ML20203K804
| ML20203K804 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/01/1986 |
| From: | Brown R, Slough R GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20203K798 | List: |
| References | |
| LO-LP-39202, LO-LP-39202-00, NUDOCS 8608210343 | |
| Download: ML20203K804 (12) | |
Text
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t Georgia Power 90wt.1 GthtRA180N CE919TMENT E
VOGTLE ELECTRIC GENERATING L o.
TRAINING LESSON PLAN!,.2 e
TITLE:
DEFINITIONS OF TECHNICAL SPECIFICATIONS NUMBER:
' -LP-39202-00 PROGRAM:
LICENSED OPERATOR TRAINING REVISION:
0 AUTHOR:
R. SLOUGH DATE:
8/1/86 3
TM [M DATE:
9/f /g APPROVEL:
INSTRUCTORGUIDELINES[
1.
OVERHEAD FOR TRANSPARENCIES 2.
WHITE BOARD WITH MARKERS l
, %9 '
s h
860E210343 G60014 PDR AcoCK 05000424 PDR 1
LO-LP-39202-00 l
l.
PURPOSE STATEMENT:
TO TEACH THE STUDENT THE DEFINITIONS OF TERMS USED IN THE TECHNICAL SPECIFICATIONS.
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ll.
LIST OF OBJECTIVES:
1.
The student shall be able to give the verbation definition from technical specifications for the following terms:
a.
Action b.
Axial Flux Difference c.
Channel Check d.
Containment Integrity e.
Core Alteration f.
Dose Equivalent I-131 g.
E - Average Disintegration Energy h.
Identified Leakage 1.
Operable - Operability J.
Operational Mode - Mode k.
Quadrant Power Tilt Ratio m.
Rated Thermal Power n.
Thermal Power p.
The student shall be able to paraphrase the definition given for the remaining terms.
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LO-LP-39202-00
REFERENCES:
TECHNICAL SPECIFICATIONS, SECTION 1. DEFINITIONS l
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1 LO-LP-39202-00 111.
LESSON OUTLINE:
NOTES 1.
PRESENTATION A.
Defined Terms in Technical Specifications 1.
Appear in capitalized type 2.
Are applicable *throughouc Tech. Specs.
3.
Terms with asterisk are required verbatim.
B.
Terms
- 1.
ACTION - shall be that part of a Specification which prescribes remedial measures required under designated conditions.
2.
ACTUATION LOGIC TEST - shall be the application of various simulated input combinations in conjunction with each possible interlock logic state and verification of the required logic output. The ACTUATION LOGIC TEST shall include a continuity check, as a minimum, of output devices.
3.
ANALOG CHANNEL OPERATIdNAL TEST - shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock and/or trip functions. They ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, interlock and/or trip setpoints such that the setpoints are within the required range and accuracy.
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- 4.
AXIAL FLUX DIFFERENCE - shall be the difference in flux signals (normalized to their full power I
l sua and expressed as their percentage) between l
the top and bottom halves of a two section excore neutron detector a.
Mathematical expression.
- AFD (or AI) = I
-I gp gg ITOP * 'BOITOM 1)
I must be " normalized" OP BOITOM 4
LO-LP-39202-00 111.
LESSON OUTLINE:
NOTES 5.
CHANNEL CALIBRATION - shall be the adjustment, as necessary, of the channel such that it responds with the required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.
- 6.
CHANNEL CHECK - shall be the qualitative assessment of channel behavior during operation by observation.
This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
- 7.
CONTAINMENT INTEGRITY - shall exist when:
s.
All penetrations required to be closed during accident conditions are either:
1)
Capable of being closed by an OPERABLE containment automatic isolation valve system, or 2)
Closed by manual valves, blind flanges, or deactivated tutomatic valves secured in their closed positions, except as provided in Table 3.6-1 of Specification 3.6.3.
b.
All equipment hatches are closed and sealed.
c.
Each air lock is OPERABLE pursuant to Specification 3.6.1.3..
d.
The containment leakage rates are within the limits of Specification 3.6.1.2, and e.
The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0-rings) is OPERABLE.
- 8.
CORE ATERATION - shall be the movement or mani-pulation of any component within the reactor pressure vessel with the vessel head removed and J
fuel in the vessel. Suspension of CORE ALTERATION shall not precluda completion of movement of a component to a safe conservative position.
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LO-LP-39202-00 Ill.
LESSON OUTLINE:
NOTES
- 9.
DOSE EQUIVALENT I-131 - shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133. I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those'11sted in Table E-7 at Regulatory Guide 1.109, Rev. 1, October 1977.
- 10.
E - AVERAGE DISINTEGRATION ENERGY - shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95%
of the total noniodine activity in the coolant.
11.
ENGINEERED SAFETY FEATURE RESPONSE TIME - shall be that interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of per-forming its safety function (i.e., the valves travel to their require,d positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays where applicable.
12.
FREQUENCY NOTATION - specified for the performance of Surveillance Requirements shall correspond to LO-TP-39202-00-001 the intervals defined in Table 1.1.
13.
GASEOUS WASTE PROCESSING SYSTEM - shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant 6
system offgases from the primary system and providing j
for delay or holdup for the. purpose of reducing the total radioactivity prior to release to the environment.
- 14.
IDENTIFIED LEAKAGE - shall bet a.
Leakage (except Reactor Coolant Pump Seal Leakoff) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or
~
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LO-LP-39202-00 Ill.
LESSON OUTLINE:
NOTES c.
Reactor coolant system leakage through a steam generator to the secondary system.
15.
MASTER RELAY TEST - shall be the energization of
)
each master relay and verification of OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay.
16.
MEMBER (S) 0F THE PUBLIC - shall include all persons who are not occupationally associated with the j
plant. This category does not include employees
)
of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational occupational, or other purposes not associated with the plant.
17.
OFFSITE DOSE CALCULATION MANUAL (ODCM) - shall contain the current methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid affluents, in the calculation of gaseous and liquid affluent monitoring alarm / trip setpoints, and in the conduct of the environment radiological monitoring program.
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- 18.
OPERABLE-OPERABILITY - a system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support j
function (s).
- 19.
OPERATIONAL M(BE-MODE - (i.e., MODE) - shall cor. respond to any one inclusive combination LO-TP-39202-00-002 I
of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.
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LO-LP-39202-00 Ill.
LESSON OUTLINE:
NOTES 20.
PHYSICS TESTS - shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation (1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.
- 21.
PRESSURE BOUNDARY LEAKAGE - shall be leakage (except steam generator tube leakage) through a i
nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.
22.
PROCESS CONTROL PROGRAM (PCP) - shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 and Federal and State regulations, burial ground requirements, and other requirements governing the disposal of radioactive waste.
1 23.
PURGE PURGING - shall bs the. controlled process of l
process of discharging air or gas from a confine-ment to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
- 24.
QUADRANT POWER TILT RATIO - shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector cali-3 brated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With.one excore detector inoperable, the remaining three detectors shall be used for computing the average.
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- 25.
RATED THERMAL POWER - shall be a total reactor core heat transfer rate to the reactor coolant of 3411 MWt.
26.
REACTOR TRIP RESPONSE TIME - shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss i
of stationary gripper coil voltage.
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LO-LP-39202-00 lli.
LESSON OUTLINE:
NOTES 27.
REPORTABLE EVENT - per Generic letter 83-43 a REPORTABLE EVENT shall be any of those conditions specified in Part 50, Sections 50.72 and 50.73 to 10 CFR.
- 28.
SHUTDOWN MARGIN - shall be the instantaneous amount of reactivity By which the reactor is subcritical or would be subcritical from its present condition assuming all rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.
29.
SITE BOUNDARY - shall be that property line shown in Figure 5.1-1 of these Technical Specifications.
30.
SLAVE RELAY TEST - shall be the energization of each slave relay and verification of OPERABILITY of each relay. The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.
31.
SOLIDIPICATION - shall be the conversion of wet radioactive waste into a form that meets shipping and burial ground requirements.
32.
SOURCE CHECK - shall be the qualitative assessment l '
of channel response when the channel sensor is exposed to a source of increased radioactivity.
33.
STAGGERED TEST BASIS - shall consist of:
I a.
A test schedule for a systems, subsystems, trains, or other designated components i
obtained by dividing the specified test interval into a equal subintervals.
b.
The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.
- 34.
THERMAL POWER - shall be the total reactor core heat transfer rate to the reactor coolant.
35.
TRIP ACTUATING DEVICE OPERATIONAL TEST - shall j
consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip functions. The TRIP ACTUATING DEV!CE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required setpoint within the l
required accuracy.
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LO-LP-39202-00 Ill.
LESSON OUTLINE:
NOTES
- 36.
UNIDENTIFIED LEAKAGE - shall be all leakage which is not IDENTIFIED LEAKAGE.
37.
UNRESTRICTED AREA - shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radio-active materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
38.
VENTILATION EXHAUST TREATMENT SYSTEM - shall be any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in affluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stresa prior to the release to the environment. Such a system is not considered to have any effect on noble gas affluents.
Engineered Safety Feature ESF) atmospheric cleanup systems are not considered to be VENTILATION. EXHAUST TREATMENT SYSTEM components.
39.
VENTING - shall be the controlled process of discharging air or gas.from a confinement to i
maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
2 II.
SUMMARY
A.
Review Objectives 10
-_.__..-_....~...,-___.---.c
.-m.v.-
-v--
TABLE 1.1 FREQUENCY NOTATION NOTATION FREQUENCY S
AT LEAST ONCE PER 12 HOURS 0
AT LEAST ONCE PER 24 HOURS W
AT LEAST ONCE PER 7 DAYS M
AT LEAST ONCE PER 31 DAYS Q
AT LEAST ONCE PER 92 DAYS SA AT LEAST ONCE PER 184 DAYS A
AT LEAST ONCE PER 366 DAYS R
AT LEAST ONCE PER 18 MONTHS S/U PRIOR TO EACH REACTOR STARTUP N A, NOT APPLICABLE P
COMPLETED PRIOR TO EACH RELEASE f()-Tf-39'LQZ C&l
TABLE 1.2 OPERATIONAL MODES REACTIVITY I RATED AVG COOLANT MODE CONDITION, K THERMAL POWER
- TEMPERATURE eff
- 1. POWER OPERATION 20.99
' 5I 2350'F
- 2. STARTUP 30.99 55%
_ 350*F
- 3. HOT STANDBY
=0.99 0
3350*F
- 4. HOT SHUIDOWN
=0.99 0
350"F = T "200 F avg
- 5. COLD SHUTDOWN
=0.99 0
5200*F
- 6. REFUELING **
_ 0.95 0
5140*F
- EXCLUDING DECAY HEAT
- FUEL IN THE REACTOR VESSEL WITH THE VESSEL HEAD CLOSURE BOLTS LESS THAN FULLY TENSIONED OR WITH THE HEAD REMOVED
- l 20 - 7/- 39702 do 7 t
_ _ _ _ _