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{{#Wiki_filter:}} | {{#Wiki_filter:a Georgia Power nea. mno war a,,, | ||
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: | |||
0_ | |||
WHITE BOARD WITH MARKERS a- | |||
.?'Y | |||
,t | |||
.- P $[ . h g,, 3 'y.; y w t | |||
\W 8608210373 860814 PDR ADOCK 05000424 l V PDH i | |||
I | |||
t' LO-LP-39213-00 | |||
: 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 hours. | |||
: 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 | |||
* T.S. 3/4.9.8.2 | |||
: 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 hours | |||
: 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 | |||
* l | |||
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 hours. | |||
: 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 hours 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 hours. | |||
: 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}} |
Latest revision as of 09:56, 31 December 2020
ML20203K836 | |
Person / Time | |
---|---|
Site: | Vogtle |
Issue date: | 08/05/1986 |
From: | Brown R, Slough R GEORGIA POWER CO. |
To: | |
Shared Package | |
ML20203K798 | List: |
References | |
LO-LP-39213, LO-LP-39213-00, NUDOCS 8608210373 | |
Download: ML20203K836 (12) | |
Text
a Georgia Power nea. mno war a,,,
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:
0_
WHITE BOARD WITH MARKERS a-
.?'Y
,t
.- P $[ . h g,, 3 'y.; y w t
\W 8608210373 860814 PDR ADOCK 05000424 l V PDH i
I
t' LO-LP-39213-00
- 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
- T.S. 3/4.9.8.2
- 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
- l
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.
- 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.
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