place load in safe condition Immediate action
- a. T.S. 3.0.3 and 3.0.4 are NA.
- 4. Bases
- a. Ensures that if a load is dropped:
l
- 1) Release limited to single fuel assembly
- 2) Distortion of fuel will not result in critical array H. Residual Heat Ramsval and Coolant circulation
- 1. At least 1 RER train OFERABLE and in operation.* T.S. 3/4.9.8.1
- s.
- Footnote - train may be removed from operation for 1. hour out of 8 during CORE i ALTERATIONS near hot legs
- b. Applicable in Mode 6, with _ 23 ft of water over vessel flange 7
l
LO-LP-39213-00 lil. LESSON OUTLINE: NOTES
- c. Actions are:
- 1) Do not increase decay heat load or reduce Irenediate action boron concentration
- 2) Initiate corrective actions, return to Immediate action oper'ation ASAP
- 3) Close containment penetrations within 4 hrs.
- 2. Two RER trains OPERABLE, one in operation
- a.
- Footnote - prior to initial criticality RER Lower (approx. none) train may be removed from operation for i decay heat load.
hour out of 2 during CORE ALTERATIONS near hot legs
- b. Applicable in Mode 6 wher, 23 fe over vessel flange.
- c. Actions are:
- 1) With 1 RER tr,ain inoperable.
- Immediate action a) Initiate corrective actions, or b) Establish water level _ 23 ft over flange
- 2) With no RER train in operation Immediate action a) Do not reduce RCS C B b) Initiate corrective actions c) Close contai m t penetrations within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- 3. Bases i
- a. , At least one RER train in operation
- 1) Sufficient cooling to remain below 140*F
- 2) Sufficient circulation to mitigate dilution event 8
--y- -- , ,- -
.,w-.-,, . . _ --w,,-we.-e,-,. , , . , -- -,--,--ema,.m-.ww-. m--- - , , - - -
l LO-LP-39213-00
'_ lil. LESSON OUTLINE: NOTES
- b. Two RER trains with less than 23 feet
- 1) Need single failure criteria a) 23 feet of water provides heat sink I. Containment Ventilation Isolation T.S. 3/4.9.9
- 1. Containment Ventilation Isolation System must be OPERABLE.
- 2. Applicable during CORE ALTERATIONS or movement of irradiated fuel within containment.
- 3. Action is to close all ventilation penetrations. Immediate action
- a. T.S. 3.0.3 and 3.0.4 are NA.
- 4. Bases
- a. Ensures penetrations isolate
- b. Minimize release to environment .
J. Water Level - Reactor VesseI
- 1. MaAntain _ 23 ft of water over vessel flange T.S. 3/4.9.10.1
- a. Applicable during movement of irradiated fuel within containment.
- b. Action is to suspend fuel movement within Imediate action the vessel.
- 2. Maintain _23 feet over irradiated fuel within T.S. 3/4.9.10.2 vessel.
- a. Applicable in Mode 6 when moving control rods within vessel
- b. Action is to stop moving control rods within Imediate action vessel
- 3. Bases
- a. Ensures sufficient water depth available
- 1) Remove 99% of 10% iodine gap activity released during rupture of irradiated fuel 9
LO-LP-39213-00 lil. LESSON OUTLINE: NOTES l
K. Water Level - Spent Fuel Pool T.S. 3/4.9.11 i
- 1. Maintain _ 23 ft water over irradiated fuel stored in pool. )
- 2. Applicable when irradiated fuel in pool. ,
- 3. Action is to stop moving fuel and crane operations Immediate action over the pool and restore level within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- a. T.S. 3.0.3 and 3.0.4 are NA.
III. Summaary A. Boron Concentration B. Instrumentation C. Decay Time D. Containment Building Penetrations E. Communications .
F. Refueling Machine G. Crane Travel - Spent Fuel Storage Building H. Residual Heat Removal and Coolant Circulation I. Centainment Ventilation Exhaust System J. Water Level - Reactor Vessel K. Water Level - Storage. Pool IV. PRACTICAL EXERCISE l A. Exercise #
- 1. Provide the students with the following information.
- a. Calculated SDN is 5.3%
- b. RCS wide range temperature is 102'F.
- c. RCS Boron concentration is 2063 ppe. .
- d. Refueling canal boron concentration 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after head removal is 1980 ppe.
10
LO-LP-39213-00 Ill. LESSON OUTLINE: NOTES
- 2. What actions are required by Tech. Specs? When?
- a. Stop CORE ALTERATIONS, positive reactivity changes
- b. Initiate
- boration at _ 30 spa of _ 7000 ppa boron B. Exercise #2
- 1. Provide the students with the following information,
- s. Unit at 100% power following first refueling outage.
- b. Fuel transfer canal gate seal mechanism removal and replacement in progress.
I
- c. You are the Licensed Operator operating the SF Bridge Crane.
- d. You are directed to move the gate to a storage area which will require traversing .
over the spent fue,1 storage racks. - --
- 2. What are your actions?
- a. Do not move the gate from its present location, or
- b. Place it in a safe condition.
(Not over spent fuel)
C. Exercise #3 i 1. Provide the students with the following l information:
- a. Unit in Mode 6.
- b. IBR Train 'A' in operation.
- c. ' RCS wide range temp. approx. 100*F.
- d. Reactor water level is 24 ft over the fuel assemblies.
- e. The Refueling Machine auxiliary hoist operator is in process of disengaging control rod drive mechanisms.
- f. 'A' DG is out of service for maintenance.
11
LO-LP-39213-00 5 Ill. LESSON OUTLINE: NOTES
- 2. A fault on the grid results in 'A' RAT feeder breaker tripping. What are your actions? What is the Tech Spec. of concern?
- a. T.S. 3/4.9.8.2 requires two trains of RHR OPERABLE and one train in operation when water lev'el is < 23 f t above vessel flange.
Required action is immediately initiate corrective action to return to two OPERABLE trains or raise vessel level to > 23 ft above flange. In addition, with no RRR train in operation, do not reduce boron concentration, return one train to operation, and close all containment
. penetrations within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- b. Suggested operator actions.
- 1) Place 'B' RER train in service.
- 2) Establish reactor vessel level > 23 f t above flange.
9 e
! 12 1 .
t