Text

Rev a to Test Procedure 72PA-1RX03, Natural Circulation Test from 80% Power. W/840927 Ltr
	ML17298B285
Person / Time
Site:	Palo Verde
Issue date:	06/12/1984
From:	Van Brunt E; ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Knighton G; Office of Nuclear Reactor Regulation
References
	72PA-1RX03, 72PA-1RX3, ANPP-30678-EEVB, NUDOCS 8410010241
	Download: ML17298B285 (154)
	v • d • e

I REGULATOR INFORMATION DISTR BU ION S,TEM (RIDS)

ACCESSION NBR:8410010241 DOC ~ DATE'4/ NOTARIZED>, YES . DOCKET 0 FACIL:STN 50 528 Palo Verde Nuclear Stationr Unit lr Arizona Pbbli 05000528 STN,50-529 Palo Verde Nuclear Stationr Uni,t Zr Arizona Publi .05000529 STN 50,530 Palo Verde Nuclear Stations Uni.t 3r Arizona Publi 05000530 AUTH, NAME AUTHOR AFFILIATION VAN. BRUNTrE-,E, Arizona Public, Service Co.

,RECIP ~ NAME RECIPIENT AFFILIATION KNIGHTONrG ~ Licensing Branch 3

SUBJECT:

Rev A to Test Procedure 72PA"1RX03i "Natural Cit culation Test From 80K Power." W/840927 ltr > 5'6W drpg D I'STR IBUTION 'CODE B0 0 1 D COPIES RECEIVED LTR'" 'NCL "'IZE~ .

TITLE; Licensing 'Submittal: PSAR/FSAR Amdts:L Related Correspondence NOTES:Standardized plant> 05000528

'Standardized plant, 05000529 Standardized .plant. .05000530 RECIPIENT COPIES RECIPIENT COPIES IO CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR/OL/ADL 1 0 NRR L83 BC 1 0 LB3 LA

'RR 0 LICITRArE 01 1 1 INTERNAL! ADM/LFMB 1 0 ELD/HDS3 1 0 IE F ILE 1 1 IE/DEPER/EPB 36 3 3

=IE/DEPER/IRB 35 1 1 IE/DQAS IP/QAB21 1 1 NRR/DE/AEAB 1 0 NRR/DE/CEB 11 1 1 NRR/OE/EHEB 1 1 NRR/Of/EQB 13 2 2 NRR/DE/GB 28 2 2 NRR/DE/MEB 18 1 NRR/DE/MTEB 17 1 NRR/OE/SAB 24 1 NRR/DE/SGEB 25 1 1 NRR/OHFS/HFEB40 1 1 NRR/OHFS/LQB 32 1 1 NRR/DHFS/PSRB 1 1 NRR/DL/SSPB 1 0 NRR/DS I/AEB 26 1 1 NRR/OS I/ASB 1 1 NR R/OS I /C P 8 1-0 1 NRR/DSI/CSB 09 1 1 NRR/OSI/ICSB 16 =1 NRR/OS I/METB 12 1 1 NRR/OSI/PSB 19 1 l N '22 1 1 NRR/DS I/RSB 23 1 1 04 l 1 RGN5 3 3 RM/OOAMI/MIB 1 0 EXTFRNAL; ACRS 41 6 6 BNL(AMDTS -ONLY) 1 1 OMB/OSS",(AMDTS) l. FEMA REP DIV 39 1 1 LPOR 03 1 1 NRC PDR 02 1 1 NSIC 05 1 1 NTIS 1 1

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Arizona Public Service Company P.O. SOX 21666 ~ PHOENIX, ARIZONA 65036 ANPP-30678-EEVBJr/t6'Q/BJA September 27, 1984 Director of Nuclear Reactor Regulation Attention: Mr. George Knighton, Chief Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3 Docket Nos. STN-50-528/529/530 File: 84-056-026 G.l.01.10
References:
(A) Letter from E. E. Van Brunt, Jr., APS, to G. W. Knighton, NRC, dated January 27, 1983, (ANPP-22841).
Subject:
Natural Circulation Cooldown Testing.
(B) NUREG-0857, Supplement No. 5, "Safety Evaluation Report related to the Operation of Palo Verde Nuclear Generating Station, Units 1, 2 and 3", dated November 1983.
(C) Letter from E. E. Van Brunt, Jr., APS, to G. W. Knighton, NRC, dated August 7, 1984, (ANPP-30141).
Subject:
PVNGS Compliance with BTP RSB 5-1.
Dear Mr. Knighton:
Reference (C) provided a report which describes the PVNGS test program which addresses the requirements of Branch Technical Position (BTP) RSB 5-1. The Reactor Systems Branch has requested that the Arizona Public Service Company (APS) submit a copy of the Natural Circulation Cooldown Test Procedure. The requested test procedure is included as an attachment to this letter.
If you have any questions concerning this matter, please contact me.
Very truly yours, E. E. Van Brunt, Jr.
APS Vice President Nuclear Production ANPP Project Director
@oo EEVBJr/BJA/dh Attachment
I
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0 ANPP-30678 Page 2.
cc: A. C. Gehr (w/a)
E. A. Lic1tra (w/a)
C. LLang (NRC) (w/a)
ANPP-30678 STATE OF ARIZONA )
) ss.
COUNTY OF MARICOPA )
I, Edwin E. Van Brunt, Jr., represent that I am Vice President Nuclear Production, of Arizona Public Service Company, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority to do so, that I have read such document and know its contents, and that to the best of my knowledge and belief, the statements made therein are true Edwin E. Van Brunt, Jr Sworn to before me this ~~~day of 1984 Notary Public F
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My Coinmission Expires:
Vy Cairns'sion Bplros April 8, ~987
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ANPP-30678
Attachment:
Natural Circulation Cooldown Test Procedure
PALO VERDE NUCLEAR GENERATlNG PROCEDURE t' STATlON MANUAL NO.
72PA"1RX03 REVISION NATURAL C IRCULATION TEST FROM 80% PO'lKR Page 1 of 71
~poII,MAYIOX Oiitx ~-
i-hag Ml. l~M i DEPT. HEAD DATE PRB/PRG REVIEW i DATE %3~6 F APPROVED BY
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EFFECTIVE DATE DN-1548V/0293V 84<Op ZO2gl Sap612 gCg. O5PPP528
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PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 2 of 71 TABLE OF CONTENTS SECTION PAGE NUMBER 1.0 TEST OBJECTIVE 2.0 ACCEPTANCE CRITERIA
3.0 REFERENCES
4.0 PQEREQUISITES 5.0 SYSTEM INITIAL CONDITIONS 6.0 ENVIRONMENTAL CONDITIONS 12 7' SPECIAL PRECAUTIONS 12 8.0 DETAILED PROCEDURES 14 9.0 RESTORATION 34 10.0 DOCUMENTATION OF TEST RESULTS APPENDICES Appendix A - Prerequisite Testing List 36 Appendix B - Post Trip Record 37 Appendix O'- Auxiliary Feedwater Log 38 Appendix D - Boron Mixing Verification 39 Appendix E - Test Log 44 Appendix F - Boron Mixing Concentrations Appendix G - Boron Mixing Plots 46 Appendix H - Determination of Power/Flow Ratio 4'7 Appendix I - Strip Chart Recorder Assignments 50 PV216 000 REV.Bf82
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LNFORMAYEON ON~ 6 PALO VERDE NUCLEAR GENERATING PROCEDURE NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 3 of 71 TABLE OF CONTENTS - Cont'd SECTION PAGE NUMBER APPENDICES - Cont'd Appendix J - Plant Status Record Appendix K - Deleted 56 Appendix L - Test Data Acquisition System Configuration 57 Appendix M - Main Control Board Recorders 61 Appendix N - Auxiliary Spray Log 62 Appendix 0 - Pressurizer Decalibration Curves 63 Appendix P >> RCS Cooldown Plots 65 Appendix Q
- Heated Junction Thermocouple Data 67 Appendix R - DW Pump Usage Log 68 Appendix S - Pressurizer Heater Usage Log 69 I
Appendix T --Atmospheric Dump Valve Nitrogen Usage Log 70 Appendix U - Missing Data 71 PV216.00D REV. 8/82
/ fl 1% ~ J jtMFOBMAT10N ONI.V PROCEDURE PALO VERDE NUCLEAR GENERATINQ NO.
STATlON MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80K POWER 'Page 4 of 71 1.0 TEST OBJECTIVES 1.1 Objectives 1.1.1 To measure plant response to a total loss of flow while at 80% power.
1.1.2 To verify natural circulation following the trip from 80'ower.
1.3 To determine that adequate boron mixing can be achieved under natural circulation conditions. (Boron mixing demonstration to be performed during this test only performed.)
if not previously
1. 1.4 To demonstrate by performance or in combination with analysis the ability to perform a natural circulation cooldown followed by a plant depressurization to shutdown cooling conditions.
1.1.5 To evaluate natural circulation flow conditions and provide data to verify training simulator models.
1.2 Test Boundaries 1.2.1 Nuclear Steam Supply System (NSSS) 2.0 ACCEPTANCE CRITERIA 2.1 Natural circulation power-to-flow ratio is less than 1.0 (8.2.11; Cessar, 14.2.12.5) 2.2 Adequate boration of the RCS is verified under natural circulation conditions (if performed during this test).
(Appendix D; Ref. 3.2.6, Step 3.7) 2.3 The Reactor Coolant System can be cooled down and depressurized during natural circulation. (8.4.17; Ref. 3.2.6) This may be in combination with analysis.
3.0 REFERENCES
3.1 Implementing References 3.1.1 72PA-1ZZ01, Power Ascension Controlling Document PV216 00D REV.8/82
0 ll5POHMAYH)N Gi'~ "f PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 5 of 71 3.1.2 41R0-1ZZ04, Loss of RCS Flow
3. 1. 3 41A0-1ZZ13, Natural Circulation 3.1.4 410P-1RC01, RCP Operation 3.1.5 410P-1CH01, CVCS Normal Operations 3.1.6 72MT-9SB01, CPC/CEAC Software Maintainance 3.1.7 41R0-2ZZ01, Reactor Trip 3.1.8 410P-1NA01, 13.8kv Non Class IE 3.1.9 410P-1SG01, Hain Steam 3.1.10 72PA-1ZZ06, NSSS Plant Steady State Test Record
( 3.1.11 3.1.12 72ST-9RX09, Shutdown Margin 73PA-1NAOl, Loss of OFFSITE Power at 50%
3.1.13 73ST-1RC01, Reactor Coolant System Transient and Operational Cycle 3.1.14 75RP-9ZZ92, Gaseous Radioactive Effluents Release Permit 3.2 Developmental References 3.2.1 CE-NPSD-154, Natural Circulation Cooldown Task 430 Final Report 3.2.2 2PA-215-01, San Onofre 80% Power Natural Circulation Test, Rev. 1 3.2.3 CESSAR, C-E SYSTEM 80 FINAL SAFETY ANALYSIS REPORT Section 14.2.12.5.1, Total Loss of Flow Trip from 80% Power with Natural Circulation Verification, Amendment 6.
3.2.4 V-CE-17093 (9114183) CESSAR Natural Circulation Cooldown.
3.2.5 Technical Specification, Section 5.7, Component Cyclic or Transient Limits (6/83) 3.2.6 Reactor System Branch (RSB-BTP-5-1) Statement of Natural Ci:rculation NUREG-800 (7/19/81))
PV216 000 REV. 8i82
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XNPOIRMAYi.oN Oui "f PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80/ POWER Page 6 of 71 3.2.7 COEG Task 477, Evaluation of Song 2 Natural Circulation (CEN-259)j 1/84.
3.2.8 AR/PP-22261, WFQ/TFQ Change to LLIR Item I.G.1 (10/82) 3.2.9 V-CE-19458 APS Natural Circulation Cooldown Test (12/16/83) 3.2.10 Technical Specifications (6/83) 3.2.11 FSAR Section 5, Question 5A.17; Amendment 7.
3.3 Abbreviations 3.3.1 ASS Anticipated Transient Vithout Scram 3.3.2 DAS Data Acquisition System 3.3.3 RCP Reactor Coolant Pump 3.3.4 ADV Atmospheric Dump Valves 3.3.5 HJTc Heat Junction Theimocouple 3.3.6 CET Core Exit Thermocouple 3.3 ' SAT Monitor Saturation Monitor 3.3 ' CST Condensate Storage Tank 3.3.9 RDT Reactor Drain Tank 3.3.10 VCT Volume Control Tank 4.1 Test Overview 4.1.1 The Natural Circulation Test is a result of NUREG-0694, TMI Related Requirements for New Operating Licenses." In a letter dated June 12, 1981, the NRC further specified that the Natural Circulation testing program should following requirements:
fulfill the 4.1.1.1 A training sequence should be conducted in which all RO's participate in initiation control, and recovery from natural circulation.
PV216 00D REV. 8/82
0 0
LNFO~TION 01iLV PALO VERDE NUCLEAR GENERATING PROCEDURE NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 7 of 71 4.1.1.2 Length of time to natural circulation stabilization, adequacy of boron mixing, and ability to cooldown to shutdown condition should be determined.
4.1.1.3 Palo Verde will meet the NRC requirements, by training exercises conducted on the simulator prior to exceeding 5% power. The remaining requirements will be satisfied by the 80% Natural Circulation test. In addition, test results will be used to verify simulator modeling of the event. (ANPP-22261 - WFQ/TFQ Change to SER and LLIR Commitment Item I.G.l) 4.1.1.4 The most significant difference between the Palo Verde Natural Circulation test and tests conducted at other sites is that at Palo Verde will attempt voiding in the upper head. Reactor vessel head voiding must be integrated into the cooldown strategy to achieve a cooldown rapid enough enough to satisfy limited condensate inventory constraints and availability of nitrogen to the atmospheric steam dump.
4.1.1.5 The test begins by tripping all four RCP's and establishing natural circulation. Once established, adequate flow through the core is verified through the power-to-flow ratio test. The natural circulation power-to-flow ratio should be less than or equal to the same ratio at 80% power.
4,1.1.6 The next test segment demonstrates adequate boron mixing through increasing primary boron by 100 ppm, then verifying that 3 consecutive samples of the RCS are within + 20 ppm.
4.1.1.7 In the final segment of the test, a cooldown of 150 to 200 F will be performed, followed by pressure reduction to the void formation threshold. Once a void is observed, it will be expanded to approximately 1000 ft3
, then collapsed through charging with charging pumps and opening the RV head vent. This procedure flushes cooler water through the hot, stagnant RV head area.
4.1. 1.8 The growth-collapse cycle will be repeated until the RV head has cooled sufficiently to prevent further void formation at the threshold pressure. The time required for the entire evolution will reflect on whether the plant can be cooled to shutdown .cooling conditions before condensate runs out.
PV216 00D REV.S/82
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IWFORYI. &YYON OM,V PROCEDURE PALO VERDE NUCLEAR .GENERATING NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL C IRCULATION TEST FROM 80% POWER Page 8 of 71 4.2 Personnel Indoctrination 4.2.1 This procedure will require 4 data collectors and 2 engineers in addition to the normal operation staff.
4.2.2 This procedure has three major evolutions. For guidance only an estimate of the time required for each of the evolutions is listed below. Those estimates may be exceeded.
Natural Circulation Verification 1-2 hours Boron Mixing Verification 8-10 hours Natural Cooldown Circulation 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4.3 Procedure 72PA-1ZZ01 calls for this test to be performed and the tests in Appendix A have been performed.
Shift Test Director Date 4.4 Personnel performing the test have been briefed at the pre-shift briefing on this procedure, associated precautions, and actions to be taken if abnormal conditions occur.
Responsible Engineer Date 4.5 The Plant Monitoring System is in service.
Responsible Engineer Date 4.6 The data points specified in Appendix L have been established on a data acquisition system. Log in Test Log which system is being used.
Responsible Engineer Date 4.7 A Data Acquistion System (DAS) is available.
Responsible Engineer Date PV216.000 RKV. 8I82
PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 9 of 71 4,8 The Load Dispatcher has been informed of the impending loss of load.
Responsible Engineer Date 4.9 The parameters specified in Appendix I have been input to the Strip Chart recorders. The recorders have been properly scaled and labeled with the information specified.
Responsible Engineer Date 4.10 The Radioactive Waste systems are prepared to receive the quantities of liquid and gaseous waste that will be generated during this test.
Responsible Engineer Date 4.11 The general procedural guidelines of Section 4 of 72PA-3.ZZOl have been reviewed.
Responsible Engineer Date 4.12 Calculate shutdown margin for the range of conditions that might occur during the test and are attached to the test package. This value will be used in Appendix D, Step 2, Boron mixing, or in the natural circulation cooldown to shut down cooling conditions.
Responsible Engineer Date NOTE The Shift Test director shall make the subjective decision of adequate decay heat. Calculations may be performed to estimate decay heat.
4.13 Adequate decay heat is available for Natural Circulation, i.e.,
the'Natural Circulation Loop delta T is not expected to drop below 10 F for the duration of the test.
Shift Test Director Date PV216 000 REV.8/82
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PALO VERDE NUCLEAR GENERATING PROCEDURE NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80K, POVER Page 10 of 71 4.14 Adequate condensate storage water is available for decay heat removal and cooldown. (Approximately 330,000 gals). Tank level should be greater than 90%.
Responsible Engineer 4.15 All three auxiliary feedwater pumps are operable.
Responsible Engineer 4.16 The atmospheric dump valves have been cycled in the preceeding 7 days and air and nitrogen supply systems inspected to verify no excessive leakage. ADV's may need only be cycled by the normal supply system.
Responsible Engineer 4.17 The procedure for the operation of the ADV's has been reviewed and understood by operations personnel who would operate the valves.
Shift Supervisor 4.18 Gaseous Radioactive Effluent permit has been obtained.
Responsible Engineer l
4.19 Notification to Chemistry has been made of the performance of this test for sampling purposes.
Responsible Engineer PV216.000 REV. 8/82
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PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 11 of 71 5.0 INITIAL CONDITIONS NOTE Instrument ID's given in this procedure are for a reference, equivalents may be used. If different instruments are used log the ID's in the Test Log.
5.1 The system is being maintained at the following conditions:
5.1.1 Reactor. Power (ID = JSCALOR) 80% (78.0 to 82.0%)
or (Excore Safety Channels)
5. 1.2 RCS Cold Leg Temperature Approximately 565 F (ID = RCT 112CC) or (ID = RCT 122CB) 5.1.3 Pressurizer Pressure 2250 psia (2235 to 2265 psia)
(ID = RCP102A) or (ID = RCP100X)
5. 1.4 Pressurizer Level (ID = RCL110X) Within Tave program (ID = RCL110Y) for PLCS
5. 1.5 Steam Generator Level (NR)
(ID = SGL1111) Stable level (ID = SGL1121) 5.1.6 Turbine Control. on Load Limit 5.2 All four channels of the PPS are operating.
NOTE The FWCS or SBCS may be put in manual, at the discretion of the Responsible Engineer. If controls systems placed in manual, log the change in the test log.
5.3 The SBCS is in automatic control.
5.4 The FWCS is in automatic control.
PV216 000 REV. 8/82
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PALO VERDE NUCLEAR GENERATING PROCEDURE NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POVER Page 12 of 71 5.5 Pressurizer pressure and level control are in automatic.
5.6 The CEDMCS is in Manual Sequential, with essentially all rods out, with CEA's within 1.5" of Group average.
5' Two charging pumps are operating and the third is in standby.
5.8 The Plant Monitoring System is in service.
5.9 The turbine bearing for automatic operation.
and RCP oil lift pumps are operable and set
5. 10 Documentation of power history has been obtained and is attached to this procedure, for the purposes of decay heat calculation.
5.11 Either QSPDS or ERFDADS is in service, log in Appendix E.
5.12 Heated Junction Thermocouple System is operable.
6.0 ENVIRONMENTAL CONDITIONS None 7.0 SPECIAL PRECAUTIONS 7.1 Three charging pumps should be available for operation.
Borations or dilutions as called for during the test should be accomplished using all three charging pumps in order to obtain maximum response.
1 7.2 A CPC trip should occur within one second after the RCP's are tripped. If the reactor does not trip within four seconds of the RCP trip, the operator should manually trip the reactor and proceed with Section 8,2 of this test. Per reference 3.2.9 plant safety is assured as long as manual trip occurs within 7.5 seconds.
PV216 00D REV.8/82
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IWFOHMATioN ONLV PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72'PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80'fo POWER Page 13 of 71 7.3 Except during cooldown, if RCS temperature (Tc ) as read from the panel B05 safety class Tc 's falls below (550 ) or pressurizer level decreases below (30%), check feed flow and/or steam flow and correct as necessary to control the temperature decrease.
Normal pressurizer spray will not be available without RCP flow.
If pressure control cannot be achieved using auxiliary spray, or through the TA~ reduction, restart pumps according to reference 3.1,4, 410P-1RC01 RCP Operation. This will terminate the test. Follow the plant operating procedures regarding the start of the pumps if a void is present in the reactor vessel head.
7.5 Minimize the use of auxiliary spray as much as possible. Note all cycling of the spray nozzle in Appendix N. Calculate Cumulative Usage Factors accordng to Table 5.7-1 of the Technical Specification, and 73ST-lRCOl.
7.6 Terminate the test if any of-the following conditions occur:
a. T 500 (except during cooldown and depressurization) c <
b. Hot Leg temperature increasing and Th) 621 (after several minutes following trip)
This temperature may be read from the highest reliable reading core exit thermocouple.
c. Indicated margin to saturation less than 28
d. Adequate natural circulation cannot be maintained.
7.7 The boron concentration of any makeup water added to the plant during cooldown shall be the same or greater than the RCS boron concentration to prevent dilution.
7.8 Do not start or jog a RCP while a condensable void is known to be present in the reactor vessel head region. Sudden forced flow of relatively cool reactor coolant into this region may result in a collapse of the condensable void with resultant water hammer effects.
If pressurizer level increases unexpectedly, this may be an indication of a void in the reactor vessel head, auxiliary spray is to be stopped, and the plant stabilized: Once the reason has been determined for the unexpected void, the reason shall be logged and the test may continue.
PV216 00D REV. 8/82
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PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POMER Page 14 of 71 7.9 Cooldown and depressurization will be performed under the simulated degraded conditions of condenser not available. The atmostpheric dumps will be used for cooldown. Depressurization will be accomplished using auxiliary spray.
7.10 Prior to performing the natural circulation cooldown test the plant should be degassed to minimize the chances of a hard bubble if voiding occurs.
F 11 Maintain pressurizer actual level greater than 30% but less than 50% prior to depressurization during the natural circulation cooldown.
7.12 Note the following test exceptions have been taken for this test (LATER) 7.13 This test will use the reactor head vent system to collapse the upper head void during the natural circulation cooldown. The system will be used for this purpose for the first time during this test. The possibility exists that the RDT rupture disk could rupture. Pressure and level should be closely monitored and the tank pumped if necessary. Calculations show liquid inventory in the RDT will increase at a rate of 3 gpm.
7.14 Notify Radiation Protection department prior to planned use of the atmospheric dump valves.
7.15 Prior to use and after refilling any tank contact. Chemistry department to ensure the water meets chemical specifications for use.
8.0 PROCEDURE 8.1'nitial Data Collection 8,1.1 Log the start of this test in Appendix E of this procedure and in Appendix E of 72PA-lZZOl.
PV216 000 REV.8182
0 0
1XPORMM'K)N ONLY PALO VERDE NUCLEAR GENERATING PROCEDURE NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 15 of 71 8.1.2 Initial Conditions 8.1.2.1 Power ID 8.1.2.2 RCS Tc ID 8.1.2.3 RCS Pressure ID 8.1.2.4 SGWL (NR) SGl ID
,SG2 ID 8.1.2.5 Boron Sample (RCS Hot Leg) 8.1.2.6 Boron Sample (Boronmeter) 8.1.2,7 CST Level ID 8.1.2.8 Nirrogeu Accumularor Pressure (ADV's) ID 8.1.2e9 CST Temperature TI 14 (local) 8.1.3 Secure steam generator blowdown.
8.1.4 Isolate all sources of 1 makeup to the condensate storage tank. This step may be performed anytime prior to step 8.2.
8. 1.5 The load dispatcher has been notified of the pending loss of load.
8.1.6 Transfer the Auxiliary Transformer loads from the Main Generator to the Startup Transformers. Refer to 410P-1NA01, 13.8KV, Nonclass IE Procedure.
8.1.7 Obtain an Incore Thermocouple Report and identify the two highest reliable reading thermocouples. Assign them to a DAS in Appendix L and log below.
CET and PV216 00D REV. 8182
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gqFO~T10N ONE,Y PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 16 of 71 8.1.8 Start the test recorders at 1 mm/sec. Establish a common timing mark.
8.1.9 Complete Appendix J and commence logging required data in Appendix Q.
8.1.10 Verify CEAC and CPC trip buffers are or have been reset, per 72MT-9SB01.
8.1.11 Invoke Technical Specification Test Exceptions (Later).
8.1.12 Request a NSSS Steady State Test Record via 72PA-1ZZ06 and attach to this test package.
8.2 Natural Circulation Verification NOTE This section of the test provides instructions for tripping the RCPs and establishing and verifying natural circulation'onditions. During this section the following will apply.
1) Either the SBCS valves or the ADVS may be used at the discretion of the Shift Supervisor and Responsible Engineer. The selection shall be logged in the test Log.
PV216 000 REV.BI82
IINFOHMAYION ONION PALO VERDE NUCLEAR GENERATlNG PROCEDURE NO.
STATlON MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 17 of 71
2) As soon as possible following the Reactor trip the main feed water system will be secured and feed water shall. be supplied to the Steam Generators using Auxiliary feedwater systems.
3) To meet the requirements of ref. 3.2.6, the determination of feedwater usage will be made during sections 8.2 through 8.5 of this procedure. It is undesirable to replenish the CST Level. Invoke technical specification test exception (later). If replenishment is required (CST level 40%)
log demineralized water pump flow to CST in Appendix R. The be used as a backup ifmayits RMWT source, of, water. only water usage is monitored.
4) Attempt to avoid making up the VCT until the boron mixing portion of the test, such that the VCT is low after trip and has sufficient room to accommodate the boron without exceeding 84%. The VCT boron concentration shall be maintained greater than the RCS when it is used as a supply to the charge pumps per Special Test Exception. (Later).
8.2.1 Announce start of test to test and operating crews.
8.2.2 Countdown each minute five minutes in advance of the test.
Increase the interval to once per second, ten seconds before the trip.
PV216 000 REV.8/82
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INPOIIlMA'lI'loN ONLY
0 PALO VERDE NUCLEAR GENERATING STATION MANUAL PROCEDURE NO.
72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80/ POWER Page 18 of 71 8.2.3 Initiate Data Acquisition System sampling of data points, five minutes before trip and or other data acquisition systems if in use.
NOTE For the data logger select one scan per second, the other systems scan rate shall be determined by the Responsible Engineer and logged in Appendix E.
8.2.4 Increase the test recorder speeds to 25 mm/sec twenty seconds before the trip.
NOTE
1. Reactor trip should occur within approximately one second of the RCP trips.
If a Reactor trip does not occur within approximately three seconds, manually trip the plant and continue with Section 8.2.
Notify STD and SS for determination of corrective action, a TER shall be written in this case.
2. Tripping of the four RCP's should cause a CPC trip on flow projected DNBR in approximately one second. If no action, a DNBR condition would not occur until 7.5 seconds.
3. Operators should be aware of a possible ATWS. Operators should be stationed at the following locations for the beginning of this test. One operator on Control Board BO 3 to trip all four RCP's simultaneously. One operator at Control Board BO 4 ready to manually trip reactor if after 4 seconds the CPC's did not trip the reactor.'nd a third (optional) operator at Control Board BO 1 to trip load centers 03 and 10 (CEDM MG set supply breaks) if required.
PV216 000 REV.8/82
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PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 19 of 71
4. Operators are not to take any action in the first sixty seconds following the trip, other than those required by procedure 41RO-1ZZ04 (Loss of RCS Flow). Any unavoidable operator actions shall be recorded in Appendix B, Post Trip Records, as well as plant events for the first ten minutes.
5. Pressurizer pressure will increase starting approximately one minute after the trip until natural circulation has been established. The pressure may approach 2500 psia or the Safety Valve Setpoint. Use auxiliary sprays to maintain pressure less than 2400 psia.
CAUTION
1. If any of the following occur during performance of Section 8.2 start the RCP per 41RO-1ZZ04. If an indication of a void is present, initiate safety injection per 41R0-1ZZ04, do not start a RCP.
a. T 500 F.
c g
b. Hot leg temperatures are increasing and TH> 621 (after natural circulation declared.)
c. Indicated margin to saturation less than 28
d. Adequate natural circulation flow cannot be maintained.
2. If Tc falls below 550 F, adjust Feed Flow or Steam Flow as necessary to stop the cooldown.
8:2.5 At time zero, trip all four coolant pumps as simultaneously as possible. Record plant and operator actions in Appendix B.
PV216 000 REV. 8/82
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JNPORMATION ONLY PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 20 of 71 8.2.6 Perform applicable portions of procedure 41RO-1ZZ04 following the trip. Do not restore the RCP's at this time.
8.2.7 Verify that Natural Circulation has been established per Appendix C of procedure 41RO-1ZZ04. The following symptoms should be evident.
8.2.7.1 Hot leg temperatures are stable or decreasing.
8.2.7.2 Cold leg temperatures are close to and trending steam generator Tsat.
8.2.7.3 Core delta T is less than full power delta T of 57 F.
8.2.7.4 The Hot Leg RTD's and core exit thermocouple readings should be consistent.
8.2.8 Verify that steam generator feedwater is being supplied by auxiliary feedwater system and main feed is secured, maintain data collection per Appendix C of this procedure.
8.2.9 Once the plant stabilizes, reset the DAS scan rate to 1 scan per minute and the test recorders to 25 mm/min.
NOTE
1. The accuracy of the power to flow ratio determined in the following steps will 'be increased by maintaining plant parameters as stable as possible. Maintain RCS cold leg temperatures as', steady as possible throughout the measurement.
2. If practical, steps 3.1 through 3.6 of Appendix D should be performed in parallel with Step 8.2.10 if Appendix D is to be performed. The object is to be able to proceed with as little wasted time as possible so the maximum amount of decay heat will be available for various evolutions.
PV216 00D REV.8/82
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1NFORMAY'foN ONYX PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72PA-1RK03 REVISION NATURAL CIRCULATION TEST FROM 80K, POWER Page 21 of 71 8.2.10 Control RCS cold leg temperatures within a target value of
+2 and an outer band of +M of their current value using the atmospheric dump values or SBCS valves (log the valves which are used). Maintain these stable conditions for at least 30 minutes. Record start and finish times below.
Start Time Completion Time 8.2.11 Complete Appendix H before continuing to determine the power/flow ratio. Record below.
Power/Flow Ratio Responsible Engineer 8.2.11.1 ACCEPTANCE CRITERIA: Power/flow 1.0 8.2.11.2 Stop Strip Chart Recorder 1 and 2, Appendix I.
8.3 Boron Mixing Test This Test may have been performed as part of the Loss of Offsite Power Test. If so, sign 8.3.1 and mark N/A in 8.3.2.
test is required mark N/A in 8.3.1.
If the 8.3.1 The boron mixing test has been performed as part of the Loss of Offsite Power Test, 73PA-1NA01.
Responsible Engineer 8.3.2 Perform Appendix D e
PV216 000 REV.8(82
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k INFORMATj.oN ONLY PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 22 of 71 8.4 Natural Circulation Cooldown NOTE This section provides instructions for performing a cooldown of 150-200 F, using Natural Circulation and should be performed in conjunction with 41AO-1ZZ13. The test assumes that all safety equipment is fully operational. If an event occurs during the test that causes a loss of equipment, refer to procedure 41AO-1ZZ13 for further guidance.
8.4.1 Verify that adequate condensate is available for at least a 210 F cooldown. Aproximately 330,000 gallons will be required.
8.4.2 Begin sampling RCS boron concentration (Hot Leg jjl) and Pressurizer Surge Line at 60 minute intervals and record in Appendix F.
CAUTION
1. ENSURE THAT MAKEUP TO THE RCS IS AT LEAST THE SAME BORON CONCENTRATION, TO PREVENT DILUTION.
2. MINIMIZE CYCLING THE AUXILIARY SPRAY TO THE PRESSURIZER WHEN THE DELTA FROM THE SPRAY TO THE PRESSURIZER EXCEEDS 150 F. RECORD CYCLES IN APPENDIX N.
3. DO NOT OPERATE THE PRESSURIZER HEATERS BELOW A PRESSURIZER WATER LEVEL OF 25%.
4. Try to MAINTAIN NORMAL PRESSURIZER AND STEAM GENERATOR LEVEL THROUGHOUT THE COOLDOWN.
5. CLOSELY MONITOR CONDENSATE INVENTORY THROUGHOUT THE COOLDOWN.
PV216 00D REV.8182
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26'ORMA.TION ONr.V PROCEDURE PALO VERDE NUCLEAR GENERATlNG NO.
STATlON MANUAL 72PA-1RX03 REVISION NATURAL ClRCULATION TEST FROM 80/ POWER Page 23 of 71 NOTE Both steam generators should steam at approximately equal rates to cool the RCS uniformly. This requires watching the position of the atmospheric dumps as closely as possible,to balance steam flow rates through both generators.
8.4.3 Transfer steam load to atmospheric dump valves per 410P-1SG01 if Steam Bypass Control Valves are in operation for heat removal if not mark NA.
A data taker. is.required to monitor ADV nitrogen pressure closely either at local guages or PMS point XD. The control room shall be notified at approximately 300 psig. A minimum nitrogen pressure of 80 psig is needed for operation of the ADV's. Reinitiate instrument air or use manual ADV operation if ADV's are still required. Log the final pressure of the nitrogen, the time and RCS temperature/pressure in the Test Procedure Log.
8.4.4 Verify the nitrogen accumulators are lined up to the ADV positioners and secure instrument air supply to the ADV's and start to collect data in Appendix T.
8.4.5 Verify that all possible steam loads have been transferred to the auxiliary steam cross tie.
8.4.6 Verify or close the main steam isolation valves and Steam Bypass Valves. Note any change required in ADV position in the Log.
8.4.7 Verify that the following turbine bypass values are closed using control console lights.
8.4.7.1 PSGN-PV-1001 PV216 000 REV.8/82
a Oix2.7 J'IPORMAT8)N PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80/ POVER Page 24 of 71 8.4.7.2 PSGN-PV"1002 8.4.7.3 PSGN"PV"1003 8.4,7,4 PSGN-PV-1004 8.4.7.5 PSGN-PV-1005 8.4.7.6 PSGN-PV-1006 8.4.7.7 PSGN-PV"1007 8.4.7.8 PSGN"PV-1008 NOTE The following step secures non class IE pressurizer heaters due to a requirement of Reference 3.2.6. Ensure Operations monitors pressurizer pressure closely.
The heaters are to remain secured until Step 8.4.15, unless necesary to maintain minimum of 28 F loop subcooling, then record usage in Appendix S.
8.4.8 Verify or Secure non safety class equipment 8.4.8.1 Non class IE pressurizer heaters.
PV218 00D AEV.8/82
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ECF QBMA'jt'IQN QNLY PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 25 of 71 CAUTION
1. DO NOT EXCEED AN RCS COOLDOWN RATE OF 100 F/HR PER TECHNICAL SPECIFICATION 3/4.4.8.
2. MAINTAIN THE RCS at least 28 F subcooled.
3. BE AWARE THAT PLANT RESPONSE TIME SLOWS TO ROUGHLY FIVE TO TEN MINUTES DURING NATURAL CIRCULATION DUE TO THE SLOWER COOLANT FLOWS.
MONITOR FOR REACTOR VESSEL UPPER HEAD VOID FORMATION BY CHECKING FOR THE FOLLOWING SYMPTOIis:
A. PRESSURIZER LEVEL INCREASE SIGNIFICANTLY GREATER THAN EXPECTED WHILE OPERATING AUXILIARY SPRAY.
B. PRESSURIZER LEVEL DECREASE WHILE OPERATING CHARGING PUMP(S).
C. LETDOWN FLOW UNEXPECTEDLY GREATER THAN CHARGING FLOW WITH THE PRESSURIZER CONTROL SYSTEM IN AUTOMATIC.
D. THE REACTOR VESSEL LEVEL INDICATOR SHOWS VOID FORMATION IN THE REACTOR VESSEL.
5. DURING THE PRESSURIZER COOLDOWN, THE PRESSURIZER LEVEL INSTRUMENTS WILL BECOt'iE DECALIBRATED. USE THE TEMPERATURE CORRECTION CURVES OF APPENDIX 0 TO DETERMINE ACTUAL PRESSURIZER LEVEL. DO NOT ENERGIZE PRESSURIZER HEATERS BELOW A CORRECTED WATER LEVEL OF 30% HEAT CUTOUT OCCURS AT 25% INDICATED LEVELS PV216 000 REV.BI82
gl p60~7M)N ONr.V PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STAT!ON MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 26 of 71
6. CONTINUALLY MONITOR THE PLANT DURING VOID FORMATION TO ENSURE THAT NATURAL CIRCULATION IS BEING MAINTAINED. IF THE RCS LOSES NATURAL CIRCULATION, REFER TO PROCEDURE 41AO-1ZZ13 FOR FURTHER INSTRUCTIONS.
7. DO NOT START ANY RCP'S WHILE THERE IS A VOID IN THE REACTOR VESSEL. STARTING THE PUMPS WITH A VOID PRESENT CAN CAUSE WATER HAEKRS IN THE REACTOR VESSEL.
8. ENSURE THE SHUTDOWN MARGIN CONDITIONS EXIST PER REFERENCE 3.2.10.
NOTE Pressurizer parameters may be monitored from the Recorders in Appendix F, as well as the Strip Chart Recorders.
8.4.9 Verify the core exit, thermocouple from Step 8.1.7 is still the highest reading reliable core exit thermocouple . This thermocouple will be used in place of hot leg temperature unless it becomes unreliable, At the discretion of the RE other thermocouples may be selected for use and used as a hot leg termperature; if this change is required it shall be noted in the Test Log.
CET used = hot leg temperature 8.4.9.1 Ensure thi's core exit thermocouple number is recorded in Appendix P.
8.4.9.2 Start strip chart recorder 3, Appendix I.
8.4.9.3 Start data collection in Appendix Q.
PV216 00D REV. 8/82
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PALO VERDE NUCLEAR GENERATING PROCEDURE NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 27 of 71 8.4.10 Using the atmospheric dump values (SGA-HA-184, SGA-HV-179, SGB-HV-185, SBG-HV-178) establish a steady cooldown rate not to exceed 75 F/hr. The cooldown will be governed by 41AO-1ZZ13. Record starting conditions below. Maintain a cooldown plot per Appendix P.
Time T LD1A ID TCQLD2B ID Hl ID H2 ID RCS Pressure ID Thermocouple ID PV216 OOD REV. S/82
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'I ENFOElVjLA.'DMI ONLT PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POVER Page 28 of 71 NOTE
1. Ensure the data points in Appendix L are available and the Data Acquisition System are in service. The Responsible Engineer may make the determination which points will be monitored and will be so noted in the test log.
2. If void formation occurs unexpectedly STOP the cooldown and stabilize the RCS pressure constant. Determine the cause and log in the Test Procedure log before continuing the cooldown.
8.4.11 Continue to cooldown using the atmospheric dumps until the RCS hot leg temperature has been reduced to approximately 350'F or indication of void formation is present. Log the temperature where cooldown is suspended.
Time COLD ID RCS Pressure ID Thermocouple ID 8.4.12 Stabilize, the plant for 30 min.
Start Time Finish Time HJTc Level .
PV216 00D REV. 8/82
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PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION 72PA-1RX03 MANUAL'ATURAL REVISION CIRCULATION TEST FROM 80% POWER Page 29 of 71 NOTE 1, During the following depressurization to approximately 400 psia a reactor head void is expected. Slowly reduce pressure and monitor void formation carefully. Secure depressurization and unexpected plant conditions arise.
stabilize if any
2. As pressurizer pressure decreases remember to reduce the low pressurizer pressure trip set point as necessary or when pressure approaches 50 psia from pretrip set point.
3. As pressure decreases to less than 715 psig depressurize Safety Injection Tank.
Monitor void formation if exceed 80% actual pressurizer level or a present. Do not 1000 ft void in the reactor vessel upper 3
head region.
5. Use Appendix 0 to determine actual pressurizer level.
6. During the depressurization use a target rate of 20 psi/min decrease in pressure.
8.4.13 Initiate depressurization per 41AO-1ZZ13 to a pressure to support initiation of shutdown cooling or less than 350 psig.-
8.4.13.1 Record depressurization in Appendix P 8.4.13.2 Increase sampling rate in Appendix Q for HJTc data.
8.4.13.3 Log usage of Auxilary Spray in Appendix N and 73ST-1RC01 if required.
PV216 00D AEV.8/82
R PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 30 of 71 8.4.13.4 Stabilize the plant and record the following prior to opening the head vent.
Time HJTc level ID RDT pressure ID RDT level ID RDT temp ID Pressurizer level ID
1. If no void is present log in the Test Log any plant conditions which might have precluded the plant from drawing a bubble and go to Step 8.4.17.
2. If void present Step 8.4.14 will demonstrate the ability to collapse a void in the reactor head by using the Reactor Head Vent System and preferentially directing charging to the reactor vessel upper head.
PV216 000 REV.BI82
~ f1 1ÃFQBMATIQN QNLV PALO VERDE NUCLEAR GENERATING PROCEDURE NO.
STATION 72PA-1RX03 MANUAL'ATURAL REVISION CIRCULATION TEST FROM 80% POWER Page 31 of 71 CAUTION
1. The following step opens the reactor head vent. This will be the first operation of the head vent in a void collapse method.
Monitor carefully: RCS pressure, RCS head level and'RDT parameters.
unexpected or uncontrolled events occur If any close the head vent valve, stabilize the plant and energize the pressurizer heaters if required.
2. Secure the head vent Tank exceeds 50 ysig if the Reactor Drain or an indicated level of 80%.
8.4.14 Commence collapsing the upper head void via the method involving the reactor head vent system per 41A0-1ZZ13..
NOTE Vent the upper head until the RDT pressure exceeds 50 psig or RDT level exceeds 80% or in the determination of the RE sufficient upper head void has collapsed to demonstrate the ability of the head vent system to collapse the void. (Positive change in meter reading.)
8.4.14.1 Record the following when reactor head vent secured.
HJTC Level RDT Pressure ID RDT Level ID RDT Temp ID PV216 00D REV. 8/82
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PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STATION MANUAL 72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80K, POVER Page 32 of 71 RDT Temp ID Pressurizer Level ID 8.4.15 Allow the plant to stabilize NOTE To minimize operation of the head vent system and possible overpressurization of the RDT, once the ability to collapse the bubble has been demonstrated, pressurizer heaters (class and non-class) will be used to continue the process.
8.4.16 Continue to collapse the Reactor Vessel upper head void using all pressurizer heaters per procedure 41AO-1ZZ13. Log heater usage in Appendix S.
8.4.17 Verify that shutdown cooling entry conditions have been met (Thhot less than 350 and pressure less than 400 psia).
Record the following:
TiIIle HOT ID RCS pressure ID 8.4.17.1 Acce tance Criteria: Shutdown cooling entry conditions have been obtained.
Responsible Engineer 8.5 Restoration of Forced Flow NOTE All pressurizer heaters may be used for the remainder of the test.
8.5.1 Restore use of all pressurizer heaters pressure control or if if required for called out in applicable operations procedures. Stop data collection in Appendix S.
PV216 00D AEV.8/82
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PALO VERDE NUCLEAR GENERATING PROCEDURE NO.
STATION MANUAL 72PA"1RX03 REVISION NATURAL C IRCULATION TEST FROM 80% POWER Page 33 of 71 8.5.2 Slowly restore letdown if secured.
8.5.3 Take the following boron samples before the starting of the first pump, then at intervals specified and log in Appendix F:
Hot leg gl every 30 minutes Pressurizer every 60 minutes VCT every 60 minutes Boronometer reading every 10 minutes NOTE
1. - A slight. cooldown ~ould be made so upon restarting the first RCP, RCS temperature will not exceed 350 F or a mode change.
2. Ensure no void indication exists in upper head at the intiation of the first RCP.
8.5.4 Start RCP's per 410P-1RC01.
8.5.4.1 Restore main spray flow and start to equalize boron in the pressurizer and RCS.
8.5.6 Restore steam generator blowdown.
NOTE Step 8.5.7 and 8.5.8 may be performed concurrently with steps 8.5.8 through 9.1.
Notify Chemistry to sample CST as required.
8.5.7 Restore CST levels as required.
8.5.8 Revoke Special Test Exception (Later), when CST level is restored.
8.5.9 Verify at least two charging pumps are in operation.
8,5.10 Monitor boron samples obtained per step 8.5.3 until the following stable conditions exist or at the discretion of the RE.
PV216 000 REV. 8/82
0 PALO VERDE NUCLEAR GENERATING STATION MANUAL PROCEDURE NO.
72PA-1RX03 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 34 of 71 8.5.10.1 RCS boron concentration is changing less than approximately 10 ppm/hour.
8.5.10.2 Pressurizer boron concentration is within 10 ppm of RCS.
8.5.11 Terminate boron samples.
8.5.12 Terminate data collection suspended.
in all appendices if not already 9.0 RESTORATION 9.1 Stop collecting data on the following devices if used:
9.1.1 Strip chart recorders 9.1.2 Data acquisition systems.
9.1.3 Computer trend groups 9.2 The Responsible Engineer shall notify the Shift Supervisor that the test is complete.
Responsible Engineer 9.3 The Shift Supervisor should restore the plant to a condition stated in the Plant Daily Schedule per Station Manual Procedure.
9.4 Retrieve CEAC and CPC trip buffers then reset per 72MT-9SB01.
Attach a copy to this procedure test package.
10.0 DOCUMENTATION OF TEST RESULTS 10.1 All data sheets and tables shall have each blank filled out or marked "N/A" when not applicable. All N/A blanks will be explained in the Test Log (Appendix E). A slash may be used where allowed by this procedure.
PV216 000 REV. 8/82
PROCEDURE PALO VERDE NUCLEAR GENERATING NO.
STAT(ON MANUAL 72PA-1RX03 REVISION CIRCULATION TEST FROIi 80% POWER of
'ATURAL Page 35 71 10.2 A Test Log (Appendix E) shall be attached to this procedure to document unusual occurrences, prolonged time lapses, and subsequent reverification of prerequisites and other significant events which occur during the test.
10.3 All original strip charts, computer printouts, recorder charts, and other recorded data that are required by this procedure shall be identified by test procedure number and step number and shall be signed and dated by the Responsible Engineer These charts shall be attached to this procedure at its completion.
PV216 00D AEV.SI82
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PROCEDURE PALO VERDE NUCLEAR GENERATING NO. APPENDIX A STATION MANUAL 72PA-1RX03 Page 1 of 1 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 36 of 71 PREREQUISITE TESTING LIST 73HF-1ZZ10 RCS VENTS DYNAMIC TRANSIENT TEST 72PA-1RX37 RCS CALORIMETERIC FLOW MEASUREMENT (80%)
PV215 000 REV.8/82
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PROCEDURE PALO VEROE NUCLEAR GENERATlNG NO. APPEHDIX B STATION MANUAL 72PA-1RX03 Page 1 of 1 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 37 of 71 POST TRIP RECORD Sheet of TIME PY216 000 RFV. 8l82
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PALO VERDE NUCLEAR GENERATING PROCEDURE NO. APPENDIX C STATION MANUAL 72PA-1RX03 Page 1 of 1 REVISION NATURAL CIRCULATION TEST FROH 80% POWER Page 38 of 71 Sheet of AUXILIARYFEEDWATER USAGE LOG Flow to SG--
Auxiliary Feedwater Pump " SGl SG2 CST Level Date/Time AFA-POl AFB-P01 AFN-P01 ID ID ID Initials Indicate status change, ON or OFF Record ID number of instrument used and record the flow at least every 10 minutes when flow initiated or stopped.
Data Taken By PV216 000 REV.BI82
G~TH)N ONYX 0 PALO VERDE NUCLEAR GENERATING STATION MANUAL PROCEDURE NO.
72PA-1RX03 REVISION APPENDIX D Page 1 of 5 NATURAL CIRCULATION TEST FROM 80/ POWER Page 39 of 71 1.0 Boron Mixing Verification without RCP flow the pressurizer must be sprayed down using auxiliary spray. In addition to controlling pressure, the pressurizer should be mixed using auxiliary spray and the pressurizer heaters in order to increase boron mixing. If pressure cannot be adequately controlled in this manner, restart the pumps per procedure 410P-1RC01.
This appendix of the test procedure
.provides instructions for increasing the RCS boron doncentration under natural circulation conditions to verify mixing.
Upon initiating the boration and for the remainder of this appendix the following apply:
1. Only 1E grade pressurizer heaters will be used. In the event that more heater power is required for adequate plant control, other backup heater banks may be used and their usage recorded in Appendix S. Do not use proportional heaters.
2. It is desirable to operate all three charging pumps to maximize circulation through the CVCS. A minimum of two (2) pumps should be used to enhance flow through the boronometer.
3. To enhance boron mixing between the pressurizer and the remainder of the RCS, the use of the 1E pressurizer heaters should be maximized to the extent practical with auxiliary spray being used as required.
PV216 000 REV.Bi82
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PROCEDURE PALO VERDE NUCLEAR GENERATING NO. APPENDIX D STATION MANUAL 72PA-1RX03 Page 2 of 5 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 40 of 71
4. Try to maintain RCS pressure constant. This will require cautious uses of the auxiliary spray system.
5. With the use of the class pressurizer heaters (300 kw) it will be very doubtful that the pressurizer vith the RCS due to low auxiliary vill mix spray flows (8 gpm) in a timely manner. During calculation of shutdown margin take in account this unmixed volume and over borate the RCS.
6. Maintain any makeup to the RCS at a boron concentration greater than the RCS concentration to meet the requirements of Special Test Exception (Later).
7. This appendix, along with demonstrating boron mixing capabilities, will demonstrate condenstate storage capacity capabilities of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of hot standbys by maintaining an inventory log of the CST per Appendix C.
1.1 Log the initial conditions of this appendix RCS T ID RCS Pressure ID 1.2 Control RCS cold leg temperature within a target value of ~2 and an outer band of +5 of their current value.
NOTE Steps 1.3 and 1.4 should be run concurrently with the rest of Appendix D. If 73PA-1NA01 has been performed time. The plant was in hot standby during natural circulation may be added to step 1.4 requirements.
PV216 00D REV.SI82
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PHFOE~Vfow 0ÃII 7 PALO VERDE NUCLEAR GENERATING PROCEPURE NO. APPENDIX D STATION MANUAL 72PA-1RX03 Page 3 of 5 REVISION NATURAL CIRCULATION TEST FROM 80/ POWER Page 41 of 71 1.3 To meet the requirements of Ref. 3.2.6 the CST shall demonstrate at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of hot standby capacity. CST inventory and AFW flow monitored in Step 8.2.8. (Same as Step 8.2.10 in main procedure.)
Start Time Completion Time 1.4 The plant has been in hot standby for at least four hours.
72PA-1NA01 72PA-1RX03 2.0 Calculate shutdown margin required to reach cold shutdown per 72ST-9RX09 and attach calculation to this procedure.
Assume volume in the Pressurizer does not change from initial value. Account for this by adding additional boron to the Reactor Vessel. This shall be calculated by the following process.
2.1 (Later) 2.2 .Secure non IE class powered pressurizer heaters.
3.0 Boron mixing 3.1 Prepare to borate the RCS. Increase the boron concentration by a minimum of approximately 100 ppm, or the value calculated below, at a flow rate of approximately 5 ppm/min by injection to the charging pump suction. Boration parameters may be calculated using the HP-85 program or core data book. Record the following values:
RWT Boron Concentration ppm Primary Boron Concentration ppm Boration Flowrate gpm Gallons of RWT Water Req'd. gals Initial Totalizer Reading gals PV216.00D REV. 8/82
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PROCEDURE PALO VERDE NUCLEAR GENERATING NO. APPENDIX D STATION MANUAL 72PA"1RX03 Page 4 of 5 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 42 of 71 NOTE
1. The VCT level should be low enough to allow for the injection of the boron required to reach cold shutdown into the VCT prior to injection into the loops. This is not required though recommended to keep VCT concentration greater than the RCS concentration.
2. The number of charging pumps should not be changed during section 3.3 through 3.4.
3. IF additional boron is required to reach cold shutdown requirements, log the amount added and the start and stop times in the Test Procedure Log. The amount of boron or the calculations are not part of the Acceptance Criteria, only the capability of Boron mixing in the RCS during natural circulation.
4. Steps 3.2 and 3.3 should be performed simultaneously.
3.2 Initiate boration at the rate of 5 ppm/min using all three charging pumps if available. Continue adding boron until concentration has been increased by a minimum of approximately 100 ppm over the value calculated above.
Time Boration Started 3.3 Obtain the following boron samples at the specified locations and intervals. Record concentrations in Appendix F.
3;3.1 Hot Leg (30 mins.)
3.3.2 Pressurizer Surge Line (60 mins.)
3.3.3 VCT (60 mins.)
3.3.4 Boronometer (10 mins.)
PV216 00D RFV. 8/82
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PROCEDURE PALO VERDE NUCLEAR GENERATING NQ. APPENDIX D STATION MANUAL 72PA-1RX03 Page 5 of 5 REVISION NATURAL C IRCULATION TEST FROM 8 0% POWER Page 43 of 71 NOTE Maintain the following RCS parameters as steady as possible as the following values: Use.instruments from Section 5.1.
Pressurizer Pressure 2250 psia (2235 psia to 2265 psia)
Pressurizer Level approximately 30%-50%
RCS Temperature steady 3.4 Upon completion of the boration record the final totalizer reading and the time the boration was completed below.
Final Totalizer .Reading.- gals.
Time Boration Ended 3.5 Continue sampling boron concentrations until the acceptance criteria are satisfied. Record the final results below:
Hot Leg ppm Pressurizer ppm VCT ppm I
Time of Stabilization pp'm ACCEPTANCE CRITERIA:
The primary boron concentration has increased a minimum of approximately 100 ppm. 3 consecutive samples of the RCS hot leg within + 20 ppm.
3.6 Return to normal charging pump operation, if desired.
3.7 Determine the boron mixing delay time per Appendix G and record below. The cooldown portion of the test may continue without this calculation.
Boron Mixing Delay Time 3.8 The Acceptance Criteria has been met and the boration portion of this is complete.
PV216 000 REV.8/82
)Jf ff INFORSIA;I'HPi< ONLY PROCEDURE PALO VERDE NUCLEAR GENERATlNG NO. APPENDIX E STATlON MANUAL 72PA-1RX03 Page 1 of 1 REVISION NATURAL CIRCULATION TEST FRO>i 80/ POWER Page 44 of 71 TEST LOG Sheet of Date Time Entr PV216 000 AEV.8/82
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PROCEDURE PALO VERDE NUCLEAR GENERATING NO. APPENDIX H STATION MANUAL 72PA-1RX03 Page 2 of 3 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 48 of 71 DETERMINATION OF POWER/FLOW RATIO " CONT'D However, since (Ah) is not yet available to us, assuming M is the same at 80% and 100/,
3800 (0.8) = k MF (Ah)80 Where (Ah) = Enthalpy rise across core at 80/ power, BTU/1bm Therefore, Power- o-Flow Ration = [k (Ah)NC] / [ k (Ah)80]
0.8 0.8 (Ah)NC / (Ah)
B. Calculation
1. Record the following from the test copy of 72PA-1RX37 (RCS Calorimeteric Flow Measurement) performed during the 80% power plateau.
a
a. Core mass flow (M80) ibm/hr b
b. Core enthalpy rise (Ah ), BTU/1bm NOTES:
a. From Appendix J, Item 6
b. From C'alculation Sheet 1, Item 5 PV216 000 REV.8/82
w PROCEDURE PALO VERDE NUCLEAR GENERATING NO. APPENDIX H STATION MANUAL. 72PA-1RX03 Page 3 of 3 REVISION NATURAL CIRCULATION TEST FROM 80/ POWER Page 49 of 71 DETERMINATION OF POWER/FLOW RATIO - CONT'D NOTE Highest, reliable reading core exit thermocouple may be used as the T instrument.
2. Record the following RCS parameters. The values should be taken from the trend groups after natural circulaton has been verified (refer to procedure Step 8.2.13). The values should be averaged over at 30 minutes with Th being the average of the two hot 'east legs'ot and T ld being the average of the four cold legs.
cold
a. Average T ld, F cold
b. Average Th , F hot
c. Average Pressure, psia
3. Calculate the following using ASME Steam Tables:
a. Cold Leg Enthalpy, BTU/ibm
b. Hot Leg Enthalpy, BTU/ibm
c. Enthalpy Rise (Ah ), BTU/ibm
4. Calculate the power-to-flow ratio:
Power-to-Flow Ration = 0.8 (AhNC)/(Ah80)
Calculated by Reviewed by PV216 000 REV.8/82 H
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PROCEDURE PALO VERDE NUCLEAR GENERATING NO. APPENDIX I STATION MANUAL 72PA-1RX03 Page 1 of 4 REVISION NATURAL C IRCULATION TEST FROM 80% PO'iKR Page 50 of 71 STRIP CHART RECORDER ASSIGNMENTS Determine gain settings and zero suppression settings for the parameters listed in the tables of this appendix and record the chosen settings in the appropriate columns of those tables. The settings should be chosen to provide optimal resolution over the desired range of the parameters.
2. Connect the required signals to the strip chart recorders as listed in the tables of this appendix.
3. Label each chart trace with:
a. Parameter
b. Sensitivity C. Bias 4, Label each recorder chart with:
a. Chart Speed
b. Date c ~ Time Initials Procedure Number Recorder Serial Number Calibration Due Date PV216 00D 4EV.8/82
0 PROCEDURE PALO VEROE NUCLEAR GENERATING NO. APPENDIX I STATION MANUAL 72PA-1RX03 Page 2 of 4 REVISION NATURAL CIRCULATION TEST FROM 80% POMER Page 51 of 71 STRIP CHART RECORDER CONNECTIONS RECORDER NO. 1 CHANNEL COMPUTER- RANGE RECORDER SETTING VERIFIED NUMBER PARAMETER ID UNITS VOLTS GAIN ZERO BY Steam 0-100% 0"10V Generator 1 ,SGL1113A Level (VR Steam 0 100% 0 10V Generator 2 SGL1123A Level (WR 0-300 0"10V Pressurizer RCP102A psia Level
.0=.100% 0-10V Pressurizer RCL110Y Level Steam 0"1524 0"10V Generator SGP1023A psia 2 Pressure Computer ID are given as a reference. If different point ID's are required, log the ID's used in the test log.
PV216 OOD AEV.B/82
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PROCEDURE PALO VEROE NUCLEAR GENERATING NO. APPENDIX I STATION MANUAL 72PA-1RX03 Page 3 of 4 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 52 of 71 STRIP CHART RECORDER CONNECTIONS RECORDER NO. 2 CHANNEL COMPUTER>" RANGE RECORDER SETTING VERIFIED NUMBER PARAI'KTER ID UNITS VOLTS GAIN ZERO BY RCS Cold Leg 500" 0-1A RCT111Y 650 F 10V Temoerature RCS Cold Leg 0" 0-1B RCT115 600 F 10V Temoerature RCS Cold Leg 500- 0-2A RCT121Y 600 F 10V Temoerature RCS Cold Leg 0- 0-2B RCT125 600 F 10V Temoerature RCS Cold Leg 500- 0-2 RCT121X 650 F 10V Temoerature Note on page 3 of 4 PV216.00D REV,8182
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~OMLATKON OM;T PROCEDURE PALO VERDE NUCLEAR GENERATING NO. APPENDIX I STATION MANUAL 72PA-1RX03 Page 4 of 4 REVISION NATURAL CIRCULATION TEST FROM 80% P04'ER Page 53 of 71 STRIP CHART RECORDER CONNECTIONS RECORDER NO. 3 LATER HEAD LEVEL SAT MONITOR PRESSURIZE PRESSURE PRESSURIZE LEVEL PV216 000 REV,S/82
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PROCEDURE PALO VERDE NUCLEAR GENERATlNG NO. APPENDIX J STAT(ON MANUAL 72PA-1RX03 Page 1 of 2 REVlSlON NATURAL CIRCULATION TEST FROH 80% POWER Page 54 of 71 PLANT STATUS RECORD NOTE This record is intended to provide a record of equipment availability prior to and during the reactor trip. The status (i.e., Automatic, Standby, Out of Service, Manual, etc.) of the following systems and equipment are to be recorded immediately before the trip. In addition, any isolated valves or pumps, or other major pieces of equipment or systems which are out of service should be noted.
FWCS No. 1 (SGN FIC - 1111 at J-RtlN-B06)
Hain Feedwater Pump A, FWN"P01A
, FWCS No. 2 (SGN-FIC-1121 at J-RMN-B06)
Hain Feedwater Pump B, FWN-P01B SBCS Master Controller (SGN PIC-1010 at J-RMN-B06)
SBCS Valve Controllers (at J-RHN-B06)
SNG-PIC-1001 SGN-PIC-1005 SNG-PIC-1002 SGN-PIC"1006 SNG-PIC-1003 SGN-PIC"1007 SNG-PIC-1004 SGN-PIC-1008 SBCS Valve Positions (at J-RMN-B06) (Open/Closed)
SGN"ZS-1001 SGN-ZS-1005 SGN-ZS-1002 SGiN-ZS-1006 SGiN-ZS-1003 SGN-ZS>>1007 SGN-ZS-1004 SGN-ZS-1008 PV216 000 REV. 8/82
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PROCEDURE PALO VERDE NUCLEAR GENERATING NO. APPENDIX J STATION MANUAL 72PA-1RX03 Page 2 of 2 REVISION II NATURAL CIRCULATION TEST FROM 80% POVER Page 55 of 71 PLANT STATUS RECORD - CONT'D Presurizer Pressure Control Channel Selected (RCN-HS-100 at J-RMN-B04)
Proportional Heater Controls (at J-1M-B04)
'1 RCN-HS-100-3 RCN-HS-100-6 RCN-HS-100-4 RCN-HS-100-7 RCN-HS-100-5 RCN-HS-100>>8 Spray Valve Control Switch (RCN-HS-100-10 at J-R.'iN-B04)
Spray Valve Control Station (RCN-HIC-100 at J-EiN-B04)
Pressurizer Level Control Channel Selected (RCN-HS-100 at J-RMN-B04 Charging Pump Status (at J-KIN-B03)
CHA-HS-216 i CHA P01 CHA-HS-217 CHB-P01 CHA-HS-218. CHE-Pol Letdown Control (at J-RMN-B04)
RCN-HS-110 RCiN-HS-110-1 Recorded by RRS CEDiiCS Mode Selected PV216 00D AEV. 8/82
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POIehng)T' PALO VERDE NUCLEAR GENERATING PROCEDURE NO. APPEi%)IX K STATION MANUAL 72PA"1RX03 Page 1 of 1 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 56 of 71 N/A (Intentionally Blank)
PV216 000 REV,S/82
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PROCEDURE PALO VERDE NUCLEAR GENERATING NO. APPENDIX L STATION MANUAL 72PA"1RX03 .Page 1 of 4 REVISION NATURAL CIRCULATION TEST FROM 80! POWER Page 57 of 71 DATA ACQUISITION SYSTEM (DAS) CONFIGURATION NOTE As a minimum the following points shall be available to a DAS. If for any reason a point can not be recorded by a DAS, the RE shall determine its effect and if a equivalent point may be used or point can be recorded elsewhere. The if the substitution shall be logged in the test log.
Verify that all, of the signals listed in Sheets 2, 3, and 4 of this appendix have been input to a DAS.
2. Determine the gain and offset voltage settings if necessary, to provide the desired range of interest for the various parameters.
3. Re-verify all the connections, and settings, or computer inputs and initial the "verified by" column.
DAS's Available
1) PMS
2) TDAS
3) Data Logger
4) Trende Recorders (Appendix M)
5) Test Recorders PV216 00D REV,SI62
4l /'gj ~ >,p, jf LNjFOHiviA:~'>ON ONJ.Y e PALO VERDE NUCLEAR GENERATING STATION MANUAL PROCEDURE NO.
72PA-1RX03 REVISION APPENDIX L Page 2 of 4 NATURAL CIRCULATION TEST FROM 80% POVER A Page 58 of 71 GAIN +
DATA POINT ID DAS USED SETTING VERIFIED DATE Pressurizer Pressure Level Temperature Hot Leg 1 Hot Leg 1 Cold Leg 1A Cold Leg 1B Cold Leg 2A Cold Leg 2B Nuclear Power Steam Generator Level 1 Level 2 Pressure 1 Pressure 2 SG1 Steam Flow Line 1 Steam Flow Line 2 SG2 Steam Flow Line 1 Steam Flow Line 2 Charging Header Flow Aux Feed Flow SG1 SG2 if used PV2t6 000 AFV.S/82
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( STATION MANUAL NO.
72PA-1RX03 ~
APPENDIX L Page 3 of 4 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 59 of 71 GAIN +
DATA POINT ID RCP Speed RCP Pump D/P Core D/P SG D/P T/C on Reactor Vessel Head HJTc ADV Valve Position ADV Nitrogen Pressure Head Level %
Saturation Monitor RCS Head CST Level Highest Reliable Reading Thermocouple 2nd Highest Reliable Reading Thermocouple Boronometer Charging Flow Letdown Flow PV216 000 REV.BI62
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1NPOEiViiAT'lLoil 0 PROCEDURE PALO VERDE NUCLEAR GENERATING NO. APPENDIX L STATION MANUAL 72PA-1RX03 Page 4 of 4 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 60 of 71 GAIN A DATA POINT ID DAS USED RDT Level RDT Pressure RDT Temperature CEDMA Norm ACU Disch Temp CEDMB Norm ACU Disch Temp Inlet Temp Nuclear Cooling Water CEDMA Inlet Outlet CEDMB Inlet Outlet Performed by PV216 00D REV. 8/82
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'0 PALO VERDE NUCLEAR GENERATING STATION MANUAL PROCEDURE NO.
72PA-1RX03 REVISION APPENDIX Page 1 of M
1 NATURAL CIRCULATION TEST FROM 80% POWER Page 61 of 71 PARAMETERS AVAILABLE ON MAIN CONTROL BOARD RECORDERS PARAIIETER PANEL J-RMN" INSTRUMENT NO.
Steam Generator 1 B06 Downcomer Flow 1 SGN-FR-1113 Steam Feed Flow SGN-FR-1112 Steam Generator 2 B06 Downcomer Flow 2 SGN"FR-1123 Steam Feed Flow SGN-FR-1122 Steam Generator 1 Level B06 SGN"LR-1111 Steam Generator 2 Level B06 SGN-LR-1121 RCS Loop 1/Loop 2 T B04 RCN-TR-lllX RCN"TR-121X RCS Loop 1A/2B T Narrow Range B04- RCN-TR-115 c
RCN-TR-125 RCS Loop 1B/2A T Wide Range B04 RCN"TR-111Y c
RCN-TR-121Y Pressurizer Pressure B04 RCN-PR-100 Pressurizer Level B04 RCN-LR-110 Condensate Storage Tank Level B03 CTA-35A SAT Monitor/Reactor Vessel Level B03 SHA.-TR3 Temp Set Margin B03 SHA-TR4 CET/Core Exit Thermocouple PV216 000 RFV. 8/82
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72PA-1RX03 APPENDIX N Page 1 of 1 REVISION NATURAL CIRCULATION TEST FROM 80% POWER A Page 62 of 71 AUXILIARY SPRAY LOG Sheet of DATE/INITIAL TIME ON TIME OFF DATE/INITIAL TIME ON TIME OFF Data Taken By PV216 000 REV. 8/82
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~ g PROCEDURE PALO VERDE NUCLEAR GENERATING NO. APPENDIX 0 STATION MANUAL 72PA-1RX03 Page 1 of 2 REVISION NATURAL CIRCULAT10N TEST FROH 80K, POWER Page 63 of 71 PRESSURIZER DECALIBRATION CURVES RCN LT-103
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KN)FORMATION OTKV PROCEDURE PALO YERDE NUCLEAR GENERATING NO. APPENDIX 0 STATION MANUAL 72PA-1RXP3 Page 2 of' REVISION NATURAL CIRCULATION TEST FROM 80/ POWER Page 64 of 71 PRESSURIZER DECALIBRATION CURVES RCA(B) -LT-110X(Y)
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g,g, PROCEDURE PALO VERDE NUCLEAR GENERATING
( STATION MANUAL NO.
72PA-1RX03 REVISION APPENDIX P Page 1 of 2 NATURAL CIRCULATION TEST FROM 80/ POWER Page 65 of 71 RCS COOLDOWN PLOTS During the Natural Circulation Cooldown and Depressurization with Void Formation, plots of Thhott vs. time and pressurizer temperature vs. time are to be maintained and attached to this procedure.
Natural Circulation Cooldown:
Collect the data on the following'a'ge at"15 minute intervals. Hot Leg temperature vs. time until RCS temperature has dropped to the desired end point. Data should be taken at least every 10 F. Choose one of the core exit
,Q( thermocouples from QSPDS and use it for THOT.
Thermocouple Deoressurization with Void Formation Collect the data on the following page at 15 minute intervals. Plot pressurizer pressure, (RCP 102A or equivalent) vs. time unit the evolution is completed.
Pressurizer Pressure 'D PV216 00D BEY.SI82
I j
V ~l C
ANPP-30678 Page 3.
bcc's:
D. B. Karner A. C. Rogers W. E. Ide W. F. Quinn T. F. Quan K. E. Jones S. R. Frost K. McCandless LCTS Coordinator (w/a)
T. G. Woods K. W. Gross (w/a)
J. M. Allen (w/a)
J. R. Bynum (w/a)
P. F. Crawley
0. J. Zeringue R. Ferguson D. R. Canady J. Donahue R. Zimmerman (w/a)
W. H. Wilson (w/a)
S. Shepherd C. Ferguson
~ 4 l
1
PROCEDURE PALO VERDE NUCLEAR GENERATING NO. APPENDIX P STATION MANUAL 72PA-1RX03 Page 2 of 2 REVISION NATURAL CIRCULATION TEST FROM 80/ FOYER Page 66 of 71 RCS COOLDOWN PLOTS, CONT'D Sheet of Pressurizer HOT TCOLD HJTc 81 Subcooled Pressure
. Date/Time (TC = ) (TE-111Y) - ( ) Margin (ID ) Initial Data Taken By PV2)6 000 REV.8/82
(..~" .' 'i",i".~ i4~thi'lf li PROCEDURE PALO YERDE NUCLEAR GENERATlNG NO. APPENDIX g STATlON MANUAL 72PA-1RX03 Page 1 of 1 REVISION NATURAL CIRCULATION TEST PROII 80/ POWER A Page 67 of 71 HEATED JUNCTION THERHOCOUPLE DATA Sheet of This data is taken for information only.
This data is taken at least every 30 minutes and every 10 minutes during void formation.
Date/Time Sensor 1 8 Initial Data Taken By PV216 000 REV.BI82
f f
V Il ~ ) p kg $ )g .j l~,
0
PROCEDURE PALO VERDE NUCLEAR GENERATING NO. APPENDIX R STATION MANUAL 72PA-1RX03 Page 1 of 1 REVISION NATURAL CIRCULATION TEST FROM 80/o POVER Page 68 of 71 DW PUMP USAGE LOG Sheet of START TIME STOP TIME FLOW (gpm) Initial Data Taken By PV216 00D REV. 8/82
/
I
j'ALO VERDE NUCLEAR GENERATING STATION MANUAL PROCEDURE NO.
72PA-1RX03 APPENDIX S Page 1 of '1 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 69 of 71 PRESSURIZER HEATER USAGE LOG Sheet of DATE BANK ON TIME ON TIME OFF INITIAL Data Taken By PV216 000 REV.S/82
(I 0
4)
YNFOMiXI'Miil0 PALO VERDE NUCLEAR GENERATING PROCEDURE NO. APPENDIX T STATION MANUAL 72PA-1RX03 Page 1 of 1 REVISION NATURAL CIRCULATION TEST FROM 80% POWER Page 70 of 71 ATMOSPHERIC DUMP VALVE NITROGEN ACCUMLATOR PRESSURES Sheet of Date SGA-X01A X01B SGB-X01A X01B Initials Date/Time PI314 PI307 PI320 PI300 Read pressure at least every 15 minutes. Data Taken By NOTE Warn the control Room if Pressure approaches 300 psig in any accumulator such that air can be restored in a timely fashion. The above point may be monitored by a data acquisition system.
PV2l6 00D REV.B/82
1
<i'
~ tl PROCEDURE PALO VERDE NUCLEAR GENERATING NO. APPENDIX U STATION MANUAL 72PA"1RX03 Page 1 of 1 REVISION NATURAL CIRCULATION TEST FROM 80/o POWER Page 71 of 71 MISSING DATA SECTION INFORMATION RESP. DEPT.
7. 12 Test Exceptions APS 8.1.11 Test, Except,ion Number APS 8.2 (Note 3) Test Exception Number APS 8.2 (Note 4) Test Exception Number
'I APS 8.5.8 Test Exception Number APS Appendix D (Note 6) Test Exception Number APS Appendix D (2.1) Shutdown Margin Calculation APS Appendix I Recorders N3 APS PV216 000 REV. 8/82
0 1

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