ML20115C529
| ML20115C529 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/08/1985 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| GN-575, NUDOCS 8504180454 | |
| Download: ML20115C529 (25) | |
Text
- - -
GeorCia Power Company Routa 2. Box 299A Wayrnsboro, Georgia 30330 Telephon 404 554-9961 404 724-8114 -
Southern Company Services, Inc.
Post Office Box 2625 Birmingham, Alabama 35202 Telephone 205 8704011 -
Vogtle Proj.ect i
April 8,' 1985 Director of Nuclear Reactor Regulation-File: X3BC35 Attention:
Ms. Elinor G. Adensam, Chief Log:
GN-575 Licensing Branch #4 Division of Licensing U. S. Nuclear Regulatory Commission-Washington, D.C.
20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE FJ.ECTRIC GENERATING PLANT - UNITS 1 AND 2 DSER OPEN ITEM 99 - INITIAL TEST PROGRAM
Dear Mr. Denton:
Attached for your staff's review is the information requested on the VEGP initial test program. This information includes the items discussed in a teleconference with your. staff on April 2, 1985 and will be included in Amendment 16 to the VEGP FSAR.
If your staff. requires any additional information, please do not hesitate to contact me.
Sincerely,
,h.
J. A. Bailey Project Licensing Manager JAB /sm Enclosure xc:.
D. O. Foster R. A. Thomas G. F. Trowbridge, Esquire J. E. Joiner, Esquire C. A. Stangler L. Fowler M..A. Miller-
-L. T.'Gucwa G. Bockhold,'Jr..
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0119m 8504180454 850408)"
PDR ADOCK 05000424 E
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u REVISED RESPONSE TO NRC QUESTION 640.02 Revise item D to read:
"D.
Each licensed reactor operator (R0 or SRO who performs R0 or SR0 duties, respectively) will participate in the initiation, maintenance, and rec 0very from natural circulation during the low power natural circulation test or receive training on the simulator."
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VEGP-FSAR-Q preoperational test (paragraph 14.2.8.1.1), and pressurizer safety valve testing has been added to the reactor coolant 9
system preoperational test abstract (paragraph 14.2.8.1.7).
The capacity of the pressurizer power-operated relief valves and the power-operated atmospheric relief valves is certified by 'the manufacturer.
The pressurizer power-operated relief valves will be opened during hot functional testing as part of the pressurizer pressure and level control preoperational test (paragraph 14.2.8.1.11) which will verify that the discharge piping is clear and does not produce backpressure affecting the set / reset pressures. 'The testing to verify that the power-operated relief valves or the steam generator atmospheric 15 release valves.do not exceed the maximum analyzed capacity is unnecessary.
%c 2naly?ed caces Ican enction 15 @ eme
-for a safsty uulcuse volve which in both chu us;c of the <g -
.Hpsascurizcr oud steam euxvs exceed the FORV vovecity by a faELvr of se e t v u m a L u l-y---2.
rxceedh.g the analy;sa
-cdou Ao uvi viudible.
The pressurizer power-operated relief valves are designed to prevent actuation of the reactor high pressure trip and the opening of the pressurizer safety valves on a 50 percent load reduction transient as described in.
subsection 5.4.13.
This verification of the capacity of the pressurizer power-operated relief valves will be demonstrated in the large load reduction test (paragraph 14.2.8.2.5.2).
The main steam atmospheric relief valves will be operated during hot functional testing which will verify the discharge. piping.is clear.
The main steam atmospheric relief valves are designed to pass suffic ent flow to achieve 50 /h plant cooldown rate as described in subsection 10.3.2.
The capacity of the main steam atmospheric relief valves will not be verified inplace, but with the manufacturer's certification and the demonstrated gg operability of the relief valves, VEGP meets the criteria of l15 Regulatory Guide 1.68, Revision 2, Appendix A, in regard to main
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steam atmospheric relief valves.
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Amend. 8 7/84 Amend. 9 8/84 Q640.30-2 Amend. 15 3/85 ll>
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VEGP-FSAR-14 3.
Installation corrections for individual RTDs and l15 isothermal corrections for individual thermocouples are determined.from the recorded data.
4.
After disconnecting special test instrumentation l1.5 and reconnecting RTDs to normal plant terminations, temperature' data are taken to verify that all temperature instruments are reading correctly.
D.
Acceptance Criteria l15 1.
Test data are recorded for future alignment purposes on'.y, and specific acceptance criteria are not provided.
However, any individual RTD reading that differs from the calculated average temperature by a specified amount will not be used for average temperature calculations.
2.
All temperature instruments operate properly after l15 reconnecting RTDs to their normal plant f.erminations.
3 All MmoWA4vre. sos mtMs diu nuded b mawud.dc.d1 W491' # d ? & V g d gen $*L**"egh A %<
RTD Bypass 71ow Measurem.
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' cat 14.2.8.1.16 A.
Objectives 1.
To determine the flowrate necessary to achieve the design reactor coolant transport time in each RTD bypass loop.
2.
To measure the flowrate in each RTD bypass l'oop and ensure that the transport times are acceptable.
B.
Prorequisites 1.
Required component testing and instrument
'I calibration are complete.
i 2.
The installed pipe length measurements are made with the plant cold before insulation is l
minstalled.
l Amend. 10 9/84 s
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14.2.8-18 Amend. 15-3/85 L
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VEGP-FSAR-14 7
containment spray a'ctuation load, load shed, and load sequencing signals.
(See figure 7.3.11-2.)
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2.
Containment spray pump and system performance characteristics are within design specifications.
s (See NSSS Startup Manual, SU-4.1.B.)
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3 3.
Spray additive eductor operating characteristics are within design specifications.
(See ESAR 15 6.2.2-4 ) ~
fi) 4.
All containment spray nozzles are unobstructed, as l'
evidenced by air passing through each nozzle.
(See l15 NSSS Startup Manual, SU-4.1.8.)
5.
Containment spray pump and room cooler fan interlocking operates properly. ' (See figure 15
/
7.3.13-1.)
6.
Containment spray system valve response times are within design specifications.
(See table 6.2.4-1.)
l15
- 7..
Available neti. positive suction head (NPSH) requirements are met for the containment spray
~
pumps, centrifugal charging pumps, safety injection pumps, and RHR pumps when all eight 3
pumps are run simultaneously.
(See figure l15
- 6. 2. 2 - 4,W G.3. L - 3, (o. 5, ]. R 4,.3. L-s) 14.2.8.1.27 Reactor Makeup Water Storage Tank and Degasifier System Preoperational Test 7, y.
A '.
Objective-E To demonstrate operatior! of the reactor makeup water storage tank and deg,asifier system.
B.-
Prerequisites
,x:
The required portions' of the following prerequisites are 11 completed ' as' necessary-to ~ support. the ~preoperational test:
f
> 1.
Construction acceptance testing completed.
2.
Component testing and instrumen't calibration completed.
1
. 3.
Test instrumentation-available and' calibrated.
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Amend. 11 11/84
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7b 6j 14'.2.8-35 Amend. 15 -3/85.
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VEGP-FSAR-.14 14.2.8.1.35 Auxiliary Feedwater Pumphouse HVAC System Preoperational Test A.
Objective To demonstrate operation of the auxiliary feedwater pumphouse HVAC system.
B.
Prerequisites The required portions of the following prerequisites are completed as necessary to support the preoperational 11
. test:
1.
Construction acceptance testing is. complete.
2.
Component testing and instrument calibration.are complete.
3.
Test instrumentation is available and cal.ibrated.
4.
Support systems are available.
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Test Method
~
1.
Verify manual and automatic system controls.
2.
Verify alarme _ir.dicating instrumente, and status lights are fuactional.
at -- - __.
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'* " " 3.
Verify desi, n airflow.
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- 1The auxiliary feedwater pumphouse HVAC system operates O'*1(AMP as described in subsection 9.4.8.
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A1 14.2.8.1'.36 Euel Han ling Building HVAC System Preoperational (q,1l,q,g Test A.
Objective To demonstrate operation of the fuel handling building' HVAC system.
B.
Prerequisites The required portions of the fcIlowing prerequisites are completed as necessary to support the preoperational 11 test:
Amend. 10 9/84 14.2.8-44 Amend. 11 11/84
u-VEGP-FSAR-14 C.
Test Met' hod l'.
Verify instrument response to simulated external inputs.
2.
Verify sampling system operation.
~
3.
Verify emergency response facilities communication systems.
D.
Acceptance Criteria 1.
The emergency response facilities function as de' scribed in subsection 9.5.10 ahen using th; abere test.T.cth:d.
2.
The post-accident sampling system operates as described in subsection 9.3.2 ah;n using th: JacT;
.__m mt
_2_
3.
The post-accident monitoring system operates as described in subsection 7.5.3.
4.
Verify the turbine plant-sampling system operates 10 as described in subsection 9.3.2.
5.
Verify the nuclear sampling system operates as
. described in subsection 9.3.2.
14.2.8.1.84 ' Reactor Protection Syste'm and Engineered Safety Features Actuation System (ESFAS) Logic Preoperational Test A.
Objectives 1.
To demonstrate operation of the ESFAS and reactor protection system and their ability to initiate appropriate reactor-trip and safety actuation signals on receipt of simulated input signals.
2.
To demonstrate operation of the; reactor protection system block and permissive interlocks.
'B.
Prerequisites 1.
Required component testing and instrument calibrations are complete.
l Amend. 10 9/84 14.2.8-89 Amend. 11 11/84
_v-VEGP-FSAR-14 i
l 1
D.
Acceptance Criterion
~
The combined leakage from containment penetrations and isolation valves 1:.ithin design limitar is 44 WbfE lq itakage, cd- 0. 02.0% by w en g h.4-of 15 a
'CobineM dse p 14f hes cd-a p re ssure_
MOh $f% Nhan Yq ( d csiq q acc(de.o.hg,rcssue_)
i 14.2.8-108a Amend. 15 3/85
VEGP-FSAR-14 14.2.8.1.100 Reactor Containment Structural Integrity Test 14.
Objective i
To demonstrate the structural integrity of the reactor containment building.
B.
Prere~uisites q
1.
Containment penetrations are installed, and penetration leak tests are complete.
2.
Containment penetrations, including equipment latches and personnel airlocks, are closed.
C.
Test Method.
The containment is pressurized to the test value and deflection measurements, and concrete crack inspections are made to determine that the actual structural response is within the limits predicted by the design analyses.
D.
Acceptance. Criterion The containment structural response is within the i
limits predicted by design analyses ( FSA. A 3,8.1, 7) 14.2.8.1.101 High-Efficienty Particulate Air. Filters Preoperational Test A.
Objective To demonstrate operation of the high-efficiency i
particulate air (HEPA) filters.
B.
Prerequisites The required portions of the following prerequisites are completed as necessary to support the preoperational 11 test:
1.
Construction acceptance testing is complete.
2.
The ventilation systems contaiping HEPA filters and charcoal absorbers have been air balanced and are' operational and available to support this test.
l l-14.2.8-109 Amend. 11 11/84.
VEGP-FSAR-14 B.
Prerequisites 1.
This-test is conducted simultaneously with hot
~~
functional testing.
2.
Supports, restraints, and hangers are installed; andereference points and predicted movements are established.
3.
Temporary instrumentation is installed as required to monitor the expansion of the components under test.
4.
A preservice examination has been performed on snubbers as defined in paragraph 14.2.8.1.103.A.2.
1 C.
Test Method 1.
During the reactor coolant system heatup and cooldown, deflection data are recorded.
2.
Snubber thermal movements are verified-by recording positions during initial system heatup and cooldown 1
3.
Snubber swing clearance is verified at specified heatup and cooldown intervals.
D.
Acceptance Criteria 1.
There shall be no evidence of blocking of the thermal expansion of any piping or components,h M (tuget3 other than by 9 bn to d a))gd suffo k /05 h~in
( ES M 3 M 3.2..I 2.
Spring hanger mo ements must remain within the hot and cold setpoints, and snubbers must not become fully retracted or extended.
3.
Piping and components must return to their approximate baseline cold position.
14.2.8.1.104. Power Conversion and Emergency Core Cooling System Dynamics Test
('
A.
Objective To demonstrate during specified transients that the system's monitored parts respond in accordance with design calculations.
Amend. 1 11/83 L
14.2.8-112 Amend. 11 11/84 L,
VEGP-FSAR-14 B.
Prerequisites 1.
Reference points for measurement of the systems are established, and required temporary instrumentation is installed and calibrated.
2..
Hot functional testing is in progress.
i 3.
.All subject systems are available for the specified dynamic operations.
C.
Test Method Deflection measurements are recorded during various plant transients.
D.
Acceptance Criteria 1.
The movements due to flow-induced loads shall not exceed design limits.CF$4A 7 4,t) 2.
Flow-induced movements and loads will not cause malfunctions of plant equipment or instrumentation.
A 14.2.8.1.105 Remote Shutdown Preoperational Test A.
Objectives 1.
-To demonstrate the capability to cool down-the plant from the hot. standby condition to the cold shutdown condition using controls and-instrumentation located outside the control room.
2.
To demonstrate the capability to control plant parameters during a simulated loss of ac power 9
using manual control and the steam-driven auxiliary feedwater pump.
B.
Prerequisites 1.
-The controls and instrumentation associated with the remote shutdown panel are available.
2.
Hot functional testing is in progress with the RCS temperatureLabove that at which the RHR system is i
in operation.
Amend. 9 8/84 14.2.8-113 Amend'.11 11/84
u VEGP-FSAR-14 3.
Test instrumentation is available and calibrated.
4.
Support systems are available.
C.
Test Methods 1.
Extraction line isolation and drain valves will be tested to verify the valves function in accordance with the control logic.
2.
Each nonreturn valve will be observed.in itc normal
.f e r i f y--thr.t the== ' -- 4 cpen-9 om o,-
- 4 n -
,mam
+- m
-i; frc-me.c cnd to verify that the valve shuts following a turbine trip signal.
D.
Acceptance Criteria gla$yn C$0%. ODN Yf4Ib d'-
valvce 1.
The extraction line isolationytand f m i.ivu n. acccrdance with the cent.rci le ic.
v 1/alW5 ofh 8ellumq o Mmt hip spl 2.
Each nonreturn valve operatcc -properly--in-its gjpyg e.:;;;l cgeretD7 ="-- z.d following a turbine 9
trip.
14.2.8.1.108 Condensate and Feedwater Chemical Injections System Test A.
Objective To verify the operability of the condensate and feedwater chemical injection system.
B.
Prerequisities 1.
Required construction acceptance testing i s complete.
11 2.
Required system flushing / cleaning is complete.
3.
Required electrical power supplies and control circuits are operational.
4.
The condensate and feedwater systems are available.
C.
Test Method 1.
The operating parameters of the positive displacement chemical feed pumps and the wet lay-up pumps will be measured.
Amend. 9 8/84 14.2.8-116 Ame.Td. 11 11/84
k VEGP-FSAR-14 l
2.
The operating parameters of the mixing pumps will be measured.
D.
Acceptance Criterion I. 7k y #sek 4to v 4lvcs o vak as bc"bd m 10 4.7.2.1 5' h
is s A a 4ma4sc 4,wk-ns,eg u,,d +o eJJ cL a cJ,,4.,
os hunbed in 1o. 4. 7. s 14.2.8.1.109 Proteus Computer Preoperatonal Test A.
Objectives 1.
To verify computer hardware is operational.
2.
To verify all analog and digital inputs are conditioned correctly.
3.
To verify computer software functions correctly.
B.
Prerequisites 9
1.
Required electriqal power supplies are operational.
2.
Test instrumentation is available and calibrated.
D.
Test Method 1.
Diagnostic programs are run on each section of hardware.
2.
Test signals are injected into the computer to simulate all analog and digital inputs.
3.
Software routines are run to verify operability of the software.
D.
Acceptance Criteria Thediagnosticprogramsrunoncompy)terhardware 1.
without error (e30tp mel4ednied %,M.
2.
The computer conditions all analog'S$
i ta$
4nputc acoordi-- to-tha A*a base.
W h%u)hl%hMS miphg, Job kase.
t r' 3.
All software routines run without error, w Q SE 'd Mk diopicshC6 f k OPP k dtova pocgron l
& foce&.
Amend. 9 8/84 14.2.8-117 Amend. 11 11/84
n VEGP-FSAR-14 14.2.8.1.110 Equipment Building HVAC and Piping Penetration Preoperational Test A.
Objective 9
To demonstrate operation of the containment penetration cooling system and the equipment building HVAC system.
B.
Prerequisites The required portions of the following prerequisites are completed as necessary to support the 11 preoperational test:
1.
Construction acceptance testing is complete.
2.
Component tenting and instrumentation calibration are complete.
3.
Test instrumentation is available and calibrated.
4.
Support systems are available.
C.
Test Method 1.
Verify manual and automatic system controls.
2.
Verify alarms,-+udiceting~rnstrumcnts, and status 9
lights are functional.
3.
Verify design airflow.
D.
Acceptance Criteria EST All fans, dampers, and heaters operate mara*11;_ nd 1.
a iwne= = t i c a c c o rdug--tode sign- -4e cis dos <f e bed
'n 4, tf. 3. L a.., J 4, 4, 9, 7.,
2.')Allga(a s,- ' dic3 tope, 4@pd c,pnttgl,: Q tchs h Mpe ute cco in% to es n.
- 3. %n a i r f lee i s "e ri f-14d,- ),t_ // pro /d, ffF -[rin IS 45 ch tr},e d i,,
- 9. J. 7 7_ m, d 7, af 9. 7.
14.2.8.1.111 Stdam Generator Blowdown Processing System 1C l
A.
Objective To demonstrate that the steam generator blowdown processing system accepts water from each steam generator blowdown line, processes the blowdown as Amend. 9 8/84 Amend. 10 9/84 i
14.2.8-118 Amend. 11 11/84
14.2.8.1.
125 Vdc Class IE Minimum Load Voltage Verification A. '0BJECTIVES 1.
To measure the voltage drops, at nominal battery voltage, to 125-Vdc Class 1E inverters and power-operated valves.
2.
To determine the voltage which would be available at the 125-Vdc Class IE inverters and power-operated valves if the batteries were discharged to the minimum voltage limit.
-3.
To verify that the voltage available to 125-Vdc Class 1E inverters and power-operated valves exceeds the design minimum.
B.
Prerequisites 1.
Required construction acceptance testing is complete.
2.
The 125-Yde Class IE inverters and power-operated valves are operable.
3.
Required load test devices are available.
C.
Test Method 1.
Each 125-Vdc Class 1E inverter will be loaded to its design capacity and the voltage drop from the battery to the inverter input measured.
2.
Each 125-Vdc Class 1E power-operated valve will be operated and the voltage drop from the battery to the motor or solenoid measured.
3.
The minimum available voltage at each 125-Vdc Class IE inverter and power-operated valve will be determined from the measured voltage drops and the battery minimum voltago limit.
D.
Acceptance Criteria 1.
The minimum available input voltage for the 125-Vdc Class 1E inverters equals or exceeds 104 Vdc.
(DC-1806) 2.
The minimum available input voltage for the 125-Vdc Class 1E power-operated valves equals or exceeds 100 Vdc.
(DC-1806).
u 1
VEGP-FSAR-14 C.
Test Method 1.
The flowrate necessary to achieve the design reactor coolant transport time for each hot and cold leg bypass loop is calculated utilizing the piping length of each leg.
2.
The hot and cold leg RTD bypass loop flow data are recorded at ' operating temperature and pressure.
I D.
Acceptance Criterion 1.
Using VEGP Unit 1 actual piping lengths the minimum flowrates were calculated to meet the transport time specified in the Westinghouse NSSS Startup Manual.
15 2.
Actual flow rates in all RTD bypass manifolds exceed the minimum required flow raterrejvistd S o (b teAit. A l.0 5 ecce1d dvan pc'4-41m t,
3.
Each RTD loop bypass low flow alarm has been verified to activate at the flow specified in the Westinghouse NSSS Startup Manual.
o 1
i '
14.2.8-122a Amend. 15 3/85 l
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7 u-l VEGP-FSAR-14 C.
Test Method 1.
Plant conditions are stabilized at selected power levels (30,u5', 75, and 90 percent).
The plant l11l15 O
load is varied, using the turbine-generator
-controller, in a manner approximating step changes of about 2-to 4-percent power.
2.
The. differential power coefficient is obtained by dividing the total reactivity added, by rod movement, by the change in power.
D.
Acceptance Criterion The average value of the power coefficient agrees with the value given in the nuclear fuel design report.
l9 14.2.8.2.27 Load Swing Test A.
Objective To verify nuclear plant transient response, including automatic control system performance, when step load changes are introduced to the turbine-generator at 30, l9 50, 75, and 100 percent and at power levels.
E B.
Prerequisite The plant is operating in a steady state condition at the desired power level.
C.
Test Method The turbine-generator output is manually charged as rapidly as possible to achieve a step load increase or decrease.
Selected plant' parameters are monitored and recorded during the load transients.
D.
Acceptance Criterion
"'Fn$6dd s
he control systems, with no manual intervention, ai in re tor power, RCS y peratu.
pressur zer r ss re and evel a d steam nerator vels/a d press esjkit out exc edip' tri point oz
produc dive sing oc ' Rations during steady-state-15 and transient operation.
r Amend. 9 8/84 Amend. 11 11/84 14.2.8-140 Amend. 15 3/85 l
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A
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Acceptance Criterion -
1.
The ' primary and secondary control systems, with no manual intervention, maintain reactor power, RCS temperature, pressurizer pressure and level, steam generator levels and pressures within accept 'ble ranges during steady-state and
' transn nt operation.*
- Control system response is reviewed and adjustments to the control systems are made, if necessary, prior to proceeding to the next power plateau.
e l
l
u VEGP-FSAR-14 3.
Core exit thermocouples will be monitored to assess core flow distribution.
i n.
D.
A Cr3ter6ew j
y must oc ur in the primary
- tem, fa'aturalcirculati a
id f imag tem l15 r
ure d
ress s
re hin e
dhigrdimi,ts fF R
ectio
.2.
s 14.2.8.2.48 Thermal Expansion Test A.
Objective To demonstrate that essential NSSS and BOP components.
can expand without obstruction and that the expansion is in accordance with design.
Also, during cooldown the. components return to their approximate baseline cold position.
Testing will be conducted to resolve discrepancies from hot functional testing and to test modifications made since hot functional testing was completed.
Systems not tested during hot functional will be tested (e.g., main feedwater).
B.
Prerequisite ~
Temporary instrumentation is installed as required to monitor the deflections for the components under test.
C.
Test Method For the components being tested the following will apply:
1.
During plant heatup and cooldown, deflection data are recorded.
2.
Snubber movements are verified by recording hot and cold positions.
D.
Acceptance Criteria For the components being tested the following will apply:
1.
There shall be no evidence of blocking of the thermal expansion of any piping or component other t/..... L,_
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P-LwL.1 D.1 Natural circulation must occur in the primary system, and primary temperatures and pressures are within the design limits ~of FSAR 5.1.2.
2.
Delta T across the reactor core is less than the full power delta T.
3.
Decay heat removal capability is demonstrated by maintaining natural circulation conditions for a minimum of one hour.
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b i
VEGP-FSAR-14 C.
Test Method 1.
The turbine-generator is tripped by opening the l8 generator main breakers.
I 2.
Selected plant parameters are monitored and recorded.
3.
If necessary, the control systems setpoints are adjusted to obtain optimal response.
D.
Acceptance Criteri$n-
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$1984'T b (lan control systems and operat r acpions c'an control l
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rRa-Lperc'ent lo'ad' 8 15 14.2.8.2.54 Steam Generator Moisture Carryover Test A.
Objective To determine the moisture carryover performance of the steam generators.
B.
Prerequisites 1.
Necessary licensing arrangements have been made for receipt and handling of approximately 1.0 Ci of sodium 24 isotope.
9 2.
A suitable chemical addition system is available, with the capabilities for mixing the radioactive tracer solution in demineralized water and injecting it into the steam generator.
C.
Test Method 1.
Inject a radioactive tracer into the steam generator and perform activity analysis of selected water and steam samples.
2.
Using the resulting data, calculate the average steam generator moisture carryover.
D.
Acceptance Criterion The measured steam generator moisture carryover is less than or equal to the warranted value.
Amend. 8 7/84 Amend. 9 8/84 Amend. 11 11/84 14.2.8-159 Amend. 15 3/85
r 3
m
%rh 1 D.
Acceptance Criterion -
1.
Following a 100 percent load rejection primary and secondary control systems and operator actions can stabilize RCS temperature, pressurizer pressure and level, and steam generator levels to no load operating temperature and pressure.
2.
The steam dump control system operates to prevent opening of primary and secondary safety valves.
~14.2.8.2.59 Gross Failed Fuel Detector Test A.
Objective 1.
To calibrate the gross failed fuel detector 2.
To establish baseline activity levels.
B.
Prerequisites 1.
Required electrical power supplies and control circuits are energized and operational 2.
A neutron source is available C.
Test Method 1.
Using a neutron source, the detector is calibrated and alarms checked.
2.
At specified power levels (25, 100%) baseline activity levels are recorded.
D.
Acceptance Criteria 1.
The gross failed fuel detector is calibrated in accordance with the Westinghouse technical manual.
2.
Base line activity levels are established.
1
+