ML19329A991
| ML19329A991 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/09/1974 |
| From: | TOLEDO EDISON CO. |
| To: | |
| References | |
| IC-2001.00, NUDOCS 8001280739 | |
| Download: ML19329A991 (77) | |
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IC 2001.00.
Davis-Besse Nuc1cer power Station .
,;-, $6-JYb
(- Unit'No. 1 4
Instrument Calibration and Test Procedure IC 2001.00
. Instrument Calfbration Prepared by n ,u: w , d "< b D // 2/!78 Submitted by ' u. e S . i.! SYR/7N Date i Y Section Het:d Reco::randed / a. *)'/ /
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V RB Ch;tirman Date
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Approved ; 4L E O<. '
Date 7 ?" Station Superintendent
/ Station Revision No. SRB Reco =endation Superintendent's Dato
/ Approval .
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- 1. PURPOSF jh -
1.1 'to provide a procedure to be 'followed in performing calibration of
.. individuai instruments and instrument loo,p tuning.
, 2. REFERENCES 2.1 Instrumentation instruction manuals a.nd drawings which are supplied
. , . . . . . .. by the various vendors of the instrumentation, and/or Bechtel
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2.2 Functional Description of systers - supplied by Bechtel Corporation.
2.3 PP 1101.02, NSS Setpoints. .. . .
2 '. PP 1101.0,3, BOP Setpoints 2.5 Equipment Instruction Manuals supplied by various vendors, e.g. Reactor Protection System and the Turbine Generator. .
2.6 Davis-Besse Nuclear Power Station FSAR and Technical Specifications .
2.7 IC 2000.01 Test Equipment " Calibration
- 3. TEST EQUIPMENT REQUIRED 3.1 The test equipment required will vary from instrument to instrument and is to be determined from the above references .
h 4. PRECAITTIOKS AND LIMITATIONS 4.1 Precautions and ifritations for the individual instruments are generally found in the above torences.
i .
4.1 The " Safety Tagging Procedure" AD 1803.00 and TECo Safetf Manual are to be followed.
4.3 A Radiation Exposure Permit (REP) is required when working on instruments containing radioactive fluid or in radiation areas .
Observe precautions and limitations stated on the REP.
4.4 Efficient and safe operation of the stat (2n Igquires,that instru-m: ntation be properly calibrated. The person performing the calibration is responsible for determining that the calibration values are proper
, and for questioning any which he does not understand er agree with.
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. 4.5 ~
In order, to . review or to use the information for' troubleshooting and - _
recalibration, the persons performing the calibration are responsible for complete and accurate documentation of their work.
. 5. DATA si1EETS RE0111 RED l . 5.1 Data Sheets hava been developed to document instrument calibration.
In general, when there are several instruments of the same type, a specific data .
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2 IC 2001.00.0 sheet is made up for it. Also, several generic data sheets have been
, , made to use on different models or types' of instruments. Additional data sheets will be made up as deemed necessary. Thesc Data Sheets
{' cre assigned DB 100 - DB 199 numbers.
- 6. PREREQUISITES 6.1 Persons performing instrument calibration are to be qualified to per-l form the work. Qualification is determined by , the Station Superinten-dont who has control over whom is assigned this type of work. The I & C Engineer and IEC Foreman will maintain control of this on a day to day basis with any questions being resolved by the Station Superintendent.
6.2 Prior to calibrating an instre=ent which is in servic e , the appropriate operations personnel, normally the Shift Foreman, are to be notified and give permission for the work to be performed.
6.3 Prior to calibrating an instrument, the Test Equipment requirements of IC 2000.01, Tes t Equipment , are to be complied wi th.
- 7. PROCEDURE 7.1 Before an instrument is calibrated an individual file for the instrument will be created and an Instrument Information Sheet, DB 126, vill be made cut on the instrument using nameplate, specification and vendor infor-mation. In addition, a calibration data sheet vill be made out filling
( in the instrument information and the desired calibration data.
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The desired calibration data is to be obtained from' either one or more of the references in section 2, calculated from the desired system response or from one of the Section Heads or the IEC Engineer. In the case of recalibration and/or tuning, the desired value may be detensined utilizing operatienal data.
7.2 The instrument will then be ca.'.ibrated and repcired, if necessary, using the procedure detai.'.cd in the 2nstruction manual for that typn c model of instrument except when the inst.rument is a common type and the practical training received in the apprentice program or by experience has made calibration of thin type of fastrument a routine item. Examples of the latter are pressure gauges , temperature "indTestors, thermocouples and voltago .ndicators.
In the event either a manufacturer's procedure does not exist or the
-- existing one is' inadequate and tha ins,trumene is -not a routino Ftem, -<
a procedure is to be written to calibrate this specific type of instrument.-
HOTE: The procedure identification which is used for calibration will be found on the instrument infor=ation sheet , Form DB 126.
j 7.3 The "as found" and the "as left" calibration. values are to be entered on the calibration data sheet and an entry made on the Calibration and l Maintenance Record, DB 111, indicating the work done.
' . . f'Yl 7.4
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After calibration the instrument will be returned to the de_ ired cervice condition and the Shift Foreman, if appropriate, notified or the 1 instrument statu.:.
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7,5 The I6C Foreman is responsible for reviewing all enlibrations and accepting the results. Ile shall so indicate by his initials or signature under " Accepted By".
q 7.6 The I&:J Engineer is responsible for reviewing all calibrations and so indicating by his initials or signature under " Reviewed By".
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- INSTPJDIENT INF0PJMTION S!!EET Davis-Besse Nuclear Power Statios Unit No. B rvice Inst. No.
N. Start-up Sys. No.
Name of Instrument.
Location Primary Element / Tap location Cable / Tube No.
Dwg. No. P 4 ID File No.
Dwg. No. Mechanical File No.
Dwg. No. Electric'al File No.
Terminal Block Location C:ntrols Connected
,* 0 (d
% Drawing No. File No.
Instruments Connected
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Drawing No. File No.
Manufacturer _,
Supplier-Mfg.-Name of Instrument " -- -
S; rial No.
Type
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Model -
- Class Calibration Range Scalc/ Chart Range Specification Sheet No. Pago No.
General Instruction No. Tab No.
"rscedurc Instruction File No.
Calibration and Maintenance Record See Following Pages Page No.
, DB *,)1 IC 2001.00.0 8Al,IBRATION AND MAINTENANCE RECORD Davis-Desse Nuc1 car Power Statioq
- Unit No.' &
Inst. No.
A.ste: Date and initial all entries referencing the calibration data sheet page no., if applicable.
D:te Int. Pg. No. Work Performed e
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TEST SPECIFICATIG!! / DRAFT PROCEDURE /. TEST GUIDE RECORD OF REVIS10!!S AilD APPROVAL ISI SP[CIFICAil0N / DRAFT FROCEDURE / TEST GUIDE H0. TG 305 01 til[ ltMAC7JR PRCffECTION GYSTEM PRE-OPERATIONAL CALIBRATION l
'0 R TOLEIA I:DISON CO:FA:1Y
'RiPAR[D BY J. J. Carr ,
/.t L' DATE Ncerember 13, 1973 IVi[WED BY G. C. Schieck' DATE November 13, 1973 .!
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.PPROVED BY K. E. cuhrke M8 ' ' DATE November 13, 1973 I IVISION DATE APPROVED REYlS10!!
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o PAGE 1 TEST SPECIFICATION Th%'
( TS 305 01 TOLEDO EDISON D AVIS-BESSE NUCLE AR STATION .
RE ACTOR PROTECTION SYSTEM PRE-OPER ATIONAL CA LIBRATICN 10 P URPO SE
- 11 TO CALIBR ATION CHECK NON-NUCLEAR INSTRUMENTATION WHICH PROVIDES SIGNALS TO THE PROTECTION SYSTEM.
NOTE! THIS DOES NOT INCL UDE BISTA BLE T RIP PODULES ASSOCI A TE D WITH THE NUCLEAR INSTRUMENTATICN PORTION OF THE REACTOR PROTECTION SYSTEM. THIS IS ACCOMPLISHED IN TS 30101, NUCLEAR INSTRUMENTATION PRE-OPERATIONAL CALIBRATION.
- 1. 2 TO VERIFY THAT EACH OF THE FOUR RPS CHANNELS RESPONOS TO SIHULATED INFUTS FROH THE NON-NUCLEAR INSTRUMENTATION AND TO ASSURE TH AT i 1.3 THE INSTALLED EQUIPHENT AND ASSOCIATED LOGIC OPERATE AS SPECIFIEO.
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TO TEST INTEGRATED STRINGS FCR PROPER CALIBRATION AND FUNCTION. -
20 REFERENCES NUCLEAR INSTRUMENTATICN AND REACTOR PROTECTION SYSTEM INSTRUCTIOh MANUALS, EAILEY HETER COMPANY B AND W OWG. NO. LATER 2.2 NUCLE AR INSTRUMENT ATION PRE-OPERA TIONAL CALIBRATIOh TS 301 01
- 2. 3 NSS PROCESS INSTRUPENTATION PRE-OPERATIONAL CALIBRATION TG 000 11 2.4 NON-NUCLE A R INSTRUPENTATION INSTRUCTION MANUALS BA ILEY METER CO.
8 + W O W G iiO . t 01 0186 30 , 01 0187 00 , 01 0188 00 .
2.5 DESIGN SPECIFICATION 1018/NSS-14/0670 SYS T EM O ESIG N SPECIFICATION FOR bOCLEAR INSTRUMENTATION, REACTOR PROTECTION SYSTEMS.
2.6
- PL ANT FSAR (SECTION 73 l ',
27
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PLANT TECHNICAL SPECIFICATIONS 2.8 l
CR0 SYSTEM PRE-OPERATION AL C ALIBRATICN TS 330 01 2.9 REVISIOb 00 305 G1 O ATE 11-13-73 l- __ _ ____1
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- A3 E 2 P.E ACTOR PROTECTICN SYSTEM OPER ATING PROCEDUPE
,, OP 1105 02 f-3.0 TIME REQUIRED:
- 3.1 10 TEAM DAYS (2 M AN TEAM)
NOTE: TIME ESTIMATES ARE FOR TEST PROCESS TIME ONLY AND INCLUDE, WHERE APPROPRIATE, EST*; MATES FOR ESTABLISHING PLANT OR SYSTEM CONDITIONS. ESTIMAT ES ARE NOT MADE FOR ADMIhISTRATIVE RECUIREMENTS, PERSONhEL REQUIREMENTS, TIME LOSSES 00E TO EQ U IP HE NT MALFUNCTION, OR F ACTORS UNIQUE TO T4E CUSTOMER POLICIES AND ORG ANIIATION.
4.0 PREREQUISITE TESTSt 4.1 NUCLEAR INSTRUMENTATION PRE-OPERATIONAL C ALIBRATION TS 301 C1 SECTIONS 9.3.3, 9.3.4, 9.3.5, 9.3.6, ANO 9.3.7.
5.0 TEST ECUIPNENT!
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5.1
REFER TO TEST EQUIPMENT SECTION OF REF. 2.3.
6.0 LIMITS AND PRECAUTIONS 6.1 VERIFY ACCURATE C ALIBRATION OF THE DIGITAL VOLTM ETER
- PRIOR TO ANY A0JUSTMENTS.
6.2 ONLY CNE (1) CHANNEL BYP ASS KEY SH ALL BE AVAILABLE AT ANY TIME EXCEPT WHEN PERFCRMING CHANNEL TRIP BYPA SS C HEC KS.
6.3 OBSERVE ALL PRECAUTIchS NORMAL TO THE OPERATION OF HIGH VOLTAGE POWER SUPPLIES.
6.4 CONSTRUCTION OR M AINTENANCE ON THE RPS OR INTERCCNNECTED SYSTEMS
~
THAT WILL JEOPARCIIE PERSONNEL SAFETY SHOULO BE DISCONTINUE 0 WHILE TESTING IS IN FF0GRESS.
6.5 CABINETS SPCULO EE CHECKED AS POWER IS APPLIED IN CASE OF WIPING FAULTS, ETC. THAT COULD PREVENT PROPER ENERGIZING OF EQUIPMENT.
6.6
- THE FREQUENCY OF OPERATION FOR THE TRIP BRE A%ERS SHOULO NOT EXCEED 23 IN 10 MINUTES OR 30 IN ONE HOUR.
6.7
\\ OBSERVE ADDITIONAL LIMITS AND PRECAUTIONS OF REF. 2.1.
7.0 REQUIREO PLANT STATUS i REVISIOb 00 305 01 O ATE 11 73
PAGE 3 7.1 -
gs COLD SHUT 00WN 80 PREREQUISITE SYSTEM COND ITIONS t 81 -
ALL ASSOCIATED NUCLEAR AND NON-NUCLEAR INSTRUMENTATION INSTALLE0.
8.2 ALL CONTROL RO C ORIVE MECHANISMS DEENERGIZED.
CONSULT REF. 2.8 FOR PETHOD OF DISCONNECTING POWER TO CROMS.
, 8.3 ALL CR0 BREAKERS INST ALLED AND OPERATIONAL.
8.4 ASSURE CORRECT WIRING OF ALL FIELD CONNECTED SIGNAL WIRES.
8.5 POWER AVAILABLE TO T HE NI/RPS CA8INE TS.
9.0 TEST HETH00 NOTES E ACH INDIVILdAL MODULE SHALL BE PROPERLY CALIBRATED AND IN NORMAL OPERATING CONDITION PRIOR TO THESE TESTS. IN
( THE EVENT TPAT ANY MODULE IS FCUNO TO BE-GUT OF CALI6 RATION
}-- . OR NOT FUNCTIONING PROPERLY, THAT HCCULE SHOULO BE CALIBRATED OR REFAIRE0 ACCORDING TO THE DETAILEO INSTRUCTIO NS CONTAINED II. THE PRODUCT INSTRUCTION NANUALS OF REF. 2.1.
NOTEI ONCE IT IS DETERMINED THAT THE CROH CONTROL SYSTEM BREAKERS OPERATE PROPERLY. IT MAY BE DESIRAOLE TO LEAVE THE BREAKER TRIPPED AND DETERMINE ONov TH AT VOLT AGE OR NO VOLTAGE EXISTS TO THE ASSOCIA TED UNDERVOLYAGE CCILS. THE TEST METHOD IS WOR 11E0 ASSUPING THE BREAKERS ARE ACTUALLY T RIPP E O. 8Y NOT CYCL ING THE BREAKER MECH ANISMS, SONE SMALL AMOUNT OF HECHANICAL WEA R WO ULO BE AVOIDEO.
9.1 INITI AL 70 hER TEST, ENERGIZING 880 SYSTEM
- 9.1.1 l
CHECK OUT THE SYSTEM AC AND OC POWER SUPPLIES IN ACCORDANCE WITH SECTION 4.0 0F REFERENCE 2 1. -
l NOTE! ALL REACTOR PROTECTION SYSTEM POWER SUPPLIES SHOULO BE ENERGIZED UPON COMPLETION OF THIS STEP.
91.2 ENERGIZE THE 0/P TRANSHITTEF i PRESSURE T7ANSMITTERS, AND TEMPERATURE TRAN!MITTERS Ih ACCORD ANCE WITH REF. 2.4 AND 2.1
, 9.2 L CHANNEL CALIBRATION NOTE: THE FOLLOWIhG STEP S APOL Y TO E ACH PROTECTION ' SUBSYSTEM UNLESS SPECIFICALLY STATED CTHERWISE. TEST SEQUENCES MUST B E REVISION 00 305 01 OA TE 11 73
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PAGE 4 REPEATED FOR ALL SUBSYSTEMS.
-, 9.2.1 rs CONSULT REF. 2.2 FOR CALIRR ATION AND TRIP SETPOINTS OF THE NUCLEAR INSTRUPENT ATION O VERPOWER, PO WER/IMB AL ANCE/ FLOW , AND POWER /PUHP S BISTA ELES.
9 2.2 I CONSUL T REF. 2.1, SEC. 5.2, FOR PROCEDURES OF SETTING THE
- ' ., TRIP POINT , AND OE A C3ANOS OF ALL BISTABLES.
. 9.2.3 FLOW CHANNEL C,*4TBRATION 01-CALIBRATE THE C/P TRANSMITTERS PROVIDING RPS INPUTS IN ACCO RD ANCE WIT F REF. 2.4 AND RECORO D AT A ON D AT A SHEETS PROVIDED WITH REF. 23 (WET CALIBRATIOh PROCEDURE RECOMMENDED).
02 PERFORM SECTION 5.5 0F REF. 2.1.
03
- CONNECT THE WATER BOTTLES AND PNEUMATIC CALIBRATOR (SEE REF.
ITEMS 02A AND C29) TO THE LCOP A FLO W TRANSHITTER SUPPLYING T INPUT TO THE RFS CHANNEL BEING CALIBRATE 0.
04 PUT INPUTS FROM 0 TO 100 PERCENT FLOW INTO THE FLOW TRANSHITTER AND VERIFY TH4 T THE SOUARE ROO T EXTRACTOR HETER READING AND SOUARE ROOT EXTRACTOR VOLTAGE OUTPUT ARE CORRECT.
05 REH0VE WET RIG AND PNEUM ATIC C ALIBR ATOR FROM THE LOOP A
FLOW TRANSMITTER AND CONNECT THEN TO THE LOOP B FLOW
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TRA N SHIT TER .
06 REPEAT STEP 04 07 AFT E R T HE SE CH E CKS ARE COPPLETED REMOVE WET RIG AND PNEUMATIC C ALIBR ATOR 08 RESTCRE FLCW TR ANSMITTERS TO NORHAL CPERATION.
RESTORE FLOW CFANNEL TO NORMAL.
09 RECORD REFERENCE VOLTAGES, TRIP VOLTAGES AND RESET ' VOLT AGES.
9.2 4 CONTACT PONITOR CHANNEL CALIBRATICN PERFORM SECTION 5.6 0F REF. 2.1.
9.2.5 PRESSURE CHANNEL CALIBRATION 01 CALIBRATE THE r7 ESSURE TRANSHITTERS PROVIDING INPUTS TO THE '
RPS IN ACC0FCf s0E WITH REF. 2.4 AND RECORD D ATA ON DATA SHEETS PROVIDEd WITH REFERENCE 2.3.
02 PERFCRH SECTION 5. 7 0F REF. 2.1.
'- 03
. NOTE: THE SETPOINT AND OEA08ANO FOTENTIOMETERS SHOULO l 3E SET FOR A TRIP AND RESET VALUE AS FOLLOWSt
, REVISION 00 305 01 O AT E 11 73 e
1 I
PAGE 5 HIGH PRESSURE TRIP BISTABLE SETPOINT ECUIVALENT TO 2355 PSIG WHEN SETTING, SET TO A.1825 (+0 000, -0.005) VLS.
TRIPt 8.1825 # -
0 005 VOC RESET! MANUAL (HAXIMUM CEADBAND)
I LOW PRESSURE TRIP BISTA8LE SETPCINT EQUIV ALENT TO 1900 PSIG WHEN SETTING, SET TO 2.505 (+0.005, -0.000) VO C.
t i TRIPS 2.505 +/- 0.005 VOC RESETt HANUAL (HAXIMUM DEA 08ANO)
SHUTOOWN BYPASS TRIP 8ISTABLE '
SETPOINT EQUIVALENT TO 1820 PSIG '
WHEN SETTING, SET TO 1.505 (+0 005, -0 000) VOC.
TRIP 1 505 +/- 0.005 VOC RESETt HANUAL (MAXIMUM DEA 0BANC) 04
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PERFCRM AN INTEGR AS PER THE FOLLCWING ATED STRING CHECK USING A DEADWEIGHT STEFS. ~
05 CONNECT A DEADWEIGHT TESTER TO THE IPPULSE INPUTTHE OF PRESSURE TR ANSHITTER SUPPLYING THE INPUT TO THE RPS CH ANNEL BEING TESTED.
(THIS TEST WILL BE PERFORME0 ON EACH OF THE 06 LOOP A AND LOOP B PRESSURE TRANSMITTERS.)
~
PUMP 1700 PSIG TO 2500 PSIG IN SPECIFIC STEPS INTO THE INPUT OF THE PRESSURE TRANSMITTER. VERIFY THAT THE SPEC READINGS ON THE BUFFER ANPLIFIEP INPUT, BUFFER AHPLIFIER 07 OUTPLT, AND INPUTS TO THE BISTABLES ARE CORRECT.
CHEC K FOR OPERA TION OF TPE BISTABLE TRIPS.THE OUTPUT STATE L AMP ON THE BISTABLE SHOULO GO BRIGHT WHEN TRIPPE0. TH E BIST ABLES WILL TRIP A S THEIR INPUTS EXCEED OR GO BELOW T SETPOINT VOLTAGES IN THE PROPER DIRECTION (IE INCREASING OR DEC R EA SING . )
BEFOR E T A KING E ACH SET OF READINGS, DEPRESS EACH BISTABLEBISTABLE
.ST ATE. RESET TOGGLE SWITCH TO ASCERTAIN TRUE 08 REFEAT SUPPLYING STEPS INPUTS05 THROUGH TO THE RPS. 07 FOR EACH PRESSURE TRANSMITTER 09 10 RESTORE ALL PRESSURE TRANSMITTERS FOR NORMAL OPERA TICN.
~
11RESTORE PRESSURE CH ANNEL TO OPER ATE IF NOT ALREADY 00NE.
1 RECORD RE"ERENCE VOLTAGES, TRIP VOLTAGES AND RESET VOLTAGES.
9 2.6 T EMPER ATURE CH ANNEL CA LI9 RATION REVISIOh 00 305 01 OATE 11-13-73
_ PAGE 6 Ci .
PERFCRM SECTION 5.8 0F REF. 2.1.
02
( ' THE BIAS VOLTAGE SHOULO BE SET AT 7.019 +/- 0.005 VOC.
THIS VOLTAGE IS BASED ON VALUES OF C=7873 AND H=16.25.
03 THE PRESSURE S ET PO!HT (PSP) SHOULO BE SET FOR 2185 79 LOS.
! AT 619 0 F AND 1909.50 L8S. AT 602.0 F. -
i 04
, NOTE THE SETPOINT AND DEA 08AND POTENTI0HETERS SHOULO BE SET FOR A TRIP AND RESET VALUE AS FOLLOWSt HIGH T EHPER ATURE TRIP BISTABLE SETPOINT EOLIVALEN T TO 619 DEG.
WHEN SETTING, SET TO 9.895 (+0.0008 -0 005) VOC.
i TRIP s 9. 8 95 + /- 0. 0 0 5 VOC RESET MANUAL (MAXINUM DEADBAND)
PRESSURE /TEMPEFATURE TRIP BISTABLE WITH TEMP ER ATURE EQUIV ALENT TO 619. 0 F.
WHEN SETTING, SET TO 6.122 (+0 050, -0.000) VOC.
TRIP 6.122 +/- 0.'050 VOC
,f RESETI HANUAL (MAXINUM DEA 0BANO) '
I s'.
WITH TEMPcTATURE EQUIVALENT TO 602.0 F.
WHEN S ETTING, SET TO 2.669 (+0.050, -0.0001 VOC. .
TRIP 2 .669 +/- 0.~052 VOC RESETt MANUAL (HAXIMUM DEA 0BANO) -
05 .
PERFORM AN INTEGRATED STRING CHECK ON THE TEHPERATURE CHANNEL USING THE FOLLOWING STEPS.
06 DISCCNNECT THE RTO WHICH SUPPLIES THE INPUT TO THE RPS CHANNEL BEING CALIBRATED.
07 CONNECT A DECA CE BOX TO THE LE ADS FEEDING THE RPS WITH THE DECADE E0X SET FOR'A RESISTANCE CORRESPCNDING TO 520 F.
08 WITH THE -PRESS / TEMP- SWITCH ON THE SIGNAL CONVERTER IN THE -TE PP- FOS IT IO N, THE SIGNAL CONVERTER SHOULO READ 5 20 F. VERIFY THIS TEMP READING AND THAT THE INPUT VOLTAGE TO THE HIGH TE PFERA TURE 3 ISTA BLE I S Z E13 VO L TS D C .
09
. SET THE DECA 0E BOX FOR A RESIST ANCE CORRESFONDING TO 5 70 F.
10
. VERIFY TH A T THE S IGN AL CONV ERTE R RE A DING IS 570 F AND THAT THE INPUT VOLT AGE TO TPE HIGH TEMPER ATURE BISTABLE IS 5 VOC.
_ REVISION 00 305 01- DA TE 11 73
PAGE 7 11 SET THE DECADE 80X FOR A RESIST ANCE CORRESPONDING TO 620 F.
12 I'
' VERIFY '.HA T THE SIGNAL CONVERTER RE ADING IS 620 F AND THAT THE HIGH T EPPER ATURE BISTABLE IS TRIPPE0 AND THA T THE VOLTAGE INPUT TO THE HIGH TEMPERATURE BIST ABLE IS 10 VOC.
CHECK EXACT TRIP POINT OF HIGH TEMPERATURE BIST ABLE.
l 13 REMOVE THE CECADE BOX AND RECONNECT THE RTO EEING CAREFUL TO CONNECT BACK TO THE CORRECT TERMINALS.
14 RESET ALL BISTABLES AND OBSERVE CHANNEL OPERATION.
15 REPEAT STEPS 06 - 14 FOR THE REHAINING CH ANNELS.
16 RECORD REFERENCE VOLTAGES, TRIP VOLTAGET AND RESET VOLTAGES.
9 2.7 REAC TOR BUILDING PRESSURE T RIP Oi VERIFY THAT 115 VAC POWER IS APPLIED TO THE CONTACT 8UFFER.
02 OEPRESS THE TEST SWITCH AND NOTE THAT THE LAMPS ARE BRIGHT.
03
' z' DEPRESS THE RESET SHITCH AND MOTE THAT THE LA tPS ARE OIM.
9.3
, REACTOR PROTECTION SYSTEN RESPONSE TIME HEASUREMENT 9.3.1 RPS TRIF RESPONSE TIHE TESTS ARE ACCOMPLISHED BY INSERTING A TEST SIGNAL A T THE INPUT OF AN INSTRUMENT CHANNEL AND TFEN VARYING THIS SIGNAL TO A POINT WHICH EXCEEDS THE SETPOINT OF THE TRIP VARIA ELE. TRIP RESPONSE TIME IS DETERHINED BY MEASURING THE TIME FROM THE POINT AT WHICH THE RPS TEST INPUT SIGNAL REACHED THE SETPOINT OF THE TRIP VARIABLE TO THE TIME OF GENERATION CF THE RPS TRIP OUTPUT SIGNAL.
9.3.2 FOR RPS TRIP ACTIONS WHICH ARE BASED ON THE HONITORING OF HORE THAN ONE VARIABLE, SEVERAL TRIP RESPONSE TIME TESTS ARE PERFORNED. THE VA RIABLE OF INTEREST IS CHANGED WHILE THE OTHERS ARE HELO CONSTANT, AND A TRIP RESPONSE TIME FOR EACH Ih0IVIOUAL VARIABLE IS HEASURED.
l l 9 3.3 l
' RPS RESPONSE TIHE HE ASUREHENTS SHOULO BE MADE USING A MULTI-
' CHANNEL RECORDER. THE RECORDER SHOULO 8E SET UP TO RECORO THE i
INPUT SIGNAL LEVEL, INITIATION OF STEP CHANGE, AND CONTACT
-q OUTPUT OF THE REAC TOR TRIP ASSEMBLY.
9.3.4 INPUT INITIATICN SHOULO BE HA0E AT THE INPUT TERMINALS OF THE REVISIOk 00 305 G1 O ATE 11-13-73
PAGE 8 RPS. USING AN APPROPRIATE CURRENT OR VOLTAGE SIGNAL.
93.5 HIGH PRESSURE TRIP Oi i INITIATE A STEP CHANGE FROM NOPMAL OPERATING PRESSURE TO
~
. 25 PSI ABOVE THE HIGH PRESSURE TRIP P02NT SETTING.
02 MEASURE AND REC 00.0 THE TOTAL DELAY TIME OF INPUT TO TH E RPS TO RELAY CONTACT OPENING OF THE REACTOR TRIP MODULE.
1 THE TOTAL DELAY TIME MUST NOT EXCEED 150 MSEC.
9 3.6 LOW PRESSURE TRIP 4
01 -
INITI A TE A STEP CH ANGE FROM NORHAL OPERATING PRESSURE TO E5 PSI BELOW TFE LOW PRESSURE TR,IP POINT e.4TTING.
02 MEASURE AND RECORO THE TOTAL DELAY TIME OF IFPUT TO THE RPS TO REL AY CCNT ACT OPENING OF THE REACTOR TRIP MODULE.
THE TOTAL DELAY TIME MUST NOT EXCEED 150 MSEC.
i 9.3.7
, PRESSURE / TEMPER ATURE TRIP 01 (A WITH T EMPER ATURE AT A CONST ANT VALUE, INITIATE A STEP CHANGE FROM NORPAL OPERATING PRESSURE TO 25 .SI BELOW THE LOW PRESSURE TRIP FOINT SETTING.
02
~
MEASURE AND RECORO THE TOTAL DELAY TIME OF INPUT TO THE RPS TO RELAY CONTACT OPENING OF THE REACTOR TRIP MODULE.
THE TO TAL DELAY TIME MUST NOT EXCEE0150 MSEC.
93.8 POWER / IMBALANCE / FLOW TRIP NOTEt THI S TRIP IS BASED ON A STEP CH ANGE FROM THE NORMAL OPERATING POINT TO ABOVE OR BELOW THE TRIP POINT SETTIbG CF ONE VARI ABLE WITH THE OTHER TWO VARIABLES HELD CONSTANT.
01 GIT H IMB AL ANCE = 6, FLOW = 100 PERCENT, INITIATE A STEP CHANGE IN POWER TO 1 PERCENT OVER THE POWER / FLOW TRIP POINT SETTIhG.
02 MEASURE AND RECCR0 THE TOTAL DELAY TIME OF IhPUT TO THE RPS TG RELA Y CONTACT OPENING OF THE REACTOR TRIP MODULE.
THE TOTAL DELAY TIME MUST NOT EXCEED 200 MSEC.
03 l LL WITH DOWER = 100 PERCENT, FLOW = 100. PERCENT, INITIATE A ST EP CH A N GE IN IMBALANCE TO i PERCENT OVER THE IMEALANCE FUNCTION OPERATING EN/ ELOPE.
l 04 L
~
CEVISIch'00 305 01 D ATE 11 73
% ~ #c n i
F PAGE 9 MEASURE AND RECORO THE TOTAL DEL AY TIME OF INPUT TO THE a RPS TO RELAY CCNTACT OPENING OF THE REACTOR TRIP MODULE.
THE TOTAL DELAY TIME MUST NOT EXCEED 200 1SEC.
(* 05 WITH POWER = 100 P ERCENT, IMB AL ANCE = 0, INITI ATE A STEP Cm NGE IN FLOW FROM 100 PERCENT TO 75 PERCENT.
06 i
MEASURE AND RECORD THE TOTAL DELAY TIME OF INPUT TO THE RPS TO REL AY CCNTACT OPENING OF THE REACTOR TRie MODULE.
l .
THE TOTAL DELA Y TIME MUST NOT EXCEED 240 MSEC.
9.3.9 '
POWER /NO. PUMPS TRIP
~
01 WITH POWER HELO CONSTANT, SIMULATE THE LOSS OF ONE PUMP.
, (THE RESPONSE TIME FOR THE POWER /NO. PUMPS IS BASE 0 ON A .
CLOSED TO OPEN CONTACT.)
02 MEASURE AND RECORO THE TOTAL DELAY TIME CF INPUT TO THE RPS TO REL A Y CONTACT OPENING OF THE REACTOR TRIP MODULE.
- THE TOTAL DELAY TIME MUST NOT EXCEED 150 MSEC.
~
9 3.10 HIGH TEMPERATURE TRIP 01 .
IMITIATE A STEP CHANGE FROM NORMAL'OPERTING TEMPERAATURE TO i
T WO DEGREES A30VE THE HIGH TEMPERATURE TRIP POINT SETTING.
02 MEASURE AND RECORD.THE TOTAL DELAY TIME OF INPUT TO THE RPS TO RELAY CONTACT OPENING OF THE REACTOR TRIP MODULE.
THE TOT AL DELA Y TIME MUST NOT EXCEED 150 MSEC.
3 9.3.11 REACTOR BUILDING HIGH PRESSURE TRIP 3 01 .
SIPULATE A CLOSED TO OPEN CONTACT.
02
- MEASURE AND RECORO THE TOTAL DEL AY TIME OF INPUT TO THE RPS TO RELAY CCNTACT OPENING OF THE REACTOR TRIP MODULE.
THE TOTAL DELAY TIME MUST NOT EXCEED 150 MSEC.
9.3.12 REMOVE ALL TEST ECUIPMENT BEING CAR 7FUL TO RECONNECT TO
, CORRECT T ERMIN ALS .
)
9 3.13
- RESTORE ALL CH ANN ELS FOR NORMAL OPERATION.
1
( 94 l
MODULE REMOV AL TEST ;
, . PURPOSE TO VERIFY THAT ALL MODULES FOR PLANT PROTECTION WILL CAUSE A TRIP WHEN REMOVED. -
i REVISIO,b 00 303 31 'O A TE 11 73 l
~.
l 1
PAGE 10 J' NOTE: ALL TEST HOOLLES SHOULO EE IN THE OPERATE POSITION. THE h- TEST TRIP LAMP CN THE REACTOR TRIP ASSEH9LY SHOULO BE DIM.
4 9 4.1 REMOVE THE POWER RANGE TEST CIRCUIT FROM THE SYSTEM AND NOTE THAT T HE TEST TRIP LAMP ON THE RE ACTOR TRIP HODULE GOES BRIGHT. 1
--- 9 4.2 REPLACE THE P0hER RANGE TEST CIRCUIT AND NOTE THAT THE TEST TRIP LAMP ON THE REACTOR TRIP MODULE GOES DIM. l 9 4.3 REFEAT THE ABOVE STEPS FOR EACH OF THE FOLLOWTNG MODULES:
POWER RANGE DETECTOR POWER SUPPLY LINEAR AMPLIFIER, 10P ION CHAMBER LINE AR A PPLIFIER, BOTTOM ION CHAMBER SUMMING AMPLIFIER
- DIFFERENCE AHPLIFIER FUNCTION GEhERATOR CONTACT NONITOR CONT ACT HONITO R AUXILI APY POW 6R SUPPLY LOOP A SQUARE ROOT EXTRACTOR LOOP B SOUARE ROOT EX TR A CTO R BUFFER ANPLIFIER (TOTAL FLOW 1 SIGNAL CONVERTER LINEAR ORIDGE
\ BUFFER ANPLIFIER (PRESSURE CHANNEL) ~
[ '
HIGN PRESSURE DIST ABLE LOW PRESSURE BISTA8LE SHUT 00HN BYPASS DISTABLE -
PRE SS/ TEMP BIST ABL E HIGH FLUX BISTAELE POWEP/IH9AL ANCE/ FLOW BISTABLE FLUX /PUPPS BIST AGL E HIGH TEMPERATURE BISTABLE CONT ACT BUFFER, RB PRESSURE TRIP SHUT 00WN BYPASS AUXILI ARY REL AY
, SHUT 00hN BYPASS KEY SWITCH 9.4.4 l REMOVE EACH HODULE IN THE SUBASSEMBLY OTHER THAN THE HODULES LISTED IN STEP 9.4.3 THE TES' 'o'P LAMP SHOULO RENAIN DIM WHETHER THE HOOLLE IS CONNECTED OR DISCONNECTED FROM THE SYSTEM l
9.5 l
THIS COMPLETES THE CALIBRATION AND TESTING OF THE RPS. INSURE ALL HODULES ARE IN T FE -OPERATE- POSITION. IF USED, RETURh THE SHUT 00WN 8YP ASS KEY SWITCH TO NCRHAL ANO REMOVE THE KEY.
r~ 9.6 k.' IF REQUIRE 0, OEENERG IZE THE RPS SYSTEM. CONSULT SECTION 4.3 0F REF. 2.1.
REVISION 00 305 01 OA TE 11 73
~
PAGE 11 10.0 DATA RECUIRED: -
)
[.13.1 INDIVIOUAL CHANNEL CALIBRATION VOLTAGES TO INCLUDE REFEDENCE VCLTAGES TRIP VOLTAGES
' RESET VOLT AGES 10 2 -
RECORD CF CORRECT OPERATION OF THE RPS INCLUDING
- 01
~
ALL CHANNELS CALIBRATED AND OPERATE IN ACCORD ANCE WITH REF. 2.1.
02 ALL CROM CONTROL SYSTEM OREAKERS OPERATE IN RESPONSE TO TRIP SIGNALS.
03 ALL CHANNEL TRIP BYP A SS CHECKS IN ACCORDANCE WITH REF. 2.1 04 '
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CHANNEL RESPONSE TIMES
~
11.0 ACCEPTANCE C FITERI A:
11 1
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THAT INSTRUMENT CHANNELS ARE CALIBPATED IN ACCORD ANCE WITH THE TEST METH00.
-( THAT ALL c1STActc TRIP SET POINTS ARE SsT IN ACC0a0ANCE WITH THE PLANT TECHNICA L SPECIFICATIONS.
- '-- 11. 3 THAT EACH CHANNEL WILL TP,IP WHEN THE PRESET TRIP POINT OF E ACH BISTABLE IS REACHED 11.4 THAT EACH CHANhEL RESPONSE TIHS IS WITHIN SPECIFICATIONS LISTED IN SUBSECTION 9 3 2
a l
l REVISION 00 305 01 O ATE 11 73 l I _ _ . _ _ . - .
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7p 0300.02 Davis-Eesse ?!uelear Power Station )
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Unit !!o.1 i
Test Procedure TP 0300.02
, , Nu=ber Reactor Pressure Instrument Pre-operational Calibration (RPS)
SUS No. 80 Record of Arrroval and C5.ances i
Prepared by Ken Brubaker . 2/1/73 '
Submitted by ^ %./ . '
. 3 //'*'d9'
. 8
/ Sectic > Head Date l
/ \
Recommended i
/ '
7/ X//-
SRC Chaip an
. -/t' / *-
Date / ~
/
approved
- ,, , , A / / A.4 . ~74,A 6
, / / / /, ,4. 4
' Station Superintendent g@* f .P/ / / /',/
Date
/ //r t Station Revision No'. SRC Recommendation Superintendent's Date Aporoval Test Completed __ _ . _ _
Test Leader -
Date - -
Recommended Section Head Date SRC Recommendation -
. , Date l
Station Superintendent's .
~
'Anproval Date
TP 300.02.0 r .
- TABLE OF CO';TC;TS 1
1 PURPOSE . . . . . . . . . . . . . . ,. . . . . . . _. .
~
1 2 TEST EQUIPl!C;T. . . . . . . . . . . . . . . . . . . . .
1
. 3 RETERENCE }!ATERIAL . . . . . . . . . . . . . . . . . . .
' 1 .
k TDE REQUIRED . ................... . .
~ 1 5 LD11TATIONS AND PRECAUTIONS . . . . . . . . . . . . . .
1
. 6 PREREQUISITES . ................... .
2
. ~7 PROCEDURE . . . . . . . . . . . . . . . . . . . . . .
5
'.8 ACCEPTANCE CRITERIA . . . . . . . . . . . . . . . . .
5 9 RESULTS DISTRIBUTION. . . . . . . . . . . . . . . . .-
- . 10 ATTAC1 DENTS: .
/
~
NONE .
O .
- . TECo .Co:pa.n.y Test Consultant._ - -
l Bl&W' Cotn' p any Cogni:: ant Engineer
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- TP 0300.02.0 1
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- 1. PURPOSE 1.1 To verify the proper performance of the reactor coolant pressure inputs
'.4, to the reactor protection system (RPS). .
1.2 To establish data for subsequent testing and troubleshooting.
1.3 To verify operation of computer hardware and software associated with l instrument string RC-2.
- 1.4 To verify the proper performance of the reactor coolant low range pressure instrument string RC 2A5 - (details later)
' NOTE: This procedure only covers the RCS pressure to the RPS. The RCS pressure to the SFAS will be checked in TP 2400.24.
- 2. TEST EQUIPMENT .
2.1 Dead Weight tester, accuracy of at least 1% Equip. No.
'2. 2 Voltmeter, accuracy of at least 0.01% Equip. No.
- 3. REFERENCES 3.1 Drawings 3.1.1 P&ID M-030, Rev. 6. Reactor Coolant Systen sA
\LF 3.1.2 Bailey Meter B556802C Page 4 Logic, File No. 896
- 3.1.3 Bailey Meter E8047534C Analog Logic Drawing, File No. 446 3.1.4 Bailey Meter D80465390, 41C, 43C, 45C External Connection Diagram, File No. 743 3.1.5 Bailey Meter D8047548C, SOC, 520, & 54C 880 System Cabinet Layout,
- File No. 742 -
- 4. TIME R?:: QUIRED
~4'.1 ~ Td6 Men;- 3 Days, one Shif t.per day. _ -
t - -
- 5. LIMITS AND PRECAUTIONS - None
~
6.. PREREQUISITES -
_ T _ _ ,
A -.--
6.1 Instrument String RC 2 Installed, Instrument Piping and Wiring Completed.
! Verified E Date l
. 6.2 'RPS Modules are calibrated. ,
Verified c; .6.3 NNI Modules are calibrated Verified. .
6.4 RPS. Cabinets are energi:cd. Ver'ified'
4
- 2 TP 0300.02.0 e
6.5 NNI Cabinets are energized Verified 6.6 Instruments are energized in string RC-2 -
Verified 6.7 855 Computer in operation Verified
{
6.8 Verify Calibration of the following instru=ents from I & C records:
FT-RC2A1 Loop 2 Hot Leg -
Verified t FI-RC2A2 Loop 2 Hot Leg Verified PRS-RC2A2 Loop 2 Hot Leg NR Pressure Verified FI-RC2B1 Loop 1 Hot Leg , Verified
- PT-RC2B2 Loop 1 Hot Leg Verified PRS-RC2B Loop 1 Hot Leg NR Pressure Verified PIC-RC2 Pressurizer Heater Controller Verified 6.9 Verify the following control switches are in the off position and tagged in accordance with AD 1803.00, Section 7.
. Verified HIS-RC2-1 Prescurizer Spray Valve Verified' HIS-RC2-2 Pressurizer Heater Verifted HIS-RC2-3 Pressurizer Heater Verified HIS-RC2-4 Pressurizer Heater , Verified HIS-RC2-6 Pressurizer Prassure Relief Valve Verified HIS-RC2-5 Pressurizer Heater - Shutdown Panel Verified HIS-RC2A Preascrizer Heater Verified HIS-RC2B Pressurizer Heater Verified HIS-RC2-9 Pressurizer Heater - Shutdown Panel Verified S 6.10 Verify t'r.e following prescure indicating controller is in the manual position, set for zero output, and tagged in accordance with AD 1803.00,
. - ~Section-3. _
PIC-RC2 Pressurizer Pressure Verified
- 7. PROCEDURE -
_ T _ _ .
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Perform this procedure in conjunction with TP 0350.07 (Computer Input verifi-cation) for startup system numbers 64 and 80.
7.1 Verification of PT-RC2B1 Instrument String Calibration
- 7.1.1 Normal operation is pressurizer pressure control inputs come from PT-RC2A1 RPS Channe.1 "1", but can be selected by a plug on the selection panel (location Channel 2, cabinet 2, row 6) to come from PT-RC2Bl. RPS Channel "3". This test will be made with FI-RC2B1 then PT-RC2A1 and the plug vill be left 'c 5. 3 PT-RC2Al position.
- 3 ,
TP 0300.02.0 f 7.1.2 Select the pressurizer pressure control inputs from PT-RC2B1 by the plug on the selection panel.
Verified
,- g*
7.1.3 Close the manifold inlet valve at FT-RC2Bl.
VerLfied' I
7.1.4 Connect the pneumatic pressure tester to PT-RC2B1 manifold test tap. Vary the inputs and record the following readings.
Tolerance t 16.~0 PSIG, t 2001G7 CTRM CTR31 PIC-RC2
- PRESSURE BUFFER INPUT C0!!PUTER PT.
PI-RC2B1 P-722 P-RC231 PRS-RC2B MEASURED VARIABLE A11P INPUT RPSD2- -
3-4 VOLTS DC W An enn .
DSR ACT DSR ACT PSIG DES 7. ACT % DSR ACT
% PSIC PSIG PSIG PSIG 1780 1780 0 1.000 10 1780 2100 2100 2100 28 5.000 50 2420 2420 2420 100 9.000 90 f.
- Time Delay ,
. Alarms "RC Leop 1 HLG Press" & CFr P 723 DSR @ 2055 psig decreasing Actual psig DSR @ 2255 psig increasing Actual psig 7.1.5 Close manifold test valve, disconnect pneumatic pressure tescer.
Leave manifold inlet valve closed at PT-RC2Bl.
Verified ,
- 7.2 Verification of PT-RC2A1 Instrument String Calibration.
7.2.1 Scicct the pressurizer pressure control inputs from PT-RC2A1 by
- the plug on the selection panel. Verrfiee,-
I 7.2.2 Close the manifold inlet valve at PT-RC2A1.
L Verifie'd l
7.2.3 Connect the pneumatic pressure tester to PT-RC2A1 manifold test tap. Vary the input and record the following readings:
- s e
. 4 TP 0300.'02.0 Tolerance: 16 psig, 200 mV
~
, INPUI COMPUTER PT. CTRM PRESSURE BUFFER- CTRM PIC-RC2" PT-RC2A1 P 730 P-RC2A1 PRS-RC2A2 AMP INPUT RPSC MEASURED VARI-1EAD CORRt 3-4 VOLTS DC ABLE DSR ACT DSR ACT Y. PSIG PSTC PSIG PSIG PSIG DSR ACT 'DSR 7. ACT 7.
10 1780 1780 1780 1.000 0 I 50 2100 2100 2100 5.000 28 90 2420 2420 2420 9.000' 100
- Time Delay Alarms -
"RC Loop 1 HLG Press" & CPT P 731 )
DSR G 2055 decreasing Actual psig j DSR 0 2255 increasing Actual psig ,
l 7.2.4 Close manifold test valve, disconnect pneumatic pressure tester.
Leave manifold inlet valve closed at PT-RC2A1.
Verified-7.3 Verifiedcion of PT RC2A2 In'strument String Calibration..
7.3.1 Close manifold inlet valve at PT-RC2A2.
. Verified 7.3.2 Connect the pneumatic pressure tester to PT-RC2A2 manifold test tap. Vary the input and record the following readings:
4 Tolerance 16.0 psig i 200 mV 2REbSURE BUEEER INPUI PT-RC2A2 COMPUT' i R FI. P729 AMP INPUT RPS A-2-3-4 HEAD CORR: P-RC2A2 VOLTS DC 7 ,_
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a -
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10.
178JL 1760 1.000
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., 50 * '2100 2100 5.000 90 2420 2420 9.000 7.3.3 Close manifold test valve, disconnect pneumatic pressure tester.
Leave manifold inlet valve closed at FI-RC2A2.
t 1 , Verified
! 7.4 Verification of PT-RC2B2 Instrument String Calibration.
I l
N w-e 5 TP 0300.02.0 I
7.4.1 Close manifold inlet valve at FT-RC2B2. .
( h Verified' 7.4.2 Connect the pneumatic prepeure tester to PI-RC2B2 manifold test
! tap. Vary the input and record the following readings:
I ' ***
Tolerance 'i '16.0 psig, i 200 mV
.! INPUT PT-RC2B2 COMPUTER Pr. P 721 p 34 HEAD CORR: P-RC2B2 VOLTS DC
% PSTC DSR PSIG ACT PSIG DSR ACT 10 1780 1780 1.000 50 2100 2100 5.000 90 2420 2420 9.000 7.4.3 Close manifold test valve, disconnect pneumatic pressure tester.
Leave manifo1.d inlet valve closed at PT-RC2B2.
Verified 7.4.4 Remove Tags installed in sections 6.9 and 6.10.
? Verified 7.5 Verification of PT-RC2A5 Instrument String Calibration.
7.5.1 Later 7.6 Notify the Shift Foreman of test completion and that all RC2 pressure transmitters arc out of servica and that pressure control was left selected from PT-RC2A1.
Verified
- 8. ACCEPTANCE CRITERIA
.'E~ ~ .-
-S.1' TM in'otrument strings itsted-below have operated properly and arc. cali-brated within a tolerance of + 2% (t 16 psig, i 200 mV) of full range.-
. . Step
_PT-RC2A1 ~ '
7.2.3 ..
. . PT-RC2A2 - -
-? '- 7.3.2 *
. PI-RC2B1 -
- 7.1.4
. PT-RC2B2 ' 7.4.2 ,
Test Leader Date
-8.2 Reactor Coolant System pressure control input can be selected from either h PT-RC2A1 or PT-RC2B1, Sections 7.1 & 7.2.
,,,, t,,,,,
3,lg - - - -
I & C Engineer Date
.__ ~_ _ .
o ,- -
6 TP 0300.02.0
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8.3 'RC2A5 - later
- 9. RESULTS DISTRIBITTION ,
BW Site Operations Manager Date
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TEco Mechanical Engineering Date 1
A "For Information Only copy of the completed procedure will be sent to:
,i Bechtel Corporation. .
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TP 0300.04 Davis-Besse Nuc1 car Power Station Unit No. 1 Test Procedure TP 0300.04 I .
- Reactor Coolant'Flov Instru=cntation Pre-Operational Calibration S.U. System No. 80 Record of Approval and Changes Prepared by W. licree, K. Erubaker, J. Orkins Jan. 29, 1973 Submittcd by ? O ,-.ws - ? 0 / 5......... Y A-:El f? 71 y ,Section IIcad,' . e abf ' Date f / / e a - . -
Reconcended ( i?. 'c , . !*? ' p
, kf b'O!~' $$N' A/7.]
SP2' Chain::an vDate Approved ~. -[6 / 'J '
[/p .$ N '~ff' / 6 . Sc Station Superintendent
~
Date
/ -
Station
' Revision No. SRB Recommendation Superintendent's Date Approval
-m -
't _ . __ _
" Test Completed Test Coordinator (P. Russell) Date
_ T
_-'"=- - _
. Recommended - ,-
Section llead Date SRB Recoraandation Date Station Superintendent's Approval Date 9
. . . . . . . . . . . . . . . . . . . . . .. . ... . .. i . . .. . 4. _ , . . - . . . . . . .
,e. ,
, TP 0300.04.0
- ~
' ~
. TABLE OF COMTC;TS -
I 1 PURPOSE . . . . . . . . .. . . . . . . . . . . . . .
1
( .
.2 TEST EQUIP'!CET. , . . . .. . . . . . * . . . . . . . . 1
. 3 REFERENCE MATERIAL. . . .. . . . . . . . . . . .
.i 1 4 TDfE REQUIRED . . . . . .. . .. . . . . . . . . . . 1 .
5 LU!ITATIONS A'ID PRECAUTIO;iS . . . . . . . . . . . .. . 1
- 6 PREREQUISITES . . . . . .. . . . . . . . . . . . . . 2
. 7 PROCEDURE . . . . . . . . ,. . . . . . . . . . . . . . . 2 8
ACCEPTANCE CRITERIA . . . . . . . ' . . . . . . . . .
10 9 RESULTS DISTRIEUTION. . . . . . . . . . . . . . . . . 10 10 ATTAC10!ENTS:
i -
Transmitter - RPS Channel Table - TECo Sketch t.
4, ,
TECo Company Test Consultant B&W Company Cognizant Engineer - - - - -
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- 1 TP 0300.04.0
- 3. " PURPOSE
(
The purpose of this test is'
. 1.1 To verify the proper performance and calibration of the Reactor Coolant Flow .
Instrumentation. -
1.2 To establish data for subsequent testing and troubleshooting.
1.3 To verify computer harduare and software associated with RC System Flow Instrumen-tation.
NOTE: This procedure includes flou inputs to the RPS in addition to the guidelines of TS 0300.04.
- 2. TEST EOUIPMENT_
Equip. No.
-2.1 Decado Resistance Box (4), accuracy of at least 0.1%. Equip. No.
Equip. No.
Equip. No.
2.2 Differential Pressure Indicators (2), min. range 0-700"11 20. Equip.. No.
Equip. No.
( Equip. No._
2.3 Digital volt /ohn meter, accuracy of at least 0.1%."
O REFERD!CES 3.1 hs30004 RC Flow Instr. Pre-op Calibration .
~
3.2 PP 1101 02 Plant Setpoints 3.3 Drawings 3.3.1 Bailey Meter Co. ; D8047539C, 41C', 43C, 45C (E:<tcrual Con tection Diagrams)
,.3.3.2 Bailey Meter Co.; D804754SC, 500, 520, 54C (880 System cabinet L.;yout) -
-T _. ..
.~ ~
.3.3.3 ~ Bailey Meter Co.;,B556802B (Logic) Pg. 17, 18 & 19 ,
'3.3.4_ Baileyh!eterCo.';C804759SB(SelectionPane).
Outputs)
. . ~
3.3.5 Bechtc1; P&ID M-030
~3.4' ICS, NNI and RPS Instruction Manuals, Bailey 3.5 Rosemount Temperatute Resistance Tables
- 4. ' TIME RF0t! IRED 4.1 Two men, four days, one shif t per day.
~
- 5. LIMITATinNS AND PRIT.At:TTONS .
5.1 Verify the following ICS Itand/ Auto Stations are on hand control nna tagged .in ,
accordance with AD JS01.00. .
. _ -.L. : . .
2 TP 0300.04.0 Verified 5.1.1 Reactor Demand '
Verified gs Feeduater Demand #1 5.1.2 Verified 5.1.3 Feeduater Demand #2 -
Verified 5.1.4 Main F. W. Valve #1 Verified 5.1.5 Main F. U. Valve #2 Verifies 5.1.6 Startup F. W. Valve #1 Verified 5.1.7 Startup F. W. Valve #2
' 6. PREREOUISITES 6.1 Instrument String RCl installed, instrument piping and wiringVerified completed.
Date
., Verified .
6.2 NNI Modules calibrated. .
Verified 6.3 NNI Cabf. nets are energized. i 6.4 Instruments are energized. (Inst' ement
~
r String RCl) Verified Verified
- 6.5 RPS Cabinets art energized.
Verified 6.6 ICS Cabinets are energized.
TP 2400.18, TP 2400.19, TP 2400.20, TP 2400.21
( 6.7 (RC Temperature Instrument Strings) ccepleted.
Verified _ . . ,
verified 6.8 855 Computer in operation. ,
I 6.9 Verify the calibratIion of the following from 1&C records:
FT-RCIA1 Loop'2 Hot Leg Verified Verified FT-RCIA2 Loop 2 Hot Leg Verified FT-RCIA3 Loop 2 Hot Leg Verified FT-RCIA4 Loop 2 Hot Leg Verified FT-RClB1 Loop 1 Hot Leg Verified FT-RC1B2 Loop 1 Hot Leg Verified
- FT-RClB3_ Loop 1 Hot Leg "~'~-"
Verified FT-RC1E4 Loop 1 Hot Leg Verified r FI-RCIA Loop 2 Hot Leg Flow Verified _
FI-RClB Loop 1 Hot Leg Flow Verific,d
-RC Total Flow FRS-RCl -
- 7. PROCEDURE Verify system operation, calibration ans tol.cecce Verifi6at0by' t made inserting test signals, by measuring, simula*.iq recording, the parameters of the primary compenent.
comparing data against the desired signals.
/ Normal operation is for flow signals from FT-RCJ Al (" Loop 2"-RPS Channelbut "1")can and5*
FT-RClB1 (" Loop 1-RPS Channel "1") being sent to FY-RCl for " Total Flev," 1"- li selected to conc from FT-RCIA2 (" Loop 2"-RPS Channel "2") and 7f-RClB2 (" Loop This t Channel "2") by FPS Selectic.n Panel plug, located in RPS channel .i-2-6-1.RPS-ScleC' I C;-
will be made using FT-RCIA2 and FT-RClD2, then FT-RCIAL and FT-RC1Bl.
Panel Plug will be'1 cit in its normal operating jack at the end of this terC.
m.
d -
l
i TP 0300.04.0 3
- Noreal operation Sr tc=perature compensation signals is from TT-RC3Al through US-RC3A to FY-RC1/. and TT-RC3D1 throu;;h US-RC3B to FY-RClB.
b Perform t.nis test in conjunction with TP 0350.07, Computer Input Verification, for Startup Systems 64 and 80.
7.1 Disconnect leads from TE-RC3Al in R;I Cab.1-5-3, torninals 15,16 & 17,18.
- Verified
- /
7.2 connect Decade Box to terminals 15,16 & 17,18 which is the input to TT-RC3Al.
Verified
~
7.3 Place HS-RC3A in the TT-RC3Al position. Verified 7.4 Adjust Decade Box to the equivalent of 6090F ( Ohms),,uhich corresponds to a 1.000 C.F. Temp. comp. for RC Flow. Verified 7.5 Disconnect leads from TE-RC3B1 in NNI Cab. 1-5-3, terminal's 19,20 & 21,22.
Verified 7.6 Connect Decade Box to terminals 19,20 & 21,22 which is the input to TT-RC3Bl.
Verified 7.7 Place HS-RC3B in the TT-RC3B1 position. Verified
\
7.8 Adjust Decade Box to the equivalent of 609 F ( Ohms), which corresponds to a 1.000 C.F. Temp. comp. for RC Flow. Verified 7.9 Verify' that " Loop 2" & " Loop 1" RC Flow, control inputa,come from FT-RCIA2 and FT-RC1L2 by Selection Panel plug connected to "Subassemb3y A' (Channel "2") -
RC Flow D/P, NNI (RPS - Chan. 2-2-6-1). Verified 7.10 Verify the 'l Loop 2" and " Loop l'* RC Floe, computer inputs, .coce from FT-RCIA2 and FT-RClB2 by Selection Panel plug connected to " Subassembly A" (Channel "2") -
RC Flow D/P, Computer (RPS - Chan. 2-2-6-1). Verified 7.11 Close 1:1 and 1:2 valves at FT-RCIA2 and FT-RC1B2. Verified 7.12 Connect a D/P Indicator to FT-RCIA2 and another to FT-RC1B2 test taps. Vary in~put"and recoW.the fol p ie:= -- - -
liOTE 1: 'Differen tials are to be applied to both transmitters simult'ancously as both feed RPS Channel "2". _ _
TOLERANCES:
' '~..
' 15.4 MPP11 for 0 to 180 i:PPH; + 4.'8 MPPH for 0 ~ to' 160 MfPJI; 12.7 MPPH for 0. co 90 MPPil; i 2.4 MPPH for 0 to 80 MPPH; i 30.0 "H2 O for 0 to 1000 "H 2O FT-RCIA2 FT-RClB2 C0:1PUTER CRT COMPUTER CRT COMPUTER CRT CO I i'R CRT D/P D/P F-728 (F-RClA2)
H F-723 (F-RClD2) F-735 (F-RC17.-%? F-734 (F-RC1Bd
(. " 11 , 0 MPPH MP'It "H20, "II20 DES. I ACT. DES.
. -"H
. ,9_0 -
.=.-... .v........_ __ _. . _ m_,::-
ACT.
,:.= . m _ ., . - - -
DES.
2 .:. u.i.
ACT. DES. , ACT.,
i 72.377 8.0 72.4 72.377l8.0 l 72.4 j
- 361.835 361.835 40.0 40.0 361.9 1
g 361.9 l
, . ... .....1-.s.- . 1 m '
. 4 TP 0300.04.0
--1 COMPUTER CRT CTRM F1-RCIA CTRM F1-RC' FT-RCIA2 FT-RC1B2 C0!TUTER CRT LOOP 2 FLOW LOOP 1' F1 C'.!
F-732 (F-RCIA) F-I727 (F-RC1B)
'O D/P D/P UH IfP
)/
" ITPH 12bH
" 112 0 "H20 DES. ACT. DES. fc7 J DES. l ACT. DES. ) ACT. . _ _ ______; m ,,._
8.0 8.0 8.0 8.0 72.377 72.377 l ,
40.0 40.0 361.885 361.885 40.0 l 40.Q 72.0 7,,2. 0 72.0 651.393 651.393 72.0 l FT-RC3A2 FT-RC1B2 CTRM FRS-RC1 '
- COMPUTER CRT D/P D/P TOTAL FLOW F-715 (F-RC1)
"H20 "H20 MPPH MPPH DES. l ACT. DES. ACT.
. 72.377 72.377 16 16 l 361.885 361.885 80 80 )
~
( 651.393 651.393 144 144 O
7.12.1 Decrease input to Pf-RCIA2 to check alarm set point of FAL-RCIA (low RC Flow " Loop 2"). Desired 438.93 "H 2O D/P = 62.3 MPPH.on FI RCIA.
. Actual
, Alarm Crt/typer
~ -
. NOTE 2? Per'foin stcys 7.12.2_ynd+12= 3 hitanco'usly *
~
7.12.2 Decrease input to FT-RC1B2 to chech alarm set point of
~
FAL-RC1B( low RC Flott " Loop 1") __ .
Desired 438,.93 "H2 D D/P-= 62.3 ITPH on _ _ ".
Acttral -
FI-RC1B Alarm Crt/typcr ~
. . 1 7.12.3 Check alarm set point of FT-RCl (Lou RC Total Flow)
Combination of stcps 7.12.1 and 7.12.2 Desired 12512Pl! on FRS-RC1 Actuni Alarm Crt/typer
, r.
7.13 Close test valves, disconnect D/P indicator from FT-RCIA2. Leave l K1 and R2 valves 0 instrument closed, and open equalir.ing valve.
.' Verified i~
~ju
~ . . .
- *
- l 5 TP 0300.04.0 i 7.14 Close test valves, disconnect D/P indicator from FT-RClB2. Leave K and K valves 0 instrument closed, and open equalizing valve.
y 2 Verified f,
7.15 Change " Loop 2" and " Loop 1" RC Flow, control inputs, from FT-RC11.2 and FT-RClB2 to FT-RCIAl and FT-RClB1 by Selection Panel plug connected to "Sul sembly B" (Channel 1) - RC Flow D/P, NNI (RPS - Chan. 2-2-6-1)
I Verified l
7.16 Change " Loop 2" and " Loop 1" RC Flow, conputer inputs, from FT-RCIA2 and FT-RC1B2 to FT-RCIAl and FT-RClB1 by Selection Panel plug connected to " Subassembly B" (Channel 1) - RC Flou D/P, Computer. Verified Verified 7.17 Close 1:1 and K2 valves at FT-RC1A1 and FT-RClBl.
7.18 Connect a D/P indicator to FT-RCIA1 test taps and another connected
- to FT-RC1Bl. Vary the input and record the following:
KOTE.3: Refer to NOTE 1 and tolerances in stcp 7.12 C01TUTER CRT CO}$' UTER CRT COMPUTER CRT 7 NClAl FT-RC1B CO>TUTER CRT
, D/P D/P F-729 (F-RCIA1) F-722 (F-RClB1) F-735 (F-RCIA-1) F 734 (F-RC1B-1)
( "hoO "li q0 "!! 20 MP?H MPPH "H90
~
DES. g ACT. ,_ DES _._j ACT. DES. ACT. DES. I ACT. .,
377 72.'377 8.0 ! 8.0 72.4 72.4 361.8S5 40.0 40.0. 361.9 361.9 361.885 .
72.0 651.4 651.4 651.393 _651.393l72.0 l The following portic_n of this.,ter.t is to verify that the interlock connected to, _ l HS-RC7 vill select the proper' temperature signal with .a loss of~RC Flow in either -
j
" Loop 2" or " Loop 1":
- 7.19 Disconnect leads from TE RC4A1 in NNI feb.1-5-4, teminals 2 a Ver1fied - 9 1, 2 & 3, 4. -
7.20 Connect Decade Box to terminals 1, 2 & 3, 4 which is the j input to TT-RC4A1. Verified I l
7.21 Place HS-RC4A1 in the TT-RC4A1 position. Verified j,
7.22 Adjunt Decade Box (TT-RC4A1) until a reading of SSO F
- k is indicated on TI-RC7A. Verified 7.23 Disconnect leads fron TE-RC4n1 in MNI Cab. 1-5-4, terminals 10, 11 & 12, 13. Verified l
1 .
... . . s .
6 TP 0300.04.0
- 7.24 Connect Uccade Box to terminals 10, 11 & 12, 13 which is the (s input to TT-RC4Bl. Verified 7.25 Place HS-RC4B1 in the TT-RC4B1 position. Verified 7.26 Adjust Decade Box (TT-Rd4B1) until a reading of 560 F is indicated on'TI-RC7B. Verified 7.27 Place HS-RC7 (T(av) controller seicetor) in the "T(av) Unit" position. TI-RC7 indicates 570 F. Verified 7.28 Lower the differential on FT-RCIAl until FAL-RCIA (low RC Flow " Loop 2") comes on. ~
Desired 438.9 " H 2O Verified 7.29 Verify that HS-RC7 indicates " Loop 1" selected and TI-RC7 indicates 560 F. Verified 7.30 Attempt to select " Loop 2" and " Unit" on HS-RC7. Verify that HS-RC7 reenins on " Loop 1" and TI-FC7 remains at 5600F.
Verified 7.31 Decrease the differential on FT-RC1B1 until FAL-RC1B (low RC Flow " Loop 1") comes on. Verified
(- Desired 435.9" H 2O 7.32 Verify that HS-RC7 can select " Loop 1", " Loop 2" or " Unit"
, and that TI-RC7 indicates 560 F, 580 F and 570 F respectively.
Leave HS-RC7 in " Unit" position. ,
Verified 7.33 Increase the differential on FT-RCIAl until FAL-RCIA (low RC Flow " Loop 2") clears. Verif,ied 7.34 Verify that HS-RC7 indicates " Loop 2" selected and that TI-RC7 rr. ads 5800F. Verified 7.35 Attemp't to select " Loop 1" and " Unit" on HS-RC7. Verify
~
that '
HS'RC7 r'ecain'-en s " Loop _y" swd T&R97wecains at 580 F.
- Verified _ - -
7.36 Rcr)ove Decade Box fron NNI Cabinet 1-5-4, terminals 1, 2&3, 4 '
and connect leads from TE-RC4A1 to terminalst 1, 2 & 3, 4 in NNI cabinet 1-5-4. -
-"_ Verified -
-7 7.37 Remove Decade Box from NNI Cabinet 1-5-4,.tcrain'als 10, 11 & 12, 13 and connect leads from TE-RC4B1 to terminals 10, 11 & 12, 13 in NNI. cabinet 1-5-4. Verified' Check temperature compensation of RC Flow as follous:
c' - 7.38 Adjust differentials on FT-RC1B1 and FT-RCIAl until the
' follouing, indicates 60 MPPl!. Verified TemperatureCoupensationis1.000b.F.atthispoint.
- .o '
7 TP 0300.04.0 1
Record Values:
('
MPPH MPPH FI-RCLA FI-RCl3 Computer Points- .
FTPH 1TPH F-728 (F-RCIA1)
F-722 (F-RClB1)
ITPH MPPH F-732 (F-RCIA)
F-727 (F-RClB) 7.39 Decrease the Decade Boxes simulating TE-RC3B1 and TE-RC3Al -
to the equivalent of 5600F ( ohms TE-RC3A1) and
(
ohms TE-RC3B1). This corresponds to a correction factor of 1.045 and the below values should be 62.7 FTPH. .
Record Values: .
FI-RCIA FTPH FI-RCl3 MPPH .
.' Computer Points:
1TPH MPPH F-728 (F-RCIA1)
F-722 (F-RClB1)
MPPH ITPH F-732 (F-RCIA)
( F-727 (F-RClB) ohms Increase the Decade Boxes to the equivalent of 620 F (
ohms TE-RC3B1). This corresponds to a O.7.40 TE-RC3A1)
- and (
correction f actor of 0.987 and the below values should be 59.2 MPPH.
/
Record Values:
FI-RCIA 1TPH
'~
FI-RCl3 ITPH Computer Points: '
MPPH FTPH F-728 (F-RCIAl)
F-722 (F-RClB1)
F-732 -(F-4:GlA) ITPH ITPH _
F-727 F-RClB) 7.41 Close test valves, disconnect D/P indicator from FT-RClBl.
valves at instrument closed, open ~ --
equalizing
__ Leave K1 and K2 .
Verified - -
. valve. .
t 7.42 Close, test valves, disconnect D/P indicator from FT-RCIA1.
Leave K1 and K2 v'alves at instrucent closed, open equalisinn Verified valvo.
7.43 Rcturn the Decade Boxes siculating TE-RC3Al and TE-RC3B1 to the resistance equivalent to 609 F. Sec steps 7.4 and Verified 7.8 for ohn value.
Verified 7.44 Close the K1 and K2 valves at FT-RCIA3.
, j i
8 TP 0300.04.0 .
1 -
7.45 Connect a D/P indicator to FT-RCIA3 test tapc., Vary input, record the following:
p
(
s- .
. U t
FT-RCIA3 COMPUTER CRT
" 112 0 F-731 (F-RCIA3)
DES. ACT.
72.377 8.0 361.885 40.0 651.393 72.0 7.46 Close test valves, disconnect D/P indicator. Leave K1 and K2 valves closed and open equalizing valve. Verified _
7.47 Close the K1 and K2 valves at FT-RCIA4. Verified 7.48 Connect a D/P indicator to FT-RCIA4 test taps. Vary
( input and record the following: -
FT-RCH4 COMPUTER CRT
" 11 0 2 F-730 (F-RCIA4)
MPP11 DES. ACT.
72.377 8.0 361.885 40.0
._ _ 651.393 j
72.0 ,. _
7.49 Close test valves,-disconnect D/P indicator. Leave T
~
~7-'
K1 and K2 valves at instrunent closed and open equalizing valvo. ' Verified 7.50 close K1 and K2 valves at FT-RC1B3.
7.51 Connect D/P indicator to FT-RC1D3 test taps. Vary input and record the following:
\
t t
. ,~ '
f*
- '
- 9 TP 0300.04.0 l
TT-RClB3 COMPUTER CRT
" 112 0 F-724 (F-RClB3) -
( MPPl!
DES. ACT.
=
'72.377 8.0 i 361.885 40.0 .
651.393 72.0 7.52 Close test valves, disconnect D/P indicator. Leave K y and K2 valves
~
at instrument closed and open equalizing valve.
Verified 7.53 Close K1and K 2valves at FT-RClB4. Verified 7.54 Connect a D/P indicator to FT-RClB4 test taps. Vary
, input and record the following:
, 'FT-RClB4 COMPUTER CRT
\
c, "H O F-725 (F-RClB4)'
2 FTPH DES. ACT.
72.377 8.0
(
361.885 40.0 651.393 72.0 1
1 7.55 Close tast valves, disconnect D/P indicator. Leave K and K 2
valves at instrument closed and open equalizing' vaTv51 '
Verified 7.56 Recove Decade Box from NNI cahinct 1-5-3, terminals 13, li & 17, . _ _
_ 18. Connect Icads frca TE-RC3Al to terminals 15, 16 &-17, 18 .
in cabinet 1-5-3. Verified 7.57' Remove Decade Box from UNI cabisc', 1-5-3, terminals' 19, 20 & 21,
- 22. Connect 1 cads from TE-RC3B1 to terminals 19, 20 & 21, 22 in cabinet 1-5-3. Verified 7.58 Incure " Selection pancl" plugs for RC Flow D/P, computer -
l i
, and control are sc1ceting the normal operating transmitter.
l Verified
~
h
~
, . . . ... .r. . . . . ,
10 - TP 0300.04.0 -
1 4 ACCEPTANCE CRITERIA i
8.1 The instrument string checks without' tethperature compensation have performed
- satisfactorily and within the tolerances specified in step 7.12.
I Test Coordinator Date
. I & C. Engineer Date l:
? 8.2 The tecperature compensated values are within + (2.7 MPPH) + (Differences between points in step 7.38) of the value given in steps 7.39 and 7.40.
Test Coordinator Date 4
- Date I & C Engineer
- 9. RESULTS DISTRIBUTION 9.1 B & W Site Operations Manager Date 9.2 TECo Mechanical Engineering Date 9.3 A "For Information Only" copy of the completed procedure will be sent to:
(
Bechtel Corporation O
e g
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p . #j ..
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- /[ , . .
j _ D}ORTI) TP 0300.04.0 STSnr4 GEllERSTOR P.
(D:}DJ 10) . . .
g ( .) .
. O l
()7'
'.' Dc Gi/-'
Fr-RC2St PT-nC231 '
l-gfg C/5, PT-RC2t%
PT-ncEa3 @'iRDRRUI 4 -
I '
(Gld C,) -
QuGDRPJ47 2 TE-CCCR33 (TG-GCSRI * ' / ,
ra-n00!MI, i c crz-GCUna - -
.(34W [Q
" T- n0101 FT nctnB .
, "Q[FT-nc taaFT-nct34 ... .. .
. NZ-t .
N,- g -NI-3 .
,'~.
NT-5 /0
~.
a l' QN \
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nunmon 4 '
\
c I tG-2 1G-4 '
US-c o o ,
. L,..- G l.
FT-ncial Fr.nc133
'N, p.D I c -[7 8 -
(. '
PT-RCl33- FT-RCIL4 QU.[nDL[c' uj a O R PS c/w re-acsan> i .m . _' ' , '
.6 GW 2 QU.p,6 ROUT S 'iE RC30 6 '" ;-i.'iE33g .,)'
(USW N' PT RC2Q cp7.RC202 .'
FT-G00GD) ~, I l PT-RC204 .
,, v P S TU O M G G U ER P.TO R [
.' .t (G(DJIS) . .
_g -
.. __ gl- ;..-
Teco tew -
nencToa parneciou sys. sFe.s Res Cl-lP. NUEL CllRN;JEL PRE 5SO.ar:. N
_ T_E_i49- U L'.C!.w P O. .:.m2' a,' .CL C'.r i
, l' ,
8- PT- RCP,G?. TE RCGC2'- NI:QE=6 PT:Rt 2Be FT-TZu c
. . .FT- RC I F 2 A PT-RC EA2 TE-RC?ad NI-l.,iE-5 PT-RC2n4- 1:T-Rc u.
., ! FT-nc1:-
3 D PT- RC2B1 TE-RCSD4 NI-4;[GC ,
FT- RC 2GS py- Rci r
/
FT-tac t 'J D 4.'
C PT-RC2R1 - TE-RCCG2 ux-3';142-7 PT- ac 2R'l Fr-IsC U ;
er nc.n
. .. . 1 V .
'?. .
TP 2400.21 f l
l Davis-Besse Nuclear Power Station-( Unit No. 1 )
i
~
- Test Procedure TP 2400.21 .
Reactor Temperature Instrumentation Pre-Operational Calibrction Instrument Strings RC 3A & 33
~
S.U. System No. 58 Record of Aoproval and Changes j 1
Prepared by W. Merce and D. Sonin ' December 5. 1972 l s'
Submitted by' 2 'e's.-/ t i- .: db 7!ZN V I /Section Head Date Recommended /_Fm . '*^
- - - r9 -
U 7 /t/?
Date C/'
% U-SRB Chairman T
C Approved n . 9' 'i. .n,.7;
./.. : 7 :. ' '.:- l '
Station Superir.tendent ,
Date
(. '
Station' Revision No. SRB Reco=mendation Superintendent's Date
. Approval
.i
-~ -
- Test.Clipleted -
Test Leader Date
- ? .
. -,' , Recommended .
- - . _, _ c
. Section Head Date
' SRB Recommendation Date Station Superintendent's Approval
- Date l .
- l. .
TP 2400.21.0 TABLE OF CONTENTS -
b, -
s . - -
I 1 PUPJOSE . . . . . . . . . . . . ... .. .. .. .. 1 .
2 TEST EQUIPMENT. . . . . . . . . .. .. . . . . . ..
1
- I . 3 REFERENCE MATERIAL. . . . . . . ... . . . . . . .. 1-t k TDZ REQUIRED . . . . . . . . . ....J. . . . ..
1 5 LU!ITATIONS AND PRECAUTIONS . . .. . . . .. . . ...
1 6 1
. PREREQUISITES . . . . . . . . . ........... -
. 7 PROCEDURE . . . . . . . . . . . . ......... ,. 2
~
1.
8 ACCEPTANCE CRITERIA . . . . . . .'.......... 3 ,
9 RESULTS DISTRIBUTION. . . . . . ............
6 10 ATTACDENTS: ,
NONE g .
t .
TECo Cohpany-Test ConsiltsT:t .~- -
, B&W Company Cognizant Engineer r -
~
l
_ T -
-]
. - .~
i % .s ., .
I . .
l l .
i e
1 TP 2400.210
,1. PURPOSE The purpose of the test is:
1.1 To verify the instrumentation is calibrated in the Reactor Temperature
- Instrument String to the RPS.
1.2 To establish data for subsequent testing and troubleshooting.
2 1.3' To verify station computer hardware'and software associated with instru-ment strings RC 3A and 3B.
- 2. TEST EQUIP'EhT 2.1 Decade Resistance Box, accuracy of 0.17. or better. Equip. No.
2.2 Digital volt /0hm Meter, accuracy of 0.17. or better. Equip. No.
3 REFERENCE MATERIAL ,
3.1 Drawings 3.1.1 P&ID M-030, Rev. 8, Reactor Coolant System
- 3.2 PP 1101.02 Plant Setpoints ,
3.3 Rosemount Temperature / Resistance Tables ,
3.4. NNI Instruction Manuals (Bailey)
- 4. TIMEREQUIRIJ 4.1 Two I&C Mechanics, one day, one shift per day plus one man (four hours) to record data in sections 7.2 and 7.4 ,
l
_, 5. LIMITATIONS AND PRECAUTIONS None .
~ '
- 6. PREREQUISITES .
l 1
6.1 Instrumedt string RC 3A and 3B installed and wiring completed.
- Verificd Date - -
6.2 .The applicable release packages are complete, the systems have been green tagged to TECa and there are no deficient items to prevent the con-duct of the test.
' Verified ' Date_
6.2 NNI cabinets are energized. Verified Date l
l l .
TP 2400.21.0 2
6.3 Instruments in string RC 3A and 3B are energized.
1 Verified Date T_ w t
6.4 853. Computer in operation. . Verified Date 6.5 Verify calitration of the following instruments from I&C records:
i TT-RC3B2 Loop 1 Hot Leg Verified Date TT-RC3B4 Loop 1 Hot Leg Verified Date TT-RC3A2 Loop 2 Hot Leg ' Verified Date TT-RC3A4 Loop 2 Hot Leg Verified Date
~
~
6.6 FK: 900.01 Scheme Verification Procedure has been completed on applicable sections of $US 58.
~
Verified Date
- 7. PROCEDURE -
7.1 RTD and computer input verification (RC 3B2 and RC 3B4)
,- 7.1.1 Disconnect two of same color leads on TE-RC3B2, check computer ,
point T-721 for open. .
Date_
([) .
Verified 7.1.2. Reconnect leads on TE,-RC3B2. Verified Date 0
7.1.3 Disconnect two of same color leads on TE-RC3B4, check computer -
point T-722 for open.
Verified Date 7.1.4 Reconnect leads on TE-RC3B4. Verified Date 7.1.5 RTD elements and lead wires are to be checked for continuity, resistance and ground from cabinet to element at the terminal on
~
. the input side of the cabinet terminal block. The following checks
- =
_ -will be made on RID's dssociated with one channel at 'a time.
7.1.6 Disconnect RTD leads.in channel 1-1-10-4-6, 7, & 8, 9, TE-RC3B2
.'and TE-RC3B4. _,_
l i
. Chann. 3-1-10-4-6, 7 & 8, 9.
t TE-RC3?.2 TE-RC3B4 *From Rosemeu..
Ohms
- Ohms Ohms
- Ohms Temperature /
[-
Leads DES ACT Leads DES ACT Resistance l
I Tables 6 to 7 6 to 7 7 to 8 7 to 8 i
6 to 9 6 to 9
- ~
- 3 TP 2400.2LO RC-3B2 Ground Check Leads 7 to 10 DES Infinite Ohms ACT Ohms RC-3B4 Cround Check Leads 7 to 10 DES Infinite Ohms ACT Ohms 7.2 Verification of Instrument Strings RC 3B2 and 3B4 Calibration.
7.2.1 Using a resistance decade box, connect to channel 1-1-10-4-6, 7, & 8, 9 TT-RC3B2.
Verified Date 7.2.2 Refer to RosemotntTemperature/ Resistance Table for output from TE-RC332 corresponding to 5300F, 5700F, and 610cF and record in the following table.
7.2.3 Varydecadeboxandtakethefollowingrbadings.
0 Tolerance: 11 F and i 100 mV Decade Box Computer Pt. 722 RPS Module-Signal Converter Loc.-Channel 1-2-4-6 TT RC3B2 Jack'- Teno. Out (J 3. 0)
TT-RC3B2 DES "F ACT OF DES VDC 1 ACT VDC
' Ohms - 530 F 530 +1 Ohms = 570 F 570 +5 Ohms = 6100F 610 -
+9 .
O 7.2.4 Disconnect decade box and reconnect leads channel 1-1-10-4-6, 7 & 8, 9 TT-RC3B2.
Verified Date 7.2.5 Using a resistance decade box, connect to channel 3-1-10-4-6, 7, & 8, 9 TT-RC3B4.
Verified Date 7.2.6 Refer to Rosemount Temperature / Resistance Table for output from TE-RC3B4 corresponding to 5300F, 570 F, and 6100F, and record in the following
....able.,
t 7.2.7 ~ ' Vary decade box and take the following readings. ,
i Tolerance: 1,10F and 100 mV . .
~
Decade Box Computer Pt. 722 RPS Module-Signal Converter l Loc.-Channel 3-2-4-6 TT RC3B4 Jack - Temo. Out (J3.0)
TT-RC3B4 DES "F ACT OF DES VDC l ACT VDC Ohms = 5300F 530 +1
. Ohms = 570cF 570 +5 Ohms = 6100F 610 +9
, 4 TP 2400.21 0 9
7.2.8 Disconnect decade box and reconnect leads clunnel 3-1-13-4-6, 7, & 8, 9 TT-RC3B4.
Verified Date
~.
7.3 RTD and Computer Input Verification (RC 3A2 and 3A4).
7.3.1 ' Disconnect two of same color leads on TE-RC 3A2, check computer point T-731 for open.
Verified Date 7.3.2 Reconnect leads on TE-RC 3A2. Verified Date 7.3.3 Disconnect two of same color leads on TE-RC 2A4, check computer point T-730 for open.
Verified Date 7.3.4 Reconnect leads on TE-RC 3A4. Verified -
nate 7.3.5 RTD clements and lead wires are to be checked for continuity, resistance and ground from cabinet to element at the terminal on the input side of the' cabinet terminal block. The following checks will be made on RTD's
. associated with one channel at a time.
7.3.6 Disconnect RTD leads in channci 4-1-10-4-6, 7 & 8, 9 TE RC 3A2 and channel. 2-1-10-4-6, 7 & 8, 9.
t .
- FromRosemount Temperature / Resistance Table' .
O* TE-RC3A2 TE-RC3A4 Ohms Ohms Oh=s 0h=s ,
Leads DES
- ACT Leads DES
- ACT 6 to 7 6 to 7 7 to 8 7 to 8 6 to 9 6 to 9
- . - RC-3A2 Cround Check Lecds 7 to 10 DES Infinite Ohms ACT Ohms _
-r .
RC-3A4 Cround Check Leads 7 to 10 DES Infinite Ohms ACT. Ohms
. 7.4 Verification of Instrument String RC 3Aa and 3A4 Calipetion.
~ _ ,
7.4.1 Using a resistance decade box, connect channel 4-1-10-4-6',.7 & 8, 9 TT-RC 3A2. '
. Verified Date 1
7.4.2 Refer'to RosecouncTemperature/ Resistance Table for output from TE-RC 3A2 corresponding to 5300F,~5700F, and 610 F, and record in the following
-table.
7.4.3 Vary decade box and take the following resdings. -
t
> * . ' .. 5 .
TP 2400.21.0 e
0 Tolerance:11 F and i 100 mV Decade Box Computer Pt. T-731 RPS Module-Signal Converter Loc.-Channel 4-2-4-6 T-RC3A2
- Jack - Te=o. Out (33.0)
TT-RC3A2 DES *F ACT "F DES VDC ACT VDC
- Ohms = 5300F 530 +1 i
0 +5
__0hms = 570 F 570 Ohms,=.610 F 610 +9 1
7.4.4 Disconnect decade box and reconnect leads channel 4-1-10-4-6, 7 & 8, 9 TE-RC3A2.
Verified Date -
7.4.5 Using a resistance decade box, connect to channel 2-1-10-4-6, 7 & 8, 9 TT-RC3A4.
Verified Date 7.4.6 Refer toRosemount Temperature / Resistance Table for output from TE-RC 3A4 corresponding to 5300F, 5700F, and 610 F, and record in the following ,
table.
(-
7.4.7. Vary decade box and take the following readings.
Tolerance: 11 F and i 100 mV Decade Box Computer Pt. T-730 RPS Cabinet-Signal Converter Loc.-Channel 2-2-4-6 4
T-RC3A4 Jack - Temo. Out (J3.0)
TT-RC3A4 DES OF ACT "F DES VDC ACT VDC Ohms = 530 F 530 &1
. Ohms = 5700 F' 570 +5
- - c - Ohms = 5100F
_ 610 +9 .. _
. 7.4.8 . Disconnect, decade box and reconnect leads channel 4-1-10-4-6, 7 & 8, 9 TE-RC3A4. . ._- _ T _-"'"_ ._ "_ ~<
~
Verified Date -
8.
ACCEPTANCE CRITERIA l 8.1 - The temperature inputs to the RPS are calibrated within a tolerance of i 1 F and i 1;.0 mV, steps 7.2.3, 7.2.7, 7.4.3, and 7.4.7.
( Test Leader
) Date L.
' ~
I&C Engineer Date
- k
A 4-.'. .- '
6 TP 2400.2LO 9 RESULTS DTSTRIBUTION s
~ Date
~
B&W Site Operation Engineer
.TECo Hechanical Engineering Date
- g. .
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- 9 4
. e END ,
TP 2400.25.
Davis-Besse Nucicar Power Station
~
Unit No. 1 .
s -
Test Procedure TP 2400.25
! Containment Pressure to SFAS & RPS Pre-operational Calibration S.U. System No. 48, 58 Record of Approval and Changes -
<<ctI LeJL.df Prepared by Paul tussell 2/15/73 Submitted by 'W k ke - f/e</7.3
/
S'ectio Hea / Date Recoimrended ' k[,[ / ' 8 0' . ') .$
/- SRB haitman' ~ ' Datd
(
Approved
.. (( [-( 2'/El' -
d7 -
' Station Superintendent Date Station Revision 1.0. . SRB Recommendation " Superintendent's Date Approval Test Completed
-Test Coordinator (P. Russell) Date Recommended - __ _
- Section Head - Date .
SRB. Recommendation Da t. a -
Station Superintendent's -
Approval __ ,_
Darc e r ,-- w
1 TP 2400.25.0 t
p -
' 1. PURPOSE i
j 1.1 To serify the~ prop 6r'perfor nee'off the' Containment Pressure inputs to the j S.F.A.S. and R.P.S. for proper performance. *
[ 1.2 To verify computer hardware and sorrware associated with the above instrument string.
i * *
- 2. TEST EQUIPMENT .
2.1 Pneumatic pressure tester, min. range 0-60 PSIG, accuracy 2: 1%.
Equip. No.
- 3. REFEREMCE MATERIAL 3.1 P&ID H-029B Containment & penetration room Sht. #2 Bechtel q
- 3. 2.5 S.F.A.S. Technical manual ,
3.3 R.P.S. Technical manual 3.4 Instrument information sheets 4 ~
855 computer list.
,Q . 3.5.. .. . .. . . . . ..-........:_. - _ . _ . . . . _ _ _ . . . . . _ . .
- 4. TIME REQUIRED
. 4.1' 2 men, 2 shi,~ts, 1 shift per day . .
- 5. LIMITS AND PRECAUTIONS ,
5.1 Prior to checking any channel in the ti.F.A.S the containment pressure bistabic trip lights on the other channels must indicate the untripped state i.e. light, out 5.2 Prior to checking any channel in the R.P.S, the containment pressure bistables in the other 3 channels must indicate the untripped state. - ,
- 6. PREREQUISITES 6.1 Instrument piping and wiring completed. .
. -~ Verified (Containment Pressure) Date 6.2 S.F.A.S. modules calibrated Verified 6.3 ,
S.F.A.S. cabinets energized Verified 6.4 S.F.A.S. channels are not bypassed Verified 6.5 855 computer in operation Verified h(
6.6 Verify the calibration of the following instruments from I & C records:
- e. a ,m,w- Spee+
2 TP 2400.25.0 PT 2000 Containment Pressure to SEAS Ch #1 Verified .
PS HI11-2 Containment Pressure - RPS Ch #1 Verified pg PI 2000 Containment Pressure (CTRM) Vc eified PI'2000 Contain=cnt Pressure (SFAS Cabinct) Verified PSH 2000B Containcent Pressure Verified i
PT 2001 ' Containment Pressure to SFAS Ch #2 Verified PS NI 15-1 Containaent Pressure RPS Ch. #2 Verified PI 2001 Contain=cnt Pressure (CTRM) Verified l PI 2001 Contain=ent Pressure (SFAS cabinct) Verified i .PSH 2001B Containment Pressure Verified
- PT 2002 Containment Pressure to SFAS Ch #3 Verified PS NI 15 Containment Piessure RPS Ch #3 verified
. PI 2002 Containment Pressure (CTRM) Verified PI 2002 Containment Pressure (SFAS cabinet) Verified
.PT 2003 Containment Pressure to SFAS Ch #4 Verified PS NI 15-3 Cont'ainment Pressure RPS Ch #4 Verified PI 2003 Containment Pressure (CTRM) Verified PI 2003 Containment Pressure (SEAS Cabinet) , Verified
- 7. PROCEDURE Perform this procedure in conjunction with TP 0350.07 (Computer Input Verification) for Startup System Nos. 48,58 and 59.
7.1 ~ Verify in the S.F. A.S. Cabinets that either: . _ - . . --
'( - 7.1.1 Containment pressure trip bistables are' reset on all 4 channels.
Verified
((g 7.1.2 Incident icvels 1, 2, 3 and 4 output modules (68 total)
. are blocked.
. . Verified 7.2 Verify in the R.P.S. that either:
7.2.1 All control rods are tripped and control rod testing will not be performed Verified, or
.- ~ 7.2.2 Containment pressure contact ~~ ~
.baffers are reset. .
Verified
~
'! .7 .' .
Ba all 4 channels,.
7 3 ', Verification,of Containment Pressure Inputs to Channel #1 * -
l ~
7i3.1 Place. Test T' rip Bypass swifch in ~S.F.A.S. Channel #1 to
~
l i
" Containment Pressure" position. Verified 7.3.2 Place Channel Bypass switch in R.P.S. Channel #1 in " Bypass" position. -
Verified 7.3.3 Close manifold inlet valve to PT-2000 & PS-HI 15-2. Verified
~
c,~' 7.3.4 Connect pneumatic pressure tester to 'the ' test '
tap of PT-2000 & PS-NI 15-2. Verified
.7.3.5 Vary the pneumatic pressure tester and take the following readings and record:
3 1r 49uu.za.v
.' Tolerance: 0.9 P.S.I.
INPUT TO CTRM COMPUTER PT. P-314 C0!? UTER PT.P-696 PT-2000 PI-2000 PT-2000 PSH-2000 B ARO .*
- CALC ** DES PRESS PRESS. P.S.I.A. DESPSIAlACTPSIA DES PSIA l ACT PSIA l18.4 PSI:
r j 0 ATMOS ATMOS ATMOS ACT
! 30 30 30 CRT 54 54 54 TYPER SFAS CABINET C0YPUTER PT.P-895 CONTACT BUFFER PI-2000 PSH-2000A 1-1-5-14
- i 3.75PSIG DES PSIA lACT PSIA DES 138.4 PSIA DES t g,nhSTC*
- No Tolerance
. 54 TYPER TYPER
\
d ** Baro. Pressure (Barometric Pressure) is the barometric reading converted to PSIA at the time of the test. Calc. Pressure (Calculated pressure) is the pressure to be applied by the test instrument to obtain the reading in the 3rd column. Applies to all following tables. , ,
Close manifold test tap, disconnect pneumatic pressure tester.
~
7.3.6 Leave PT-2000 & PS-NI 15. 2 manifold inlet italve closed.
Verified 7.3.7 Reset Containment Pressure Bistable in S.F.A.S. Channel #1 and return Test Trip Bypass to " Operate" position.
Verified
~ ._ ~
7.3.8 Reset Containecntiressure contact buffer in R.P.S. channel
~
~
- 1 and return Channel Bypass to " Operate" position.
Verified
~
-~
_~ _
7.4 VERIFICATION OF CONTAINMENT PRESSURE INPUTS TO CHANNEL #2 - f-7.4.1 Re-verify that steps 7.1 and 7.2 arb still satisfied.-
! . Verified l 7.4.2 Place Test Trip Bypass switch in S.F.A.S. Channel #2 to
" Containment Pressure" position. Verified
$ 7.4.3 Place Channel Bypass switch in R.P.S. Channel #2 in
" Bypass" position. Verified 7.4.4 Close manifold valve to PT-2001 & PS-HI 15-1. Verified
g Ar 44vu.4J.v 7.4.5 Connect pneumatic pressure tester to the test tap of PT-2001 & PS-NI 15-1 Verified 7.4.6 Vary the pneumatic pressure tester and,take the following readings and record:
Tolerance: ! 0.9 PSI,,
CTRM COMPUTER PT. P-315 COMPUTER PT. P-699 INPUT TO PT-2001 PI-2001 PT-2001 PSH-2001 DES fAhg p ,
P.S.I.A. DESPSIAlACTPSIA DES PSIA l ACT PSIA l 18.4PSL AEOS ATMOS ATMOS ACT O
30 30 20 CRT 54 54 54 TYPER SFAS CATTNET COMPUTER PT.' P-898 CONTACT BUFFER PI 2001 PSH-2001A 2-1-5-14
- No Tolerance DESPSIAlACTPSIA DES !38.4 PSIA DES .
ATHOS ACT TRIP i
. 54 TYPER TYPER
( .
7.4.7 Close manifold test tap, disconnect pneumatic pressure tester.
Leave PT-2001 & PS-NI 15-1 manifold inlet valve- closed.
~
Verified -
7.4.8 Reset Containment Pressure Bistable in S.F.A.S. Channel #2 and return Test Trip Bypass to " Operate" position. ~
Verified 7.4.9 Reset Containment Pressure Contact Buffer in R.P.S. Channel #2
, and return Channel Bypass to " Operate" ' position.
,) Verified 4
- l l
1
TP 2400.25.0 5 .
'.. . j l
7.5 VERIFICATION OF CONTAIRCNT PRESSURE INPUT TO CHANNEL #3 h -
7.5.1 Re-verify that steps 7.1 and 7.2 are still satisfied.
Verified 7.5.2' Place Test Trip Bypass switch in S.F.A.S. Channel #3 ,
to " Containment Pressure" position.
- Verified 1 7.5.3 Place Channel Bypass s91tch in R.P.S. Channel #3 in ,
" Bypass" position Verified 7.5.4 Close manifold inlet valve to PT-2002 & PS-NI 15-4. Verified 7.5.5 Connect pneumatic pressure tester to the test tap of PT-2002 & PS-NI 15-4 ' Verified 7.5.6 Vary the pneumatic pressure tester and take the following readings and record:
. Tolerance: 0.9 P.S.I.
INPUT TO CTRM COMPUTER PT.P-316 CONTACT BUFFER PT-2002 PI-2002 PT-2002 3-1-6-14 j
A hg p ,
P.O.I.A. DESPSIAlACTPSIA DES ?SIA l ACT PSIA DES l4 S 0 ATMOS ' ATMOS ATMOS TRIP 30 30 30 CRT
.' .54 54 54 TYPER SFAS CABINEI
- No Tolerance PI-2002 -
. DESPSIAlACTPSIA
._ ~
'ATM0'S .
~
-. 30' _
54
- l. / -
'7.5.7 Close inlet test tap, disconnect pneumatic pressure tester.
l.
g,ygd{T-2002 & PS-NI 15-4 manifold inlet valve Veriffed i
- j. 7.5.8 Roset Containment Pressure Bistable in S.F.A.S. Channel #3 I
and return Test Trip Bypass to " Operate" position.
Verified
~~
- _. w
6 TP 2400.25.0 7.5.9 Reset Containnent Pressure contact buffer in R.P.S. Channel #3 and return Channel Bypass to " Operate" position.
Verified 7.6 VERIFICATION OF CONTAIR:ENT PRESSURE INPUTS TO CHANNEL #4 7.6.1 Re-verify that steps 7.1 and 7.2 are still satisfied.
. Verified 7.6.2 Place Test Trip Bypass switch in S.F.A.S. Channel #4 to " Containment Pressure" position. Verified 7.6.3 Place Channel Bypass switch in R.P.S. Channel #4 in
. " Bypass" position. -
Verified 7.6.4 Close manifold inlet valve to PT-2003 & PS-NI 15-3. Verified 7.6.5 Connect pneumatic pressure tester to the test - - - -
tap of PT-2003 & PS-NI15-3 Verified 7.6.6 Vary the pne'umatic pressure tester and take the following readings and record:
Tolerance: 0.9 P.S.I...
..(Q ,
INPUT TO CTPJi COMPUTER PT. P-317 CONTACT BUFFER l-PT-2003 PI-2003 PT-2003 4-1-6-14 l' f^hs p , ,
P.S.I.A. DES PSIA l ACT PSIADES I-SIA l ACT PSIA DES l E{.f '
O ATMOS ' ATMOS . ATMOS TRIP 30 30 ~30 CRT
.' 54 54 54 TYPER
~
l
- No Tolerance _
SFAS CABINET -
PI 2003
~ ~M DESPSIAIACTPSIA
. 9,
, 'An!OS .
l 30 -
l l
.}
l l
' ~ ~ ~
7 . TP 2400.25.0 7.6.7 'Close manifold inlet test tap, disconnect pneumatic pressure tester. Leave PT-2003 & PS-NI 15-3 manifold inlet valve closed. Verified
]'7, 7.6.8 Reset Containment Pressure Bistable in S.F.A.S. Channel #4 and return Test Trip Bypass to " Operate" position.
Verified 7.6.9 Reset Containment Pressure contact buffer in R.P.S. Channel #4 and return Channel Bypass.to " Operate" position.
Verified
- 8. ACCEpTA' ICE CRITERIA The instrument strings have performed satisfactorily and within the specified tolerance.
Test Coordinator Date I & C Engineer Date
- 9. RESULTS DISTRIEUTION TECo Mechanical Engineering -
Date B&W Site _ Operations Manager Date
( A "For Information Only" copy of the completed" procedure , vill be sent to:
/ Bechtel Corporation.
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Davis *icsrc Nuclear Fa.:er Stction Unit !;o. 1
'lcst Procedere TP 0300.22 e4
- 1:55 Haat nalence Chech Test Precedure S.U. Systen !!c. 64 Record of J.noroval ard Chnnees -
Jerry Iceses 3 A-
- 7 >'
Prepared by .
s' .
.~
Subnitted by
- se: tion !! cad Date Reco.:nended SRI Chaarran U3:0
( _ ,
Approved Station Su,2crintendcat Data
,..- Ctation Revisien So. SRD Reco :cudation Superinter. dent's Data Approval
- Test Completed l Test Leador Date i )
1 s
~
Recommended -
Section s'uad Date i
SRS Reccc=enda:ica -
Date Station Superi:itendent's Approval __
Dato O -
1
-2 .
1 TP 0S00.22.3
~
- 1. PURPOSE . -
1.1 testing.
To verif y the EPS Daily Heat Salanco Check SI 5038.02 during power escalation 1.2 To verify couputer calculated heat balance computations.
1 1.3 Provide baseline data for comparison with subsequent Heat talance Checks.
, 1.4 ,To determine the deviation, if any, of calculated loop pover, Primary versus Secondary, for reactor coolent loop flow metering instrumentation.
- 2. EOUTP~2NT 5EEDED Nonc
- 3. REFEREi:CES '
3.1 ASHE Perfor=ance Test Code for Nuclear Stoca Supply yctems (PTC 32.7 - 1c59)
~
3.2 RPS Daily Heat Dalance Check procedure ST 5058.02.
3.3 Plant Computer Specification CS-3-901 NSS-14 3.4 Reactor Coolant , Pump Flcv Test TP 200.11 k 4. TITC RCOUIRED
) ,
4.1 1 man /2 hours (at cach required peuer icvel)
NOTE: If adjustments are required to reactor coolant loop f1cu meterin;
{ instrumentation consult I&C procedure (later) for tima required.
- 5. LIMTTATICN3 AND P.ECA'rrIONS e
None
- 6. PREREGUISITES 6.1 The follouing tests have been completed.
~ -~~== ~
- 6.1.1 Reactor Coolant Pump Flow Test TP 200.11 Verified 6.1.2 Zero Power. Physics Test TP 710.01. Verified i . - -
~
~~
6.2 Reactor critical .
~ ~
Verified 6.3 Plant computer in service and final internal calibration corrections have been made. .
Verified 6.4 Reactor coolant cysten loop cnd lea fleus in the core thermal po::ct program module hav been revised to a3ree with the results of the RC Pump Flov Tost,' reference 3.4. Verified
o 2
TP 0000.22.0 f
~ 6.5 The P.eactor coolnut Pur.:p input. constact used by the computer has been i
verified as the latest value availabic. Verified l 6.6 Four (4) reactor coolant pumps in operati.on Verified ,
6.7 The necessary panel indications for this procedure are operabic and available for service. Verified
- 7. Pn0CEDURE ,
NOIE: This test moetc the requirement of the AS;'C Performance Test Code 32.1- 1969:
with the exceptien of the calculations for losses to RCP actor coolin,; vacar '
and radiation and convectica lorras. These losacs are El cov:ceo values and arc included in the calculations. Data for all tects will be taken from the c.oeputar and sor.e data recording, calculatio,s vill be donc~for each test from ST 5058.02, RPS Dailey H :st Salence Chcck, section
~
6.1~and 6.2. .
This procedura is a sencric procedure to be used during the power escalation sequence. This procedure :nst be ran at 15%, 757., 95.01%
and 1007,of full powor. This procedure ray be ran at other power levels as decarnined by the Technical Engineer.
(O ~
7.1, Estab'lish steady state as defined in referencc 3.2 section 6.1.1 & 6.2.1 at the selected pouer plateau.
7.2 cbtain data por ST 5058.02, RPs Daily heat Dalance check, sections 6.1.z.nd
. 6.2, and section 1 of Form A of this procedure. At tha same tine, initiate a compu:cr calculation of core thermal power.
j 7. 't .1 Compute the total cora ' power calculations of ST 5058.02 Forms 1.1 and 1.2.
~
7,2.2 LCo:puter individugl- lo6p picr output calculations of Ferns
'5-
.- A and B of this procedure.
7.3 -(To b4 perfor,med at,100'Lif , full. ts. uer_onlyJ From the co1cu,lations of Step 7.211 (For:s 1.2) c:mpare primary systen power and secondaty system power. If a deviation of greater than 17.
-reactor power c:tists, eniculate the individual pric:ary loop flo is (Form C of this procedure) and adjust the reactor coolant flow instru-
-- - mcutation using I1C procedura (later) and rerun this procedure at 1007.
full power. . .
i 0 -
3; , . 4
~
I .e j I
- 8. AccidrAN.1: C!!TTFP.1A TP 0800.22.0 l 8.1 Ti:e Prisury Systca !! cat Balance Chech has no acceptance criteria assec- l f.h
\
iated with it. .
8.2 The value of rer.; tor pcver eniculated in form 1.2 of ST 505S.02 c;ree I
within 12% of computer calculated v. lues. .
I Test Leader Date 8.3 The Loop 1 ond 2 hiand calculated values of the pris:ary loop heat .b'alence versus the cocondary loop heat balance agrec within 117. rea'ctor p:ner E.e ,
of ca:h other.
Date Test Leader
- 9. RESULTS DIST*.ICUTION BEU Site Operations II: nager Date TECo Me.chanical Engineering Date
(O A "For Infc. ation Only" copy of the ec picted procedure vill be sent to Ecchtel Corporation. .
I .-
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END l
t A
e' TP C3;' *:.2.. 0 Fom A PRI!!!.Ti S'.*ST:." LCO? 1 E. 2 Page 1 of 1 HEAT CAllO*CF,CIRCd 4
,- Dcte Th:o Shift Calcualted by
- 1. Data:
i 1.1 Feactor Pos.cr (7.) CII1(::I 6) CH2 (NI-5 )' CH3(NI-S) CE'* (NI-7 )
1.2 Reactor Coolant fictr (1b/hr) Loop 1 (F1-RC1D) Loop 2(FI-RCIA)
, 1.3 Reactor Coolant AT (OF) Loop 1(TDI-RC61D Loop 2 (TDI-RCGA)
Unit (TDI-RC6)
- 2. Calcult*t,iens :
2.1 P3 ge (Reactor Potice in negauctts therical) is given by: ,
PWt1 = (Leop 1 AT) (Loop 1 Flcs)7 P Ut2 = (Loop 2 4T) (Loop 2 Flow)F where F i.s a conversion constant = 1.984 10-7 >Me 0F -lb/hr P} Tdt 1 " ( )( ) 1 M
- 10-7 Ir.it = Et Pg.t2 =( )( ) 1.9P4 10-7 >Mt =- _
Ut 2.2 The loop recctor pe'icr P16-2 in percent of rated core thor:nal po::er is:
P1 " S 3t1 100 = . 100 = 7. P2 = ht.2 100 = . 100 = ,
, 2772 2T/2 2772 2772' .
2.3 The avert.;c indicated reactor power, P ., I is:
Sum of the four PR Channels = + + +
~
4 4 P1- 7,
~~.m- ,
- 3. Sumary - .
Calculated P1 = 7. '
~- '
._-~=~ _ =. -m I
Calculated P2 = - '
7.
Total P = 7. .
Indicated P =
I.
L
TP 0~~.U.22.0 Form B I Petc _ L of 1 CaLCULATIC ; CF Mill'.RY
~
SYSTE:1 LCCP UCAT EAL.'.'.:CE Gi1IC?(
Date Time Shifc
- 1. Obtain Renctor Coolant Enchalif t fre the AS:12 Steam Tabics Loop 1 Recctor Ceolant Tn Enthalpy 1:;11(P729.T722)= BTU /lba ,
Loop 1 Reactor Coolcnt TC Enthalpy HC1(P729.T717)= BTU /lbn Loop 2 Reactor Coolant Tn Enthalpy HH2 (P729.T731)= BTU /lba Loop 2 Reactor Coolant TC Enthalpy HC2 (P729,T726)=_ BTU /lbm Make-up 11ater Enthalpy IIs t (P729,T726)= DTU/lba
- 2. Calculate the loop heat rat'es, letdoun losses, and makeup addit!.cn. ~
Loop i Heat Race, l g = 11RCl(UlI1~UC1)
HRgt = { )( -
)
HRgt = ( )( ) .
HRgt = ETU/hr Loop 2 Heat Rate, HRL2
- IIRC2(Ng2 HC2 HRL2 * ( )( "
)
URL2, " ( )( )
HRL 2 = , BTU /hr Letdo::n Loss, LLD " NLD
- 497P22(EC1)
GPM LLD = ( ) (497 PZH_) ( )
GEd LLD = BTU /hr IIakeup Addition, GMU " N;.:g'497PEl(UFU)
G P_'! - - - - -
GMU " ( ) (497 PPM) ( )
GPM ,
. G BTU /hr NU =
- 3. Uslag the data above and the following formula, calculate the loop pouer, -
Ppar 1 & 2 from the primary heat balance.
PPI'I " diRL1 + LLD + K) .2.931 10-7 :c.it DTU/itr
, . , , ,~ n ,
e, .
- ~
t' arm D I TP 0300.22.0 Page 2 o f ,2_ , CALOU! W10N OF E :M/::'t SYSIE:1 LOOP itil.T BALA::C2 Cl'ICK c where 2.931 10-7 ::!: is a conversion factor from ETU/hr to !!ge and BTUTd K = heat loss to radiation and co:.vcetion Icsocs of 0.225 106 LTU/hr per loop
-un s Ppart = + + 0.225 *106 2.931 10-7
. P PRI = 2.931 10-7 P - Wt pg71 Loop 1 Pouer in (7.), P7.p = PRI - 100 = . 100 = 7.
- RATE CO2E Tli;iO~AL PU,lER 2772 P
PRI2" L2- pg + K) 2. 931
- 10~.7 m BIU/hr where 2.931 10-7 r.-It 10 a conversion factor from BTU /hr to int and ETU/hr K = heat 1 css to radiation and convectica lossos of 0.225 106 BTU /hr per loop P pg7 " + + 0.225. 10 6 2.931
- 10-7
_+
P pRI2=[ f l 2.931 10-7 P
paI2
~ }Mt P
Loop 2 Power (7.), P7.p2 " EEI
- 100 "
100 = 7.
RATE CO2E THEI'.\L PCER 2'/72 O
b D
i sO .
s .
TP C00').22.0 Torn U II .~
P ..;;c 3_ of 5 CALcut.nIc:: 07 SEcc::.e!.rt s;STF.:1 p.O LOOP E' t.T ::AL/.:.'.:S CHECK
'- Date Time Shift
- 1. C*atnin rccchiatec cnd S cc 1 Enthalpy from the A051: Ste:1m Tabic::.
SG 1-1 Feeduater Inlet Enthc1py Uri (P930,TSSM=
SG 1-1 Steam Outict Enth tlpy lisi (P931, TSP 51=
SG x 2 Fooduater Inlet Enthalpy Hp; (P935,T900)"
SG 1-2 Jter.n Outlet Enthc1py Egg, (P936,T901)=
- 2. Calculate SG heat rntes and letdeun losses. .
SG 1 Heat Rate laggt = W7 1(Hgt-HF1)
HRgg1 =( *) ( .
_ )
1Rsci = ( )( )
HR gg1 = ETU/hr
/' '
SG 2 heat rate laSG2
- WF2 CHd-H72) -
HRSG2 " C )( ,
)
HRSG2 " ( )( )
IIRSG2 = BTU /hr Letdo m loss Q = U g
- 497 PPH(Hgg)
GP4 L)=
L1 { } (497 P_Pil) ( )
GP:t .
kD= BTU /hr Mahcup Addition G;.g=W.,.y
- 497 PPM (li..g)
Grn
- %gg = (__ ) (497 P?R) ( -
) - -
GPM G:n; = BTU /hr
PE1 = Total of average powers of Loop 1 pim:ps PEI = W+ KN PE1, .
l R
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e Forn 3 II TP 0300.22.0 Page d,,,of _5 C/Jf.UtJ. TIC:: O'.' 5::CO/:).'.'n' .",YSTT.:1.
LOJJ IisliT E.*.LA::CE Ci"ICK r' PC2 = Total of eversg.c pr,.ers of Loop 2 r.u aps PE2 = ICI + IS PE2 =
4'. Using the data above and the follouing formula, calculate the reactor ccre p .ecr, .
PSEC,fromthes[cor.d-Iryheatbelance.
PSEC1 = (iia g g; + LLD + C) 2.931
- 10-7 1.St - pet DTU/hr I600 where 2.931 10-7 -p;t is the conversion fcctor from BTU /hr to :a't. .
ETU/ hr and C is tiie heat lo.sses frot., cad additions to, the acactor Coolant Sycte= t.nd the steam generators. The term in'cludes:
6 Primary System radiative and convection lossed (K) = 0.223 0 STU/hr per loop Radiation and convaction from the SG's = 0.34',.106 ETU/hr per loop Heat losses to RC? notor cooling vster =- L 0 106 g:U/hr per icep C = 3.67 10 6 UTU/hr par loop PSEC1 " (~ .-
+ + 7.34 105 ) 2.931 . 10 per loop 1000 PSEC1 = ( ) {2.931 10-7) - ( )
P SEC1 "I )~I )
PSEC1 "
W' PSEC1=
WE .
Core . Power in (7.), P73 = STC1 Ing = 100 RATED CORE I'iER:DL PC'.;ER 2772
' ' ~
~ '
F/S1 = %l PS ::C; = (11S02 - C,s + C) 2.931 10-7 :.itt -h IITU/hr 1000 PSEC + + 3.67 106 ) 2.931 10-7 2 "(
l 1000 i, , PSEC2 " ( ) (2.931 10-7) (' )
PSEC2"( )-( )
P = ;7,.;e 3gc2
l e,
e .
Form ". II TP 0800.22.0
. Pa;c 5_of 5 CALCULAnc : 0" :;r.C'/.::i!/ a* sysTc ! ,
LOW . EAT 3.*.1.::CE C1! C:t 1
- 7. O- .
l 3 c., n . s.
g =
PS EC2 - 100 _
, 100 l 2772 Core Po cr in (7), F".3 =(DATED CC/.c Iid.UU.L PC.- ca 6,2 = %
, o
$U ::!ARY:
W " %
PSEC1=
Et = %
Pynil =
o er
' =
SEC1 PPR11 PSEC2" - ,
. PpgI 2= We = %
.
- 7'
- e. PSEC2 -PPEI2 ,
DATE CALCULATED BY REVIDiED BY -
/
APPROVED BY Technical Engineer M
O e .
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? 1.0 1 of 2 111 TP 0000.22.0
- 1. Co.npleta the followin ; calculctions if it baco .cs uccesscry to deterutno
~
(' accctor Cools.nt I.oop fic:: using cl.c recults of the seccadury heat balance I calculation.
j 4
Pc , -
-.i
- 2. 93 ,,10-1 :.J-- t
-LD-K t
=
1 LI;;/hr UR-"1
- Hai - Ec1 ,
t
- - 0.225 X 10 6 DTU/hr 2.93 X 10-i j d j Ii?U/hr = W
> RC y l
t i
- 6 4
(
- -- - 0.225 x 10 tTU/hr) . gC1
( )
=:- -
(
-) = U.p ..,v.:.
(__. -
o
".RC-4
~
f -
PSEC2 + G eJ - K 2.93 X 10-/ H:t B757hr =URC2 HH2 . EC2
+ 0.225_X,1(6g7pf.nr
- 2. o.'l X 10- / K t I -
El';!/hr =W .
! - RC1 .
f ". ..
t
--i 6
( - - 0.225 X 10 1.TU/hr) k,n*,-
- . [ )
t 7
- 6 i:C2 1
+ , . .* ..Q a***
e
' 8
- TP 0300.22,i!
Forn C .
III-Pa,;e 2 of 2
/' Loop 1 Calculated Flov
.s.
Lcep 1 Indicated Flov Loop 2 Calculated Flow -
Loop 2 Indicated Flov ,
- 2. Using the calculated flou(s) above, adjust the Reactor Coolant Flow Instrum;nta-tion, using I & 2 procedurc /, ; . . ,-- , to bring Pr'iraary Syste:a Lcep Heat Balanco Calculation (s) within j- l'!. racctor power of Sece.-dary System Loop .
Heat Lalance Calculation (s).
CALCULATED LY-FIVIr..*ED BY APFaoVED BY DATE e
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ST 5058.02 Davis Besse Nuclese Power Station 3
(~ Unit No. 1 .
I Surveillance Test Procedure ST 5058.02 .
RPS I)aily Heat Balance Check S.U. System No. 64 Prepared by J. D. Isaacs . [ U /0 9 3/27/73 Submitted by C t ~u t' O d , f 5 e. . ' /7/ r'
-L -
Section !!ead . .
Date'
') '
.' . ' . vy!' '
.'>'? t: ';' 7/. ,:.- ^ v/ . .,
Recommended - '
Date O'- o' .
./ //
SRB Chairman (s- ..] / , ' ' '
Approved
'2 O ' - '((8 "
'// ' ' - '
Da t e -
- 'f
~
Station Superintendent f.' L Station
/'
Superintendent's Date i Revision _No. SRB Recot:mendation ,
Approval W
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1 ST 5058.02.0 .
- 1. OBJECTIVE
. 1.1 ' To provide a quick approximation of reactor power by calculating a pri-r-O. , mary system heat balance check using data from panel indicators or the t.- plant computer. . .
, 1.2 To provide a primary system and secondary system weighted heat balance check to verify plant computer calculations of reactor power using I data from the plant computer. .
1.3 To provide : means of checking the nuclear instrumentation indi ations against the heat balance calculations. .
- 2. REFERENCES -
4 (TS)'2.1 Technical Specification Section 4.1 2,2 Plant Computer Operators Manual SP 1105.10 -
2.3 Reactor Coolant System P&ID, Bechtel Drawing M-03U, Rev. 7.
2.4 Secondary Plant System P&ID Bechtel Drawing M-007, Rev. 7 2.5 Makeup and Purification System P&ID, Bechtel Drawing M-031, Rev. 4.
2.6 Plant Computer Input listing
- 3. REQUIRED EQUIPMENT None (
- 4. PRECAUTIONS AND LIMITATIONS 4.1 The plant should be at steady state conditions before and during the test as specified in the prerequisites'.
4.2 The weighted primary and secondary system calculation (Form 1.2) is the principal daily check of the nuclear instrumentation as specified in Tech. Specs. Section 4.1. For operation mird-tess than four (<4) RC pumps, only Sections III and V of Form 1.2 must be completed.
4.3 .1Nue Primary Heat Balance Check Form 1.1 can be used as an option to
(
-~ -
using^the Primary and Secondary Weighted.deat Balanc'e Check, Form f.2. ,[
- 5. PREREQUISITES .
5.1 The prercquisites are included in the appropriate procedure section.
- 6. ' PROCEDURE '4 6.1 Primary System' Heat Balance Check 4
This check should be used as a quick approximation of reactor power, should such an estimation be needed.
1 __-- _a. . .J
." - . 2 ST 5058.02.0
+ 6.1.1 The following prercquisites are satisfied thereby assuring steady state condition:
0
- 1. . Reactor TH and TC temperatures constant within i 1 F. .
( . . . 2. Steam Generator level constant within + 2*/..
- 3. Pressurizer level constant within i 2".
{
[ 4. Xenon at equilibrium with no Xenon oscillations,or near a minimum or maximum after a power change.
- 5. Reactor Power must be kept within i 1*/. during data collection.
~
NOII: Collection of data may be from control room indicators or the computer. Do not use data from an idle Cold Leg.
- 6. Proper TC transmitters selected for RC pump combination. .
.. 6.1.2 Complete Form 1.1 (Primary System Heat Balance Check) 6.2 Primary and Secondary SystemWeikhtedHeatBalanceCheck 6.2.1 The following prerequisites are satisfied thereby assuring steady state condition:
- 1. Feedwater Flow constant within + 30 x 103 lb/hr
' , _) -:
v 2. Control Rod Drive System in auto.
- 3. ICS in auto. (Unit toad Demand may be on hand)
- 4. }u demand constant
- 5. Pressurizer level constant within i 2".
- 6. R.C. i'ressure constanu within 20 PSIG
- 7. R.C. Flow constant within 1.31 x 106 lbm/hr 8: Steam HeaderJ.res.sure. Constant within i 10 PSIG ,
_ 'I
- 9. Feedvater temperature i.onstant within i 4 F.
1
- 10. }!akeup plus seal injecti3n flow is equaT to the letdown . --
~
. flow plus the controlled bicedoff. -
- 11. FolloUing computer points assembled as an operator special l summary per SP 1105.10:
l R795 Rea : tor Power CH1 P950 SG Inlet F.W. Pressure 1-1 R804 Rear: tor Power CH2 P935 SG Inlet F.W. Pressure 1-2 R814 Reactor Power CH3 T884 SG Inica F.W. Temperature 1-:
l
-(h ~ R820 Reactor Power CH4 T722 RCS TH Loop 1-T900 F674 SG Inlet F.W. Temperature 1-y SG Inlet F.W. Flow 1-1
- - .g,m
=
' ~
3 ST 5058.02.0 ,
T731 RCS TH Loop 2 F679 SG Inlet F.W. Flow 1-2 T717 RCS TC Loop 1 P931 SG Outlet Pressure 1-1 T726 RCS TC Loop 2 P936 SG Outict Pressure 1-2
,I O P729 RCS Pressure T885 SG Outlet Temperature 1-1
_J F615 RCS Flow Loop 1 T901 SG Outlet Temperature 1-2
, ,F619 RCS Flow Loop 2 F717 Letdown Flow J788' RCP Electric Pouer 1-1 F740 Makeup Flow J808 RCP Electric Power 1-2 T735 Makeup Temperature -
' JS28 RCP Electric Power 2-1 F782 Seal Injection Flow
~ J848 RCP Electric Power 2-2 NOTE: If computer is unavailable, data must be taken from the panel indications as listed on Form 1.2 of this procedure.
6.2.2 Perform the fellowing if the computer is available for service:
- 1. Initiate the printout of the assembled operator special log -
(Section 6.2.1) at five minute intervals for a total of five printouts. ,
- 2. ' Complete the appropriate sections of Form 1.2 (Primary and Secondary System Weighted Heat Balance Check) using data from the computer printout.
NOTE: For operation with all four (4) RC pumps: At power r -levels of 15% and belou, the primary heat balance only
' *is to be used. From 15% to'100% power, the secondary '
heat balance is to be weighted per Figure 1 in con- '
()l ,
junction with the primary heat balance.
For operation with less than (4) RC pumps: The secondary heat balance at all power levels is to be
- used and is not to be weighted. The primary heat balance is not to be used. .
6.2.3 Perform the following if the computer is unavailable for service:
- 1. Complete the appropriate sections of Form 1.2 (Primary and Secondary System Weighted Heat Balance Check) using data
- l. ,
- from the listed-Pans 1 Indications. Data is to -be taken at -
five minute intervals for total of five sets of data. ,
- ' NOTE: For operation with all four (4) RC pumps: At power
, . .- Icvels'5f 15% anar below, the primary heat balance only -
~
- is to be dsed. From 15% to 100% power, the secondary
" ' heat balance is to be weighted per Figure 1 in con ,
~
junction with the primary heat balance.
For operation with less than four (4) RC pumps: The secondary heat balance at all power levels is to be used and is not to be weighted. The primary heat balance is not to be used, t,
p
-. - - - - ,w.--
PRIMARY SYSTE}! IEAT !!ALANCE CIIECK ET 5058.02.0 .
Forut 1.1 Page 1 of 2 Time Shift Date i
- 1. Data: .
l'.1 Reactor Power (7.) Clll (NI-6) C112 (NI-5) ,
Cll3 (NI-8) CII4 (NI-7) t Loop 2(FI-RCIA) 4 1.2 Reactor Coolant Flow (Ib/hr) Loop 1 (FI-RClB) 1.3 Reactor Coolant Unit 4 T (8F) (TDI-RC6)
NOTE: If listed Panel Indicator is unavailable for service, consult the Shif t Foreman for an alternate source of data and note this alternate source.
Alternate Source of Data
- 2. Calculations:
2.1, Pygt (Reactor Power in megawatts thermal) is given by:
PtMt = (Unit AT) (Loop 1 Flow + Loop 2 Flow)F 10-7 FMt where F is a conversion constant : 3.9678 OF-lb/hr PFMt = ( )( + ) 3.9678 10-7 tut .
- Pg pe = (_, .) ( ) 3.9678 10-7 1st
& P3 pg = ( ) 3.9678 10-7tMt .
t PtMt " .
2.2 The reactor power P in percent of rated core thermal power is:
P = PFMt . 100 = . 100 = 7, 2772 2772
- 3. Summary .
Calculated Core Power P= 7.
~
Indicated Core' Power ~
"CIII =- 7. -
- CH2 = 7.
C113 = 7.
CII4 = 7. .
~ - - - .
NOIE: , The chiculated and indicated core power should not di'M by more .
l than i 27.. If these differ by more than t 27. the % clear instru-i mentation shall be calibrated Calculated By .
it Reviewed By (Shif t Foreman)
Approved By Date (Technical Engineer) e o
l
- I F rm 1.1 PRIMARY SYSTEM IEAT DALANCE CIIECK ST 5058.02.0 -
- Page 2 of 2 _
l
~
l J
e' -
Nuclear Insttumentation Ca'.ibration
- required (IC 2000.00 Nuclear Instrumentation
~
Calibration at Power): ,
Yes No CH 1 2 3 4 Performed By Date Time e
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Form 1.2 PRIMARY A!!D SECONDARY SYSTEM ST 5058.02.0 Page 1 of 7 WEIGiffED HEAT BALAt:CE CHECK Date: Time Shift 7 1 NOTE: Take readings at five (5) minute intervals. Circle data _ source: Computer or Panci Indications (If listed Panel Indication is unavailable for service,
. consult the Shift Foreman for an alternate data source and note this alternste source on next page.
Panel Variable CPT Indication 1 2 3 4 5 AVE Reactor R795 ITI-6 CH1 Power (7.) R804 NI-5 CH2
, R814 NI-8 CH3 1
R820 NI-7
~.
CH4 RCS T T722 TI-RCB4 LP1 )
(DF)H l T731 TI-RC3A2 LP2 . l TI-RC4B1 '
RCS Tc T717 (Tc AVE) LP1 (oy) TI-RC4 A1 T726 (Ic NIE) LP2 RCS Pressuro h (pSic) Pi29 PRS-RC2A2 LPl
)
RCS Flow F615 FI-RCIB GJRC1)
(MPPD LP2 F619 FI-RCIA 01RC2)
RCP J788
- IT-RCS Bl 1-1 Electric.
Power J808
- IT-RCS B2
. 1-2 (KW)
J828
- IT-RC5 A1 2-1 ,
_ J848
- IFRC5 A2 2-2 O PT-616 1-1
. W r e PI-618
. P935 -t:2 . - _, _
TI-SP1 -
~
SG Inlet T884 (TT-SP1-2) 1-1
- W Temp. TI-SP1 l
s ( F) T900 (TT-SPI-1) 1-2 FI-SP2B 1-1 SG Inlet F674 (FY-SP2B) OJF1) '.
W Flow FI-SP2A 1-2 (KPPil) F679 (FY-SP2A1) GJF2)
'h SG Outict Press P931 PT-SP12B 1-1 (PSIC) P936 PI-SP12A 1-2
- The only available Panel Indication is given in amps.
. F rm 1.2 ST 5058.02.0 ,
Page 2 of 7 Panci Variable CPT Indicstion 1 2 3 4 5 AVE SG Outlet T885 TI-614 1-1 Temperaturc ,
(OF) T901 TI-613 1-2 -
Letdown Flow (CPM) F717 FI-IIU7 OILD)
Makeup Flow (cpm) F740 FI-MU31 OIMU)
. Makeup Temp.
(OF) T735 TI-MU8 Seal Inj.
Flow (CPM) F782 FI-MU19 Alternata Panel Indication used: .
II CALCULATION OF PRIMARY SYSTEM IEAT BALANCE CIECK (To be completed only during four (4) RC pump operations)
- 1. Obtain Reactor Coolant Enthalpy from the ASIE Steen Tables Loop 1 Reactor Coolant T H Enthalpy HH1(P729,T722)= BTU /lbm
(
Loop 1 Reactor Coolant TC Enthalpy hcl ( )" '
Loop 2 Reactor Coolant T HEnthalpy HH2 (P729,T731)= BTU /lbm Loop 2 Reactor Coolant T CEnthalpy HC2 (P729,T726)= BTU /lbm Makeup Water Enthalpy Hgy (P729,T735) = BTU /lbm
' ~
- 2. Calculate the loop heat rates and' makeup losses.
Loop 1 Heat Rate, HRtt = WRCl(HH1 - HC1)
E 1,1 " I --) I -
~
-)
HRg1 = { -) ( ~) " = -
HRgt = BTU /hr Loop 2 Heat Rate, HRg=WRC2(EH2-IIC2) ~
l HRL2 " I )I -
)
! Ep( )( )
, %= BTU /hP Letdown Loss, LLD " ULD* 497PPII(IICl-HMU GPM LLD = ( ) (497PPil) ( -
)
GPM LLD = ( ) (497PPil) ( )
GPM LD=
L BTU /hr .
- TP 5058.02.0 Firm 1.2 " '
Page 3 of 7
- 3. Using the data above and the following formul'a, calculate the core power,
- P PRI fr m the primary heat balance.
PPRI "(img1 + HEL2 + btD + K) 2,391
- 10-7 nit i BTU /hr where 2.931 10~7 IMt is a conversion factor from BTU /hr to IMt -
BTU /hr 6
and K = heat loss to radiation and convection losses = 0.4510 BTU /hr 6
P .+ + + 0.45 10 ) 2.931 10-7 PRI " ! ,
PPRI = 2.931 10-7 P Mit
_ PRI =
Core Power in (%), P7.p = PRI 100 = . 100 = %
RATE CORE THERMAL PO'.JER 2772 i
III CALCULATION OF SECONDARY SYSTEM HEAT BALANCE CHECK
- 1. Obtain Feedwater and Steam Enthalpy from the ASL". Steam Tables.
( ,
SG 1-1 Feedwater Inlet F.nthalpy Hp1(P930,T884)= BTU /lbm SG 1-1 Steam Outlet Enthalpy Hs1(P931,T885)= BTU /lba l
SG 1-2 Feedvater Inlet Enthalpy HF2 (P935,T900)= BTU /lbm SG 1-2 Steam Outlet Enthalpy HS2 (P936,T901)= BTU /lbm Loop 1 Feactor Coolant Tc Enthalpy hcl (P729,T717)= BTU /lbm Makeup Water Enthalpy Hmu(P729,T735)= BTU /lbm
, 2. Calculate SG hqst rates and latdolm ips_ses. _.
SG 1 Heat Rate HR 3gt = Wp y(HS I-Hpi)
IRSGI " ( - _ I(_ - -
--"_ } _ ".
~
,,e i uRSG1 " C } ( )
HRggi = BTU /hr
-H ) ',,'
- SG 2 Heat Rate IRSG2"NF2 (HS2 1RSG2 " ( )( -
)
HRSG2 " ( )( ) -
HRgg2 = BTU /hr
[
L a .
Form 1.2 ST 5058.02.0
- Page 4 of 7 Letdown Loss Lg=WLD 497PPH (hcl-Ih)
GPM g=(
I . ) (497 PPH)( -
)
.GPM LLD e ( ) (497PPH) ( )
GPM Lp=L BTU /hr ,
Computer as data source PE = Total of average powe'rs of the four pumps .
PE = W+ W+ KW + 101 PE = IGi .
Panel Indication as data source PE = Total of' average powers of the four pumps
! PS = ( amps + amps + amps + cmps) x 13.8 KV
(
I
. ' PE = 107 (h
- 4. Using the data above and the following formula, calculate the reactor core power, PSEC, from the secondary heat balance.
PSEC = (IIR3G1 + HRSG2 + LLD + C)'2.931
- 10-7 3pe
- PE 1000 BTU /hr where 2.931 10-7 We is the conversion factor from BTU /hr to 1Mt BTU /hr-and C is the heat losses from, and additions to, the Reactor C'oolant System and the steam generators. The term includes: -
! Primary System. radiative and convection losses. (K) '= 0.45 106 3.iU/hr .
i* Radiation . and convection-from Ehe bSI'T _ . = 0.69~106 BTU /hr
~ '
Heat losses to RCP motor cooling water = 6.20 10 6BTU /hr *
.. -- = 7.34 100 STU/hr
+ + ~ + 7.-34 7-L PSEC =(
10h 2.931 10 - -
[. .
1000.. . . . . .
, PSEC = ( ) * (2. 931
- 10-7) - ( )
PSEC " I )-( ) '
li .
PSEC " Wt P SEC Core Power in (7.), P73 = 100 . . 100 RATED CORE THERE\L POWER 1772 7.
P73 =
Fcrm 1.2 ST 5058.02.0 .
- Page 5 of 7 '
IV CALCULATION OF WEIClifED HEAT BALANCE (To be conplcced only during four (4)
(h, RC pump operation).
-Complete the Hand Calculation by applying the proper weighting factor.
i ,
PS EC(a) + PPRI (1-a) = veighted calculated core thermal power (Pg) a = Percent weighting from attached graph (Fig.1) a= (1-a) =
-~ ---. . ..-.. . .. . .. .. . . . .. . . .. . . .. . . . . _ _ ,, _
a=
1- a = __
PSEC(a) + PPRI(1-a) = Pg
( Nt) ( )+( wt) ( ) = Pg
( wt) + ( w t) = Pg ,
^ .-
N"* MWt ,
P%w = Pw - 100 ,
RATED CORE THERMAL POWER P%w *
- 100 =
2772 P%w == %
, V.
SUMMARY
Four R(' Pump Operation
" '~
$and Cal'culated Core Power Pw Wt .
P%w %
~" ~
~
. Computcr Calculation Core PoweT C936 - ~- mt -
(when available) . C913 %
Indicator Averaged Rea'c tor Power CH 1 %
l H2 %
CH 3 %
CH 4 %
e b .
4, Form 1.2 ST 5058.02.0 ,
. Page 6 of 7 NME: The hand calculated and computer calculated' core power should not differ by more than i 27.. Computer calculated and indicated reactor power
( ,, should not differ by 1 27.; if these values do not agree within 1 27. ,
the appropriate nuclear instrumentation channels shall be calibrated.
If the computer is unavailable for service, the hand calculated and indicated reactor power should be compared. If these differ by more than i 27., the appropriate nucicar instrumentation channel shall be i
calibrated.
Less than Four RC Pume Ocoration Hand Calculated Core Power (Secoadary) PE2C " Mit P73
=, %
Indicator Averaged Reactor Power CH 1 %
CH 2 % .
CH 3 %
CR 4 %
NorE: The hand calculated core power (sec'ondary) and the indicated reactor power should not differ by more than i 27.. If these values do not agree within i 2%, the appropriate nuclear instrumentation channels shall be es11brated.
(
h Calculated By Reviewed By .
(Shift Foreman) .
Approved By (Technical Engineer) (Date) ~ ,; .
y b 4- 3,4 ,
Nuclear Instrumentation Calibration . IC 2000.00 Nuclear Instrumen:- alibration at power)
Required ?
No Yes CH 1 2 4- -
" ~
. Performed By -Date 'T'ime
~~
~
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- ' ST 5058.02.0
. . F:rm 1.2
- Page 7 of 7
.r' O- *. '
FIGURE I 1.00 - ;
4 l
, i :
. i ,
e . l' ii : -
o . :
- a 0.80 --
i --- .
i
.e4 . . .
a
. . .1 .
. f ., . i I u .o -
ou
- u n. .
- " C 0.60 . ,
L1 !=
ab am l.
. t 1
8' I l I
i mm .-
4 C 4 j } i .i l fb 8 - 3
. 1 i
i ,
l 0.40 ~ ~
gm -
-i.
j j
u i gow .
- i l '
l 0.20 --
. t .
f
(- ..A ~ .
,V g 8 l l t ..
0 0 20 40 60 80 100 t .
% Average Indicated Power r
(
I- .
e 1 .
. e e
S i
l s
l(
END
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