ML20090J263
| ML20090J263 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/25/1984 |
| From: | Koester G KANSAS GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| KMLNRC-84-123, NUDOCS 8407300268 | |
| Download: ML20090J263 (23) | |
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l KANSAS GAS AND ELECTRIC COMPANY THE ELECTM COMPANY cLENN L.
NOESTER vica perseormt. muctran July 25, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 KMLNRC 84-123 Re:
Docket No. STN 50-482 Subj: Initial Test Prograra Changes
Dear Mr. Denton:
SNUPPS FSAR Section 14.2.3 addresses the availability of 'r'SAR testing commitments for NRC review.
In support of this section, transmitted herewith are marked-up changes to the Wolf Creek Initial Test Program described in the Wolf Creek and SNUPPS FSARs.
Attachment A contains changes to the Wolf Creek FSAR Addendum. These j
changes include incorporation of tests previously described in the SNUPPS FSAR and modifications, corrections and clarifications to test abstracts.
Attachment B contains changes to the SNUPPS FSAR.
These changes include modifications and clarifications to test abstracts and clarifications relating to the preoperational test schedules. Schedule clarifications reflect the fact that Administrative Procedures exist to ensure that all prerequisites are met before testing -a initiated.
This information will be formally incorporated into the next revision of the Wolf Creek and SNUPPS Safety Analysis Reports. This information is hereby incorporated into the Wolf Creek Generating Station, Unit No.1, Operating License Application.
Yours very truly, 8407300268 840725 PDR ADOCK 05000482
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GLK:bb Attach xc: PO'Connor (2)
HBundy JCermak-SNUPPS DWalker-UE p
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201 N. Market - Wichita, Kansas - mar Address: PO. Box 208 i Wichita, Kansas 67201 - Telephone: Area Code (316) 261-6451
F OATH OF AFFIRMATION STATE OF KANSAS
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) SS:
1 COUNTY OF SEDGWICK )
I, Glenn L. Koester, of lawful age, being duly sworn upon oath, do depose, 5
state and affirm that I am Vice President - Nuclear of Kansas Gas and Electric Company, Wichita, Kansas, that I have signed the foregoing letter of transmittal, know the contents thereof, and that all statements contained therein are true.
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KANSAS GAS AND ELE'"TRIC COMPANY I--
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f Glenn L. Koeste'r '
3' Vice President - Nuclear k'.
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Prothro, Assistant Secretary b
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a-g; STATE OF KANSAS
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1 COUNTY OF SEDGWICK )
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BE IT REMEMBERED that on this 25th day of July, 1984
, before p-me, Evelyn L. Fry, a Notary, personally appeared Glenn L. Koester, Vice 1
President - Nuclear of Kansas Gas and Electric Company, Wichita, Kansas, I
who is personally known to me and who executed the foregoing instrument, and he duly acknowledged the execution of the same for and on behalf of 2
l and as the act and deed of said corporation.
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,.........JN WITNESS WHEREOF, I have hereunto set my hand and affixed my seal tne V:
'M b t d' ate and year voove written.
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- My' Commission expires on August 15, 1984.
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A&. A SNUPPS-we It Press &ue Relief %4r 14.2.12.1.te >PR9 Cold Preoperational Test (#E ^'E902) it Su3-68ow 14.2.12.1.10.1 Objectives To demonstrate that the reactor makeup water system can supply design pressurizer relief tank (PRT) spray flow against design backpressure.
The operation of the PRT nitrogen isolation valves, including their response to a containment isolation signal, is also verified.
81 14.2.12.1.L&.2 Prerequisites Required component testing, instrument calibration, and a.
system flushing / cleaning are complete.
b.
Required electrical power supplies and control circuits are operational.
The reactor makeup water system is available to supply c.
water to the PRT.
prssveise d.
The service gas system is available to providc a nitrc;cn 3-supp'y td"the PRT.
/2 14.2.12.1.20.3 Test Method With a design backpressure in the PRT, a reactor makeup a.
water pump is operated to obtain the spray flow to the PRT.
b.
The response of the PRT nitrogen isolation valves to a containment isolation signal is verified.
14.2.12..b.4 Acceptance Criteria The reactor makeup water system supplies the design a.
spray flow to the PRT with design backpressure in the l
PRT.
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PRT nitrogen isolation valves close on receipt of a containment isolation signal.
Valve closure times are i
within design specifications.
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SHUPPS-WC 14.2.12.1.26 Charging System Preoperational Test (SU3-BG03) 14.2.12.1.26.1 Objective To demonstrate positive displacement charging pump operating characteristics and to verify the operation of the regenera- -
tive heat exchanger inlet isolation valves and the letdown
-isolation valves, including their response to a safety in-jection signal ( SIS ) '.
14.2.12.1.26.2 Prerequisites s
a.
Required component testing, instrument calibra-tion, and system flushing / cleaning are complete.
b.
Required electrical power supplies and control circuits are operational.
c.
The volume control tank contains an adequate supply of demineralized water for the performance of this test.
Y d.
The ccm,2cs..L eooling water cycts is available to prc ride ccclin3 2tcr tc the positive displacement Y
charging pump.
e.
The reactor coolant system is available to receive charging system flow.
14.2.12.1.26.3 Test Method a.
The positive displacement charging pump is oper-ated, and pump operating data are recorded.
b.
Regenerative heat exchanger inlet isolation valve and le tdown system isolation - valve control cir-cuits ~ are verified, including valve response to safety injection signals.
14.2.12.1.26.4 Acceptance Criteria Positive displacement charging pump operating char-h.
acteristics are within design specifications.
b.
Charging pump to regenerative heat exchanger inlet isolation valves close on receipt of an SIS.
Valve closure times are within design specifica-tions.
c.
The le tdown line containment isolation valves close on receipt of a
containment isol: tion signal.
Valve closure times are within design specifications.
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14.2.12.1.25 Sea] Injection Precperational Test (S 000002)
'3u s-BGot 14.2.12.1.25.1 Objectives To demonstrate the' ability of the chemical and volume control system to supply adequate seal water injection flow to the reactor coolant pumps and verify the operation of the seal water return containment isolation valves, including their response to a CIS.
14.2.12.1.25.2 Prerequisites a.
Required component testing, instrument calibration,' and system flushing / cleaning are complete.
b.
Required electrical power supplies and control circuits are operational.
c.
The' volume control tank contains an adequate supply of demineralized wateb for the performance of this test.
d.
The cc.;po mat gooling water c'ctc. is available to j
-previde cccling catm. to-the charging pumps.
14.2.12.1.25.3 Test Method a.
With a charging pump in operation, seal water throttle valves are adjusted to maintain the required flow to each reactor coolant pump.
b.
Seal water return containment isolation valves control logics are verified, including their response to a CIS.
14.2.12.1.25.4 Acceptance Criteria a.
Seal water injection flow to each reactor coolant pump is within design specifications.
b.
Seal water return containment isolation valves close on receipt of a CIS.
Valve closure times are within design specifications.
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SNUPPS - WC dr 14.2.12.1.30 Fuel Pool Cooling and Cleanup System Preoperational Test (S 02:001)
Su3-acol 14.'2.12.1.30.1 Objectives To demonstrate the operating characteristics of the fuel a.
pool cooling, fuel pool cleanup, and pool skimmer pumps and to verify that the associated instrumentation and controls are functioning properly.
b.
To verify that the fuel pool cleanup pump refueling water storage tank (RWST) suction isolation valves close on receipt of a safety injection signal (SIS).
To verify that each fuel pool cooling pumproom cooler c.
starts when the associated fuel pool cooling pump starts.
14.2.12.1.30.2 Prerequisites Required component testing, instrument calibration, and a.
system flushing / cleaning are complete.
b.
Required electrical power _ supplies and control circuits are operational.
Thecomp'nentTpoolingwatersysterisavailableto c.
providc c; cling "ater t1'the fuel pool cooling and cleanup system heat exchangers.
d.- The liquid radwaste system is available to drain the refueling pool to the RWST.
The essential service water system is available to e.
provide cooling water to the spent fuel pool pumproom
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coolers.
f.
The spent fuel pool and fuel transfer canals are filled to their normal operating levels.
14.2.12.1.30.3 Test Method
- a. 'The fuel pool cooling, fuel pool cleanup, and pool skimmer pumps are operated in their various modes, and pump operating data are recorded.
b.
System component control circuits are verified, including the operation of system pumps and valves on receipt of safety signals.
The ability of each fuel pool cooling pumproom cooler to c.
start when the associated fuel pool cooling pump starts is verified.
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14.2.12.1.30.4 - Acceptance Cr ter a a.
The operating characteristics of the fuel pool cooling,
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fuel pool cleanup, and pool skimmer pumps are within design specifications.
b.
The fuel pool cleanup pumps RWST suction isolation valves close on receipt of an SIS.
c.
Each fuel pool cooling pump trips on a low spent fuel pool level signal.
d.
Each fuel pool cooling pump trips on receipt of a load shed signal.
e.-
Each fuel pool cooling pumproom cooler. starts when the associated fuel pc.o1 cooling pump starts.
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E SNUPPS -wc 14.2.12.1.34 Residual Heat Removal (RHR) System Cold Preoperational Test (0-03CJCl) fus-E78/
14.2.12.1.34.1 Objectives To demonstrate the operability of the RHR pumps, demonstrate by flow test their ability to supply water at rated pressure and
. flow, and verify their response to safety signals. The opera-tion of system motor-operated valves, including their response to safety signals, are also verified.
The RWST control and alarm circuits are also verified.
14.2.12.1.34.2 Prerequisites a.
Required component testing, instrument calibration, and system flushing / cleaning are complete.
b.
Required electrical power supplies and control circuits are operational.
c.
The reactor vessel head is removed, and the water level is above the nozzles.
d.'
The refueling water storage tank contains an adequate supply of demineralized water for the performance of this test.
gooling water cynt;m is available to e.
Ti.; se...re..mu m auppl
- tcr to the RHR pumps and heat exchangers.
2 f.
The instrument air system is available to supply air to system air-operated valves.
14.2.12.1.34.3 Test Method a.
Performance characteristics of the RHR pumps are verified during discharge to the reactor coolant hot and cold loops and test recirculation.
b.
PWST and RHR system component control circuits are verified, including the operation of the RHR pumps and system valves on receipt of safety signals.
14.2.12.1.34.4 Acceptance Criteria a.
RHR pump performance characteristics are within design specifications.
h.
RHR system components align or actuate in accordance with system design to safety injection, containment isolation, load sequencing, load shed, and tank level signals.
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speed is within design specifications.
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.RHR system motor-operated valve closure times are within^ design specifications.
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v 14.2.12.1.37 Safety Injection Flow Verification (C CCE"C2) sus-Enos
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14.2.12.1.37.1 Objectives To demonstrate the operating characteristics of the safety a.
injection pumps and the centrifugal charging pumps.
b.
To demonstrate the capability of the safety injection i
pumps to provide balanced flow to the reactor coolant l
system and prevent runout flow in the cold leg and hot leg injection modes.
To demonstrate the capability of the ch'arging pumps c.
to provide balanced flow to the reactor coolant system and prevent runout flow in the boron injection mode.
d.
To demonstrate the capability of the residual heat removal pumps to provide required net positive suction head to the safety injection pumps and the centrifugal cbarging pumps.
To demonstrate that the safety injection and centrifugal c.
charging pump room coolers maintain room temperature with-in design limits.
f.
To demonstrate that associated system valve operating times are within specified limits.
14.2.12.1.37.2 Prerequisites Required component testing, instrument calibration, and a.
system flushing / cleaning are complete.
b.
Required electrical power supplies and control circuits are operational.
The CVCS is available to supply rated flow to the c.
reactor coolant system via the boron injection path, while simultaneously supplying other required loads.
d.
The residual heat removal system is available to supply adequate suction head to the safety injection and centrifugal charging pumps during required injection modes.
The borated refueling water storage tank contains an e.
adequate supply of demineralized' water for this test.
f.
The reactor vessel is available to receive water, and the temporary reactor vessel pumpdown system is operational (if
. required).
g.
The auxiliary building HVAC system is available to cool the pumprooms and verify associated pump interlocks.
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- h. _The accumulator safety injection system piping from the safety injection system to the reactor coolant system is available, and an accumulator tank is capable of receiv-ing water.
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Th^ ^^=rencnt pooling water cyctcm is available to r :. Jm cvuliu; fic;. to required pumps and heat ex-changers.
j.
The compressed air system is available to supply air to associated system valver.
.k.
The residual heat removal system hot leg and cold leg flow orifices have been sized for required flow.
14.2.12.1.37.3 Test Method The safety injection pumps are operated in the cold leg a.
flow mode to verify pump performance characteristics and to_ identify the weaker pump.
b.
The safety injection cold leg branch lines are balanced using'the weaker-s=f'ty injection pump and the balance checked with the stronger pump.
The balance is per-formed so that injection flow is maximized while prevent-ing pump runout.
c.
The safety injection hot leg branch lines are balanced, using their respective safety injection pump.
The balance is performed so that injection flow is maximized while preventing pump runout.
d.
The centrifugal charging pumps are operated in the boron injection mode to determine pump performance characteris-tics and to identify the weaker pump.
e.
The boron injection branch lines are balanced, using the weaker centrifugal charging pump and the balance checked with the stronger pump.
The balance is performed such that injection flow is maximized while preventing pump runout.
f.
Each residual heat removal pump is operated in series with the centrifugal charging pumps and safety injection pumps to verify that the residual heat removal pumps can supply adequate suction head.
g.
With each centrifugal charging pump and safety injection pump operating, pump room temperatures are allowed to stabilize, and room temperature data are recorded.
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SNUPPS-wc 14.2.12.1.37.4 Acceptance Criteria The safety injection and centrifugal charging pump a.
response times and valve operating times are within design specifications.
b.
The safety injection pump room coolers start with their respective pump.
The NPSH provided by the residual heat removal pumps c.
to the centrifugal charging pumps and safety injection pumps is within system design specifications.
d.
Safety injection cold leg, hot leg, and safety injec-tion pump flows are within design specifications.
Boron injection and centrifugal charging pump flows e.
are.within design specifications.
f.
The safety injection and centrifugal charging pump room coolers can maintain room temperature within design limits.
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14.2'.12.1.41 Containment Spray System Preopcrational Test (S43 EH013-03R:02 )
14.2.12.1.41.1 Objectives a.
To demonstrate the operation of system components, including their response to safety signals, and verify that the associated instrumentation and controls are functioning properly.
System flow characteristics in the test and simulated accident modes are also._rified.
b.
To demonstrate the ability of the pump room coolers to maintain room temperatures within design limits.
14.2.12.1.41.2 Prerequisites a.
Required component testing, instrument calibration, and system flushing / cleaning are complete.
b.
Required electrical power supplies and control circuits are operational.
c.
The refueling water storage tank contains an adequate supply of demineralized water for the performance of this test.
d.
Tcr.pcr ry piping in iaatullcd frcr the cpr?y k^2 der-t-es43d ennnac+4^nr to the rce Lut
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The auxiliary building HVAC system is available to cool the pump rooms and verify associated pump interlocks.
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The containment spray pump rooms are closed.
14.2.12.1.41.3 Test Method a.
Performance characteristics of the containment spray pumps are verified in the test mode, recirculating to the refueling water storage tank, and in the simulated accident mode diccharging to thc r^2cror vaccel.5*
b.
System component control circuits are verified, in-cluding the operation of system pumps and valves on receipt of load sequence / shedder and CSAS/CIS signals, respectively.
c.
During system operation, spray additive eductor operating characteristics are verified.
d.
During containment spray pump operation, pump room temperature data are recorded.
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J SNUPPS - WC 14.2.12.1.41.4 Acceptance Criteria a.
Containment spray pump performance characteristics are within design specifications for the tested modes of operation.
b.
Containment spray pump and valve response to load sequence / shedder and CSAS/CIS is verified, and the associated response times are within design specifica-tions.'
Spray additive edactor operating characteristics are c.
within design specifications.
d.
The containment spray pump room coolers maintain the room temperature within design limits.
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$t SNUPPS-wc 14.2.12.1.45 Control Building HVAC System Preoperational Test
( VM 3 - Gke lusvuui) 14.2.12.1.45.1 Objectives To demonstrate the capacities of the control building supply air unit,-control building exhaust fans, access control exhaust fans, control room pressurization fans, control room filtration fans, control room air conditioning units, access control fan coil units, counting room fan coil unit, and Class IE electrical equipment ac units.
To demonstrate that the control room pressurization fans are capable of maintaining a positive pressure in the control room following a control room venti-lation isolation signal (CRVIS).
The system instrumentation and controls, including the components' responses to safety ae+
jsgowsignals, are also verified.
To demonstrate that the e
ventilation to battery rooms 1 through 4 is in accordance with system design.
14.2.12.1.45.2 Prerequisites a.
Required component testing, instrument calibration, and system air balancing are complete.
b.
Required electrical power supplies and control circuits are operational.
c.
The compressed air system is available to supply air to system air-operated dampers.
14.2.12.1.45.3 Test Method The control building system fans are operated, and fan a.
capacities are verified.
b.
Proper response of system components to control room ventilation isolation signals'(CRVIS))I, safety injec-tion signals (SIS), and fire cign:Ic is verified.
c.
With a CRVIS present, the ability of each control room pressurization fan to maintain the control room at a positive pressure is verified.
d.
The air flow to battery rooms 1 through 4 is verified.
14.2.12.1.45.4 Acceptance Criteria a.
The control building HVAC system fan capacities are within design specifications.
b.
The control building HVAC system fans and dampers properly respond to CRVIS[ign.
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The control room pressure maintained by the control
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room pressurization fans is within design specifica-tion'..
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d.. The' air flow'to battery rooms 1 through 4 is in accordance with system design.
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SNUPPS-WC 14.2.12.2.6 Liquid Radwaste System Preoperational Test (SU4-HB01) 14.2.12.2.6.1 Objectives a.
To demonstrate the operating characteristics of liquid radwaste system pumps and reverse osmosis unit and to verify the operation of their. associated control circuits.
- /
b.
To demonstrate the operation of the liquid radwaste system containment is~olation valves, including their response to a CIS.
c.
-To determine by. opera tional test that the liquid system containment isolation valves ' closure times are within design specifications.
14.2.12.2.6.2 Preregnisites a.
Required component testing, instrument calibration, and system flushing / cleaning are complete, b.
Required electrical power supplies and control cir-cuits are operational.
c.
Thr errp:::nt pooling water cyc t:a is available to y vv u
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the reactor coolant drain tank heat exchanger and the reverse osmosis unit.
14.2.12.2.6.3 Test Method a.
The liquid radwaste system pumps and reverse osmosis unit are operated, and performance characteristics are recorded.
b.
The operability of the system pump and valve control circuits is verified.
c.
The liquid radwaste system containment isolation valves are operated under flow conditions, and operating times are recorded.
14.2.12.2.6.4 Acceptance Criteria a.
The performance characteristics of the liquid radwaste system pumps are within design specifications.
b.
Each pump trips on receipt of a low-level signal from its respective tank.
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14.2.12.2.7 Waste Evaporator Preoperational Test (3100:002) 544-48o3 10.2.12.2.7.1 Objectives To demonstrate the operability of the waste evaporator and its associated pumps, valves, and control circuits.
14.2.12.2.7.2 Prerequisites a.
Required component testing, instrument calibration, and system flushing / cleaning are complete.
b..
Required electrical power supplies and control circuits are operational.
c.
Th cerpenent cooling water systca is available to supyly waces L,& the waste evaporator.
d.
The auxiliary steam system is available to supply steam to the waste evaporator, The waste evaporator condensate tank and the primary e.
evaporator bottoms tank are available to receive waste evaporator effluent.
14.2.12.2.7.3 Test Method The waste evaporator is operated, and performance data is a.
recorded.
b.
With the waste evaporator in operation, a low feed inlet pressure signal is initiated, and the evaporator is verified to shift to the recycle mode.
The waste evaporator distillate pump is verified to trip c.
on a low evaporator condenser level.
14.2.12.2.7.4 Acceptance Criteria The waste evaporator process flow is within design a.
specifications.
b.
The waste c"aporator goes into the recycle mode on low feed inlet pressure.
t The waste evaporator distillate pump trips on a low c.
evaporator condenser level.
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7 AU. 8 SNUPPS Gamma and neutron radiation curveys are performed at selected points throughout the station.
Periodic sampling is performed to verify chemical and radio-chemical analysis of the reactor coolant.
14.2.10.4 Power Level Ascension After the operating characteristics of the reactor have been verified by low power testing, a program of power level ascension brings the. unit to its full rated power level in successive stages.
At each successive stage, hold points are provided to evaluate and approve test results pr.ior to proceeding to the next stage.
The minimum test requirements for each successive stage of power ascension are specified in the initial startup test procedures.
Measurements are made to determine the relative power distribu-tion in the core as functions of power level and control assembly bank position.
Secondary system heat balance measurements ensure that the indi-cations of power level are consistent and provide bases for cali-bration of the power range nuclear channels.
The ability of the reactor coolant system to respond effectively to signals from primary.and secondary instrumentation under a variety of condi-tions encountered in normal operations is verified.
At prescribed power levels, the dynamic response characteristics of the primary and secondary systems are evaluated.
System response characteristics are measured for design step load changes, rapid load reduction, and plant trips.
Adequacy of radiation shielding is verified by gamma and neutron radiation surveys at selected points throughout the station at various power levels.
Periodic sampling is performed to verify the chemical and radio-chemical analysis of the reacrt; coolant.
14.2.11 TEST PROGRAM SCHEDULE se.
a The" sequential schedule for the Preoperational Test Program is l
provided in Table 14.2-4.
The sequential schedule for the Initial Startup Test Program is provided in Table 14.2-5.
Detailed schedules for testing will be prepared, reviewed, and revised on a continuing basis as plant construction progresses.
/w.c.pp Preoperational testing is scheduled to commence approximately 18 months prior to fuel loading.
The preoperational tests are performed and sequenced during this period as a function of system turnover, system interrelationships, and acceptance for testing d ^ ^ t i " -- '
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Initial startup testing is scheduled to be conducted over a period of approximately 3 to 5 months, commencing with fuel leading.
The initial startup tests are completed as identified 14.2-12 Rev. I/I
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INSERT 1 Preoperational tests which are not performed according to the Table 14.2-4 schedule are reviewed on a case-by-case basis.
Administrative
. procadures are establishad-to ensure that all prerequisites are met
- before testing'is initiated.
Upon completion of all prerequisite tests applicable.to a system or subsystem, a documented review is c
- cor. ducted by Startup personnel to verify that appropriate documentation is available and that required crerequisite tests have been satisfactorily completed.
All deficiencies which would prevent performance of preoperational
, tests or generate negative test results are identified and dispositioned
- prior to implementation of the preoperaticnal tests.
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SNUPPS 14.2.12.3.18 Reactor Coolant System Flow Coastdown Test (S-07BB04) 14.2.12.3.18.1 Objectives a.
To measure the rate at which reactor coolant flow changes, subsequent to tripping all reactor coolant Pumpc.
ff,,, A w,,fy b.
To determine.that the reactor coolant system low-flow delay timeges,se less than or equal to the total low-flow delay timeg assumed in the safety analysis for loss of flow.
Tc determine that +h= "" der'?^1""Ce trip
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frcquency trip dclay tim c are "ithin deeign eraci-
fic tiens.
14.2.12.3.18.2 Prerequisites a.
Required component testing and instrument calibration are complete.
b.
Required electrical power supplies and control circuits are operational.
c.
The reactor core is installed, and the plant is at normal operating temperature and pressure with all reactor coolant pumps running.
14.2.12.3.18.3 Test Method Flow coastdown stabilization and loss of coolant delay-time data are recorded while tripping reactor coolant pumps.
14.2.12.3.18.4 Acceptance Criteria a.
The rate of change of reactor coolant flow is within design specifications.
b.
The reactor coolant system low-flow delay times are less than or equal to the total low-flow delay times assumed in the safety analysis for loss of flow.
Themudervuliegc trie and under4r-equency trip-dclef c.
tince are "i-tMn-design spucification w 16 Rev. J8 14.2-170 4/44 3/gy m.
-,-- - - -. ~, - _ _,
c.--
O SNUPPS 14.2.12.3.33 RCCAorBankWorthMeasurementatPower(S-07SF09)[
C 14.2.12.3.33.1 Objectives 4 To measure RCCA cr Lu sa worthf l*r
- rectejcofed A*m f4 Nf/* rod rhscrf%
l.:n:t m.
14. 2. par,y-tara7 4 12.3.33.2 Prerequisites
.:g.
Testing will be performed at 30-percent and 50-percent power with the reactor stable.
14.2.12.3.33.3 Test Method M)c jectedrool~ C*=p=!t-ef ths.
Y the change in reactivity associated with aaeh. change in "M
"CC = RCCA bmrk position.
iitilluus duLa frcr thm & cav Li ti tP cx.patcz, cc p"tc rcd :crthc.
InffRT
-)
a 14.2.12.3.33.4 Acceptance Criteria y Ejes%f ro.4~
- ' 4 Vee!*dr**' &
The rod wortlls'5re conrictent wi*h th ccccptauuc criteri/
in thc !!uc1ccr Occign % crt within tolerance values v m.
specified in vendor design documents.
0 Dropped rect-74.peakr*y &%s are. w. % N e, A h, h.rpa,4d n
vendoe dessyn docuinen&.
in Inster.f j) ro dsterm.* e heare-ter ons< reraHoy Sorn a droffect toel w'th II n
ofler control rods near ully tarWdrawn.
In sent.1 f)'progsc/reol~Dehrm*'ne lle AusdranY fewer Wlf Aaft'e en n el be t" e./anns/ faetars fy use. af 1/~ /ncors F/ux Mappihy S;rtem.
I I
I P
I v fec the C&llw ay Site Addnndur Rev. >S IL 14.2-185 2ftM 9/$4 i
)
e.
'e,..
J SNUPPS TABLE 14.2 4 (Sheet 5)
Beger-Contamment Hot Fuel T estms Test Functmed Lee's i
Pro,ere Precedures
\\
Ta
/
t t
5 5
a I
l 18 HAthal 03 Months) ( 2 Months) 10 Months)
S04PK01 125. V(Non Cass (E) de Systens F.coperatsonal Test - - - - - - - - - - - - - - - - - -
S04PN01 Instrument AC(Non Cass IE) System Prooperatend Test --------- - -- ---
un S40D01 Emeegency Lightmg System Preoperational Test=====------------
S uoF0,
~,c, A ress Syst.m Pro.oers.mnel Tes, - - - - - - - - - - - - - - - - - - _
=
$040J01 Heat Treceng Freere. Protecteon System Precoeratend Test
= '. - - - - - - -
S 04RM01 Secondary Sampimg System Preoperatend Test - - - - - - - - - - - - - - - - - -
l 5045001 Area Radiaten Womtonne Preoperational Test ---- + - - - - - - - - - = = -. - - - - - - - - - -
4 S04SC01 Seismic Montoring instrumentet.on Systene Preoperationd Test ------------ --
a 504SJ01 Dele *=d 1
$090007 Ptant Perforniacce Test
'2)
$04ACO2 Turbene Trip im -. - - -- - - - - -.- -- -.- -. -.- - -
.i
=
}
$04ACC3 Turbene Systen* Cold Test - - - -== - - - - === - -. - - -.- - - - - -. -
$04AQ01 Condensate and Feedwater O.emical Feed Preoperstonal Test---. ------- --- -- --
S O4LE 31 Oet, Wests System Preoperatenal Test - -== = - - -=== - - -- - - = - - -==. - -. -
l
$ 04L F01 Floce and Equipt wnt Drain System Preoperatenal Test ----.= = ----- ---.. -- =
l S 04A F 01 Secc,ncary vent and Drain System Freoperatonal Test ---== -. ----. -
\\
S04EB01 Cased Cochng Water System Preoperatend Test --------=--==--.--==e--
i
$090023 Electes 1 Distribution System Voltage Ver ficaten Test=======-------
=
t j
S095001 Loose Parts Monstormg System Test = = = = = -- - -.- --. - - - - -- - - - - -
LEGEND Procedure Preparation, Reeww. and Approest Testi Perf E
Test med During This Time Frame To 8. Completed j
By This Tirne NOTES: (1) Ddeted s
(2) Centmued on Table 14.24.
j May Be Performed
[,
Dunng Construction Complet on Testmg See Wolf Creek Addendum section 14.2 4.
(4) See the Wolf Creek $ste i
- Addendum, i
9 Ree.bN e
W64 fl r 'l 4
1 4
-