ML20137J074
| ML20137J074 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/28/1985 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| GL-84-23, NUDOCS 8508300131 | |
| Download: ML20137J074 (26) | |
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O PS G Company Pubc Serece Electnc and Gas 80 Park Plaza, Newark, NJ 07101/ 201430 8217 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 Robert L. Mitti General Manager Nuclear Assurance and Regulation August 28, 1985 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:
Mr. Walter Butler, Chief Licensing Branch 2 Division of Licensing Gentlemen:
POWER ASCENSION PROGRAM CHANGES HOPE CREEK GENERATING STATION DOCKET NO. 50-354 At the August 1, 1985 accelerated power ascension test program meeting, PSE&G was requested to provide the NRC a schedule for expected submittals on modifications to the power ascension test program which may require NRC approval.
By letter dated August 21, 1985, PSE&G transmitted the first five detailed justifications on power ascension test modifications.
The balance of the justifications will be transmitted in accordance with the following schedule:
September 16, 1985 1.
Test Number 2 - Radiation Measurements Surveillance 2.
Test Number 10 - Average Power Range Monitor Calibration 3.
Test Number 12 - Reactor Core Isolation Cooling System 4.
Test Number 13 - High Pressure Coolant Injection System 5.
Test Number 14A - Selected Process Temperatures 6.
Test Number 1 - Chemical and Radiochemical 7.
Test Condition 4 - Natural Circulation Operation 8.
Test Number 9 - LPRM Calibration 8508300131 050828 PDR ADOCK 05000354 P
PDR h 00l The Energy People tlll zm nw m
Director o'f Nuclear 2
8/28/85 Reactor Regulation September 23, 1985 1.
Test Number 11 - Process Computer 2.
Test Number 28B - Recirculation Pump Trip - Two Pumps
-3.
Test Number 28D - Recirculation Pump Runback 4.
Test Number 32 - Reactor Water Cleanup System 5.
Test Number '16 - TIP Uncertainty 6.
Test Number 20 - Pressure Regulator 7.
Test Number-21A - Feedwater System Response 8.
Test Number 22 - Turbine Valve Surveillance September 30, 1985 1.
Test Number 23A - MSIV Functional Tests 2.
. Test Number 28E - Recirculation System Cavitation l
3.
Test Number 3 - Fuel Load 4.
Test Number 5 - Control Rod Drive / Hot Single Rod Scram Testing in Conjunction with Plant Scrams
'5.
Test Number 23B - MSIV Fuel. Isolation 6.
Test Number 24 - Relief Valves 7.
Test Number 31 - Drywell Piping Vibration 8.
Test Number 30 - Loss of Offsite Power Test Justification outlines for each of the aforementioned items with the exception of Test Number 30 - Loss of Offsite Power Test are attached for your information.
Test Number 30 will be. addressed in conjunction with PSE&G's response to Generic' Letter 23-84 "Special Low Power Testing and Training Recommendations for BWRs".
The forthcoming detailed justifications will be in the same format as those transmitted in the August 21, 1985 Jetter to NRC.
Please notify PSE&G if this format does not provide the necessary information for NRC's review.
Since the enclosed modifications impact finalizing the related power ascension testing detailed procedures, an expedited review is requested.
PSE&G is ready to meet with cognizant NRC personnel to discuss the proposed modifications should you require additional information.
Very truly yours, i
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' Director ~df Nuclear,.
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~8/28/85 Reactor. Regulation':
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- Attachment C.- D.H.-Wagner
~USNRC Licensing Project. Manager A.R. Blough USNRC Senior Resident Inspector t
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i TEST NUMBER 1 - CHEMICAL AND RADIOCHEMICAL TEST SIMPLIFICATION - REDUCED NUMBER OF TESTS REQUIREMENT:
DEMONSTRATE DESIGN CAPABILITY OF CHEMICAL CONTROL SYSTEM TO MAINTAIN WATER QUALITY WITHIN LIMITS IN THE REACTOR COOLANT SYSTEM OBJECTIVE:
COMPLIANCE WITH PLANT TECHNICAL SPECIFICATION REQUIREMENTS IS VERIFIED DURING TEST CONDITIONS 1,
3, 5 AND 6.
TO ESTABLISH THAT REACTOR COOLANT SYSTEM WATER QUALITY LIMITS ARE NOT EXCEEDED SIMPLIFICATION:
SUBSTITUTE THE PLANT TECHNICAL SPECIFICATION SURVEILLANCE PROCEDURES TO DEMONSTRATE COMPLIANCE WITH TECHNICAL SPECIFICATION REQUIREMENTS AND DELETE TESTING OF THE RWCU AND CONDENSATE DEMINERALIZER PERFORMANCE AT TEST CONDITION 3 PLANT TECHNICAL SPECIFICATIONS DEFINE THE MONITORING REQUIREMENTS FOR DEMONSTRATION OF COMPLIANCE WITH REACTOR COOLANT SYSTEM CHEMISTRY REQUIREMENTS PLANT TECHNICAL SPECIFICATION SECTIONS REQUIRE THAT AT LEAST ONCE PER 72 HOURS THE CHEMISTRY LIMITS ARE DETERMINED TO BI: WITHIN THE SPECIFIED LIMITS DEMONSTRATION OF THE PERFORMANCE OF THE RWCU AND THE CONDENSATE DEMINERALIZERS TO MAINTAIN WATER QUALITY IS ADEQUATELY VERIFIED AT TEST CONDITION 6 MEETS OBJECTIVES OF REGULATORY GUIDE 1.68 i
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e-e TEST NUMBER 2 - RADIATION MEASUREMENTS SURVEILLANCE SUBSTITUTE WITH SURVEILLANCE PROCEDURE REQUIREMENT:
PERFORM NEUTRON AND GAMMA RADIATION SURVEYS TO ESTABLISH THE ADEQUACY OF SHIELDING AND FOR IDENTIFICATION OF HIGH RADIATION ZONES AS DEFINED IN 10CFR PART 20 OBJECTIVE:
SURVEY BACKGROUND RADIATION THROUGHOUT THE PLANT SITE PRIOR TO FUEL LOADING, AND SUBSEQUENT TO FUEL LOADING, DURING REACTOR HEATUP, AND AT NORMAL POWER LEVELS (25%, 50%, AND 100% OF RATED POWER).
ALL POTENTIALLY HIGH RADIATION AREAS WILL BE SURVEYED SUBSTITUTION:
SUBSTITUTE HEALTH PHYSIC 3 SURVEILLANCE PROCEDURE ASSOCIATED WITH COMPLIANCE TO RADIATION DOSE RATE AND SURVEYS, FOR TEST NUMBER 2 RADIATION MEASUREMENTS WILL BE COMPARED TO REQUIREMENTS DEFINED IN 10CFR20, WHICH ASSURES PROTECTION OF PERSONNEL DURING PLANT OPERATION COMPLYING WITH THE PLANT HEALTH PHYSICS SURVEILLANCE PROCEDURE REQUIREMENTS SATISFIES THE OBJECTIVES OF REGULATORY GUIDE 1.68 l
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TEST NUMBER 3 - FUEL LOADING TEST SIMPLIFICATION - ELIMINATE FUEL LOADING CHAMBERS REQUIREMENT:
PREVENT INADVERTENT CRITICALITY DURING I2;iTIAL FUEL LOADING OBJECTIVE:
LOAD FUEL SAFELY AND EFFICIENTLY TO THE FULL CORE SIZE SIMPLIFICATION:' SIMPLIFY THE FUEL LOADING PROCEDURE BY REPLACING THE FUEL LOADING CHAMBERS (FLCs) WITH THE SOURCE RANGE MONITOR (SRM) INSTRUMENTATION AND LOWERING THE CURRENT MINIMUM REQUIRED SRM COUNT RATE FROM 3 COUNTS PER SECOND (CPS)
TO APPROXIMATELY 0.7 CPS OR LESS.
QA/QC DURING FUEL DESIGN AND MANUFACTURING ENSURE THAT THE FUEL IS MANUFACTURED AS SPECIFIED
- - PRE-FUEL LOADING PRECAUTIONS PROVIDE SIGNIFICANT ASSURANCE AGAINST INADVERTENT CRITICALITY FUEL WILL BE INITIALLY LOADED BETWEEN THE NEUTRON SOURCE IN ITS ALTERNATE LOCATION AND THE CLOSEST SRM SIMPLIFIED FUEL LOADING WILL USE THE FIXED LOCATION SRMs FOR MONITORING OF THE NEUTRON FLUX AS WELL AS LOCATING THE NEUTRON SOURCES IN THEIR ALTERNATE LOCATIONS WHICH ARE CLOSER TO THE FIXED SRMs FUEL LOADING SEQUENCE WILL BE MODIFIED SUCH THAT INITIAL FUEL LOADING WILL BEGIN BETWEEN AN SRM DETECTOR AND A NEUTRON SOURCE ALL CONTROL RODS WILL BE INSERTED DURING FUEL LOADING ANALYSIS INDICATE THAT AS MANY AS 16 FUEL BUNDLES CAN BE LOADED WITH THE CONTROL RODS WITHDRAWN AND STILL MAINTAIN SUBCRITICALITY LOADING WILL CONTINUE IN A SPIRAL PATTERN AROUND THE INITIAL SRM UNTIL THE FULL CORE IS LOADED REGULATORY GUIDE 1.68 OBJECTIVE MET 28 AUGUST 1985
m TEST CONDITION 4 - NATURAL CIRCULATION OPERATION DELETE TEST CONDITION REQUIREMENT:
TESTING OF CORE' PERFORMANCE AND CONTROL SYSTEM RESPONSE OBJECTIVE:
PERFORM TESTING AT THE EXTREMES OF POSSIBLE OPERATING MODES FOR FACILITY SYSTEMS IF THE FACILITY IS INTENDED TO BE OPERATED IN THESE MODES.
DELETION:
DELETE ALL TESTING IN TEST CONDITION 4 OPERATION AT NATURAL CIRCULATION CONDITIONS IS NOT AN INTENDED MODE OF OPERATION EXTENSIVE SPECIAL TESTING AT NATURAL CIRCULATION HAS PREVIOUSLY BEEN PERFORMED THOROUGHLY CHARACTERIZING THE PERFORMANCE OF NATURAL CIRCULATION CONDITIONS TESTING OF PLANT SYSTEMS IS PERFORMED OVER A WIDE RANGE OF OPERATING CONDITIONS REPRESENTING THE EXTREMES OF POSSIBLE OPERATING MODES INTENDED FOR THE PLANT 28 AUGUST 1985
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. TEST NUMBER 5 - CONTROL ROD DRIVE / HOT SINGLE ROD SCRAM TESTING IN CONJUNCTION WITH PLANT SCRAMS
. REQUIREMENT:
. DEMONSTRATES THE PERFORMANCE OF THE CONTROL ROD DRIVE SYSTEM OVER THE FULL RANGE OF PRIMARY COOLANT CONDITIONS OBJECTIVE:
PERFORM SCRAM TIME TESTING DURING PREOPERATIONAL TESTING, COLD CONDITIONS AFTER FUEL HAS BEEN LOADED, AT HOT. CONDITIONS WITH RATED REACTOR PRESSURE AND IN CONJUNCTION WITH PLANNED SCRAMS FROM OTHER STARTUP TESTS CONJUNCTION:
PERFORM INDIVIDUAL CONTROL ROAD SCRAM TIMES AT HOT CONDITIONS IN CONJUNCTION WITH OTHER PLANT SCRAMS DURING THE POWER ASCENSION PROGRAM DATA ACQUISITION SYSTEM WILL RECORD THE SCRAM TIME DATA FROM ALL CONTROL RODS DURING A FULL CORE SCRAM
, PLANNED SCRAMS JLT TC1 or TC2 CAN BE USED TO OBTAIN THE SCRAM TIME DATA ALL CONTROL RODS-WILL BE TESTED DURING THE PREOPERATIONAL AND COLD CONTROL ROD DRIVE TESTING PHASE ANALYSIS CAN BE PERFORMED TO JUSTIFY LACK OF SCRAM DATA OF THOSE CONTROL RODS NOT FULLY WITHDRAWN DURING SCRAMS CONTROL ROD SCRAM TIME CAN BE RECORDED DURING INADVERTANT SCRAMS AT POWER MEETS INTENT OF REGULATORY GUIDE 1.68 28 AUGUST 1985
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TEST NUMBER 9 - LPRM CALIBRATION TEST SIMPLIFICATION - REDUCED NUMBER OF TESTS REQUIREMENT:
INCORE NEUTRON FLUX INSTRUMENTATION USED TO CALCULATE THERMAL POWER LEVEL BE CALIBRATED AND OPERATION VERIFIED OBJECTIVE:
VERIFICATION OF INSTRUMENTATION RESPONSE DURING CONTROL ROD MOVEMENT SIMPLIFICATION:
DELETE HEATUP TESTING OF THE LPRM RESPONSE LPRM RESPONSE DURING HEATUP IS NOT REQUIRED BY REGULATIONS DURING HEATUP, MANY DETECTORS HAVE SIGNALS WHICH ARE LESS THAN THE DOWNSCALE VALUE LPRM RESPONSE CAN READILY BE OBSERVED BY THE OPERATOR DURING CONTROL ROD MOVEMENT AT POWER LEVELS CALIBRATION OF THE LPRM SYSTEM AT SEVERAL TEST CONDITIONS SATISFIES THE OBJECTIVES OF REGULATORY GUIDE 1.68
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TEST NUMBER 10 - AVERAGE POWER RANGE MONITOR CALIERATION SUBSTITUTE WITH TECHNICAL SPECIFICATION SURVEILLANCE i
REQUIREMENT:
THE INCORE NEUTRON FLUX INSTRUMENTATION BE CALIBRATED AND PROPER OPERATION VERIFIED DifRING POWER ASCENSION TESTING OBJECTIVE:
AVERAGE POWER RANGE MONITOR (APRM) CALIBRATION, IS PERFORMED OVER A WIDE RANGE OF OPERATING CONDITIONS.
SUBSTITUTION:
SUBSTITUTE WITH PLANT TECHNICAL SPECIFICATION SURVEILLANCE PROCEDURES PLANT TECHNICAL SPECIFICATIONS DEFINE THE CALIBRATION REQUIREMENTS FOR THE APRM SYSTEM AS PART OF THE SURVEILLANCE REQUIREMENTS FOR THE REACTOR PROTECTION SYSTEM TECHNICAL SPECIFICATION CALIBRATION SHALL CONSIST OF THE ADJUSTMENT OF THE APRM CHANNEL TO CONFORM TO THE POWER VALUES CALCULATED BY A HEAT BALANCE DURING OPERATION COMPLIANCE WITH THESE TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS MEETS THE OBJECTIVES OF REGULATORY GUIDE 1.68 28 AUGUST 1985 l
TEST NUMBER 11 - PROCESS COMPUTER TEST SIMPLIFICKTION - DELETE 0D-11 TESTING REQUIREMENT:
DEMONSTRATE OPERABILITY OF THE CONTROL ROOM COMPUTER SYSTEM OBJECTIVE:
VALIDATE THAT THE PROCESS COMPUTER IS RECEIVING CORRECT INPUTS FROM PROCESS VARIABLES AND THAT PERFORMANCE CALCULATIONS ARE BEING PERFORMED CORRECTLY UNDER PLANT OPERATING CONDITIONS SIMPLIFICATION:
DELETE TESTING OF THE OD-ll OPTION, PCIOMR MONITORING EXTENSIVE TESTING OF EACH OPTION OF THE PROCESS COMPUTER IS PERFORMED TO SATISFY SYSTEM DESIGN REQUIREMENTS BARRIER FUEL EXPERIENCE TO DATE SUPPORT ELIMINATION OF PCIOMR RECOMMENDATIONS HOPE CREEK GENERATING STATION WILL HAVE PCI RESISTANT BARRIER FUEL, THEREFORE OPERATION OF THIS OPTION IS NOT REQUIRED, AND TESTING WILL NOT BE REQUIRED i
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K TEST NUMBER 12 - REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM TEST SIMPLIFICATION - REDUCED NUMBER OF TESTS OBJECTIVE:
VERIFY THE PROPER OPERATION OF THE RCIC SYSTEM OVER ITS REQUIRED OPERATING PRESSURE RANGE REQUIREMENT:
DEMONSTRATION OF THE OPERABILITY OF STEAM-DRIVEN ENGINEERED SAFETY FEATURES SIMPLIFICATION:
DELETE CONTROLLER TUNING AT LOW REACTOR PRESSURES EXPERIENCE AT PREVIOUS PLANTS HAS SHOWN THAT CONTROLLER TUNING AT THE LOW PRESSURE CONDITION DOES NOT RESULT IN OPTIMUM PERFORMANCE AT HIGHER PRESSURES SYSTEM TUNING WILL BE PERFORMED AT NEAR RATED REACTOR PRESSURE SYSTEM WILL BE RETESTED AT LOWER PRESSURES FOR VERIFICATION OF CONTROL LOOP SETTINGS A SET OF DEMONSTRATION TESTS WILL BE PERFORMED WITH THE FINAL SETTINGS AFTER ALL FINAL CONTROLLER AND SYSTEM ADJUSTMENTS HAVE BEEN DETERMINED OBJECTIVES OF REGULATORY GUIDE 1.68 ARE MET 28 AUGUST 1985
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e TEST NUMBER 13 - HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM TEST SIMPLIFICATION - REL'JCED NUMBER OF TESTS OBJECTIVE:
VERIFY THE PROPER OPERATION OF THE HPCI SYSTEM OVER ITS REQUIRED OPERATING PRESSURE RANGE REQUIREMENT:
DEMONSTRATION OF THE OPERABILITY OF STEAM-DRIVEN ENGINEERED SAFETY FEATUREO SIMPLIFICATION:
DELETE CONTROLLER TUNING AT LOW REACTOR PRESSURES EXPERIENCE AT PREVIOUS PLANTS HAS SHOWN T!1AT CONTROLLER TUNING AT THE LOW PRESSURE CONDITION DOES NOT RESULT IN OPTIMUM PERFORMANCE AT HIGHER PRESSURES SYSTEM TUNING WILL BE PERFORMED AT NEAR RATED REACTOR PRESSURE SYSTEM WILL BE RETESTED AT LOWER PRESSURES FOR VERIFICATION OF CONTROL LOOP SETTINGS A SET OF DEMONSTRATION TESTS WILL BE PERFORMED WITH THE FINAL SETTINGS AFTER ALL FINAL CONTROLLER AND SYSTEM ADJUSTMENTS HAVE BEEN DETERMINED OBJECTIVES OF REGULATORY GUIDE 1.68 ARE MET I
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TEST NUMBER 14A - SELECTED PROCESS TEMPERATURES SUBSTITUTE WITH TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT:
REGULATORY GUIDE 1.68 DOES NOT SPECIFICALLY ADDRESS REQUIREMENTS FOR MEASUREMENT OF SELECTED PROCESS TEMPERATURES OBJECTIVE:
ESTABLISH LOW PUMP SPEED LIMITS FOR THE RECIRCULATION PUMPS TO AVOID COOLANT TEMPERATURE STRATIFICATION IN THE REACTOR PRESSURE VESSEL (RPV) BOTTOM HEAD REGION, AND TO ASSURE THAT IDLE RECIRCULATION LOOP TEMPERATURE DIFFERENTIALS ARE WITHIN TECHNICAL SPECIFICATION LIMITS PRIOR TO RESTARTING RECIRCULATION PUMP (S)
SUBSTITUTION:
SUBSTITUTE TECHNICAL SPECIFICATION SURVEILLANCE PROCEDURES ASSOCIATED WITH THE DETERMINATION OF RECIRCULATION LOOP TEMPERATURE DIFFERENTIALS PLANT TECHNICAL SPECIFICATIONS PLACE LIMITS ON THE TEMPERATURE DIFFERENTIAL BETWEEN THE IDLE LOOP (S) AND THE REACTOR PRESSURE VESSEL STEAM SPACE COOLANT TEMPERATURE TESTING OF THE MINIMUM RECIRCULATION PUMP SPEED TO DETERMINE APPLICABLE STRATIFICATION LIMITS ASSURES PROPER PERFORMANCE OF THE RECIRCULATION SYSTEM OCCURS AT LOW PUMP SPEEDS COMPLIANCE WITH THE PLANT TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS WILL SATISFY EXISTING TESTING REQUIREMENTS 28 AUGUST 1985
TEST NUMBER 16 - TIP UNCERTAINTY JUSTIFY TEST DELETION REQUIREMENT:
NO SPECIFIC REGULATORY REQUIREMENT OBJECTIVE:
DEMONSTRATES THE REPRODUCIBILITY OF THE TRAVERSING INCORE PROBE (TIP) SYSTEM DELETION:
DELETE TEST NUMBER 16 THE BASIS FOR THIS TEST IS TO ASSURE REASONABLE COMPLIANCE WITH THE TIP UNCERTAINTY APPLIED IN THE GETAB CALCULATION OF THE SAFETY LIMIT MCPR DETERMINATION OF THE TIP UNCERTAINTY AT PREVIOUS BWR'S HAS DEMONSTRATED THAT THE UNCERTAINTIES ARE WITHIN REASONABLE LIMITS 28 AUGUST 1985
TEST NUMBER 20 - PRESSURE REGULATOR TEST SIMPLIFICATION - REDUCED NUMBER OF TESTS REQUIREMENT:
DEMONSTRATE OPERABILITY AND PERFORMANCE OF THE PRESSURE REGULATOR SYSTEM OBJECTIVE:
DETERMINE THE RESPONSE OF THE PRESSURE REGULATOR SYSTEM TO RAPID PRESSURE SETPOINT CHANGES AND DEMONSTRATE TAKEOVER CAPABILITY OF THE BACKUP PRESSURE REGULATOR SIMPLIFICATION:
DELETE THE PRESSURE REGULATOR TESTS AT TEST CONDITION 4, THE BACKUP PRESSURE REGULATOR TAKEOVER TESTING AT TEST CONDITION 5 AND THE AUTOMATIC LOAD FOLLOWING MODE TESTS AT TEST CONDITIONS 3 AND 6 TESTING AT TEST CONDITION 4 IS BOUNDED BY TESTING AT TEST CONDITION 3 AND 5, AND IS NOT AN INTENDED MODE OF OPERATION TESTING OF THE BACKUP PRESSURE REGULATOR AT TEST CONDITION 5 CAN BE DELETED SINCE TESTING AT TEST CONDITIONS 2, 3 AND 6 PROVIDES ADEQUATE DEMONSTRATION OF THE CAPABILITY OF THE BACKUP PRESSURE REGULATOR TO CONTROL PRESSURE IN THE EVENT OF A FAILURE OF THE CONTROLLING PRESSURE REGULATOR ALF' MODE WILL BE DISABLED AND, THEREFORE, NO TESTING OF THE ALF MODE IS REQUIRED FOR THE PRESSURE REGULATOR SYSTEM 28 AUGUST 1985
TEST NUMBER 21A - FEEDWATER SYSTEM RESPONSE TEST SIMPLIFICATION - REDUCED NUMBER OF TESTS REQUIREMENT:
DEMONSTRATE OPERABILITY AND PERFORMANCE OF THE FEEDWATER CONTROL SYSTEM OBJECTIVE:
VERIFY THAT THE FEEDWATER SYSTEM RESPONSE PROVIDES ACCEPTABLE REACTOR WATER LEVEL CONTROL DURING ALL POWER AND FEEDWATER PUMP MODES SIMPLIFICATION:
DELETE WATER' LEVEL SETPOINT AND MANUAL FEEDWATER FLOW TESTS AT TEST CONDITION 4, AND AUTOMATIC LOAD FOLLOWING (ALF) MODE TESTS AT TEST CONDITION 6 TESTING AT TEST CONDITION 4 IS BOUNDED BY TESTING AT TEST CONDITION 3 AND 5, AND IS NOT AN INTENDED MODE OF MODIFICATION ALF MODE OF OPERATION WILL BE DISABLED, THEREFORE, TESTING OF THE FEEDWATER SYSTEM WILL NOT BE REQUIRED IN THE ALF MODE l
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TEST NUMBER 22 - TURBINE VALVE SURVEILLANCE SUBSTITUTION WITH TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT:
DEMONSTRATION OF THE OPERABILITY OF THE TURBINE STOP VALVES, TURBINE CONTROL VALVES AND TURBINE BYPASS VALVES OBJECTIVE:
DETERMINES THE OPERABILITY OF THE TURBINE STOP VALVES (TSV), TURBINE CONTROL VALVES (TCV) AND TURBINE BYPASS VALVES (BPV) AND THE MAXIMUM POWER LEVEL AT WHICH SURVEILLANCE CAN BE PERFORMED WITHOUT SCRAM SUBSTITUTION:
PLANT TECHNICAL SPECIFICATION SURVEILLANCE PROCEDURES ASSOCIATED WITH TURBINE VALVE SURVEILLANCE TESTING FOR TEST NUMBER 22 THE PLANT TECHNICAL SPECIFICATIONS DEFINE THE REQUIREMENTS FOR DEMONSTRATION OF COMPLIANCE FOR TURBINE VALVE OPERABILITY THE MAXIMUM POWER CONDITION FOR TESTING WILL BE SELECTED BY EVALUATING THE DATA BASE FROM PREVIOUS BWR STARTUP AND OPERATION THE ADEQUACY OF THIS POWER LEVEL WILL BE DEMONSTRATED BY THE TURBINE VALVE SURVEILLANCE TESTING REQUIRED BY THE TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS PERFORMING THE TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS SATISFIES THE OBJECTIVES OF REGULATORY GUIDE 1.68 4
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TEST NUMBER 23A - MSIV FUNCTIONAL TESTS SUBSTITUTE WITH TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT:
DEMONSTRATE THE OPERABILITY AND RESPONSE OF THE MAIN STEAM ISOLATION VALVES OBJECTIVE:
DETERMINE THE FUNCTIONAL PERFORMANCE AND INDIVIDUAL FAST CLOSURE TIME OF EACH MSIV AT HEATUP, BETWEEN TEST CONDITIONS 1 AND 3, AND THE MAXIMUM POWER LEVEL AT WHICH FULL INDIVIDUAL CLOSURE CAN BE PERFORMED WITHOUT SCRAM SIMPLIFICATION:
SUBSTITUTE PLANT TECHNICAL SPECIFICATION SURVEILLANCE PROCEDURES FOR MSIV TIMING AND OPERABILITY REQUIREMENTS THE PLANT TECHNICAL SPECIFICATIONS DEFINE THE REQUIREMENTS FOR DEMONSTRATION OF COMPLIANCE FOR MSIV RESPONSE TIMES AND OPERABILITY THE MAXIMUM POWER CONDITION FOR TESTING WILL BE SELECTED BY EVALUATING THE DATA BASE FROM PREVIOUS BWR STARTUP'S AND OPERATIONS TESTING TO DETERMINE THE MAXIMUM POWER LEVEL AT WHICH THE MSIV SURVEILLANCE TESTING CAN BE PERFORMED WITHOUT SCRAM CAN BE PERFORMED AT A LATER TIME PERFORMING THE TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS SATISFIES THE OBJECTIVES OF REGULATORY GUIDE 1.68 28 AUGUST 1985 i
TEST NUMBER 238 - MSIV FULL ISOLATION TEST SIMPLIFICATION - EXPAND TEST WINDOW REQUIREMENT:
DEMONSTRATE THAT THE DYNAMIC RESPONSE OF THE PLANT IS IN ACCORDANCE WITH DESIGN FOR THE CASE OF AUTOMATIC CLOSURE OF ALL MAIN STEAM ISOLATION VALVES OBJECTIVE:
PERFORM A SIMULTANEOUS FULL CLOSURE OF ALL MSIV'S AT TEST CONDITION 6.
TRANSIENT BEHAVIOR OF PLANT AND ASSOCIATED SYSTEMS WILL BE DETERMINED DURING AND FOLLOWING THE MAIN STEAM ISOLATION SIMPLIFICATION:
SHOULD AN MSIV FULL ISOLATION OCCUR AT A POWER LEVEL LESS THAN 1004 (>70%),
SUBSTITUTION OF THE LOWER POWER LEVEL RESULTS WITH APPROPRIATE ANALYSIS AND EXTRAPOLATION FOR THE HIGHER POWER LEVEL RESULTS, WILL BE MADE TO DEMONSTRATE REGULATORY GUIDE 1.68 OBJECTIVES ARE STILL MET THE MSIV FULL CLOSURE AT TEST CONDITION 6 WILL PROVIDE DATA THAT WILL VERIFY COMPLIANCE WITH THE LEVEL 1 AND LEVEL 2 ACCEPTANCE CRITERIA.
HOWEVER, SHOULD A FULL CLOSURE OF THE MSIV'S OCCUR AT A LOWER POWER LEVEL (>70%) SUPPORTING ANALYSIS WILL CONFIRM THAT THE LEVEL 1 AND LEVEL 2 CRITERIA WILL STILL BE MET.
PERFORMANCE OF THE REACTOR AND ITS ASSOCIATED SYSTEMS DURING THIS TEST IS WELL DOCUMENTED BASED ON DATA OBTAINED FROM PREVIOUS PLANT STARTUPS, IT CAN BE SHOWN, THAT THE RESULTS FROM THE TEST AT A LOWER POWER LEVEL MAY BE EXTRAPOLATED TO THE HIGH POWER CRITERIA N
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TEST NUMBER 24 - RELIEF VALVES TEST SIMPLIFICATION - REDUCED NUMBER OF TESTS REQUIREMENTS:
DEMONSTRATE THE PROPER OPERABILITY OF THE MKIN STEAM RELIEF VALVES OBJECTIVE:
VERIFY THE OPERABILITY, RESPONSE TIMES, RELIEVING CAPACITIES, SET POINTS AND RESET PRESSURES FOR THE MAIN STEAM RELIEF VALVES SIMPLICATION:
DELETE MAIN STEAM RELIEF VALVE TESTING AT LOW REACTOR PRESSURE ACTUATION OF RELIEF VALVES AT LOW PRESSURES HAS BEEN IDENTIFIED AS A CONTRIBUTOR TO VALVE SEAT DAMAGE CAUSED BY RESEATING AGAINST ABNORMALLY LOW PRESSURE QUALIFICATION TESTS PERFORMED ON THESE VALVES DEMONSTRATE THAT THE DESIGN SATISFIES SPECIFIED REQUIREMENTS BENCH TESTS ARE PERFORMED ON EACH RELIEF VALVE TO PROVIDE ASSURANCE THAT EACH ASSEMBLY WILL PERFORM SATISFACTORILY PREOPERATIONAL TESTS CHECK OUT THE ADEQUACY OF ELECTRICAL POWER SUPPLY, LOGIC AND AIR SUPPLY TECH SPEC SURVEILLANCE VERIFIES AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) VALVES OPERABILITY TESTING OF THE RELIEF VALVES AT RATED REACTOR PRESSURE BETWEEN 20-30% CORE THERMAL POWER DEMONSTRATES THE ACCEPTABLE PERFORMANCE OF THE RELIEF VALVES i
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TEST NUMBER 28B - RECIRCULATION PUMP TRIP - TWO PUMPS IN CONJUNCTION WITH TEST NUMBER 25 REQUIREMENT:
DEMONSTRATE THAT THE DYNAMIC RESPONSE OF THE PLANT IS IN ACCORDANCE WITH DESIGN FOR LIMITING REACTOR COOLANT PUMP TRIPS OBJECTIVE:
TWO PUMP RECIRCULATION PUMP TRIP PERFORMED AT TEST CONDITION 3 WILL VERIFY THE PERFORMANCE OF THE RPT CIRCUIT AND THE RECIRCULATION PUMP FLOW COASTDOWN CONJUNCTION:
PERFORM THIS TEST IN CONJUNCTION WITH TEST NUMBER 25, GENERATOR LOAD REJECTION, AT TEST CONDITION 6 DURING TEST 25, GENERATOR LOAD REJECTION AT TEST CONDITION 6, A TWO PUMP TRIP OCCURS AS THE RESULT OF THE PROTECTIVE RPT FUNCTION DATA ACQUISITION SYSTEM WILL RECORD THE FLOW COASTDOWN DATA DURING THE TRANSIENT ALONG WITH THE DATA NECESSARY TO DEMONSTRATE THE COMPLIANCE OF THE GENERATOR LOAD REJECTION TO TEST NUMBER 25 ACCEPTANCE CRITERIA MEETS INTENT OF REGULATORY GUIDE 1.68 28 AUGUST 1985
.o TEST NUMBER 28D - RECIRCULATION PUMP RUNBACK IN CONJUNCTION WITH TEST NUMBER 21C REQUIREMENT:
VERIFY PERFORMANCE OF RECIRCULATION FLOW CONTROL SYSTEM OBJECTIVE:
SIMULATE A LOSS OF FEEDWATER PUMP AT TEST CONDITION 3 NEAR RATED RECIRCULATION FLOW TO DETERMINE THE ADEQUACY OF THE RECIRCULATION PUMP RUNBACK FEATURE IN PREVENTING A SCRAM CONJUNCTION:
PERFORM THIS TEST IN CONJUNCTION WITH TEST NUMBER 21C, FEEDWATER PUMP TRIP AT TEST CONDITION 6 DURING TEST NUMBLR 21C FEEDWATER PUMP TRIP AT TEST CONDITION 6, A RECIRCULATION PUMP RUNBACK OCCURS AS THE RESULT OF THE FEEDWATER PUMP TRIP THIS TESTING RESULTS IN AN ACTUAL DEMONSTRATION OF THE RECIRCULATION PUMP RUNBACK CIRCUIT UNDER REAL AS OPPOSED TO SIMULATED CONDITIONS MEETS INTENT OF REGULATORY GUIDE 1.68 4
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TEST NUMBER 28E - RECIRCULATION SYSTEM CAVITATION TEST SIMPLIFICATION PEQUIREMENT:
VERIFY PERFORMANCE OF THE RECIRCULATION FLOW CONTROL SYSTEM OBJECTIVE:
VERIFY THAT RECIRCULATION SYSTEM CAVITATION WILL NOT OCCUR IN THE OPERABLE REGION'OF THE POWER FLOW MAP SIMPLIFICATION:
SIMPLIFY TESTING SUCH THAT OPERATION AT THE ANALYTICALLY DETERMINED CAVITATION LIMIT IS PERFORMED TO DETERMINE IF CAVITATION OCCURS AND IF THE RECIRCULATION RUNBACK FEATURE IS ACTUATED CAVITATION INTERLOCKS DESIGNED TO PREVENT OPERATION IN REGIONS OF POTENTIAL PUMP CAVITATION ARE ANALYTICALLY DETERMINED ON A CONSERVATIVE BASIS SIMPLIFIED TESTING WILL VERIFY THAT CAVITATION DOES NOT OCCUR AT OR ABOVE THE CAVITATION INTERLOCKS POWER WILL BE REDUCED BY INSERTING CONTROL RODS DOWN TO THE CAVITATION INTERLOCK AND VERIFYING THAT THE INTERLOCK IS ACTUATED TESTING WILL BE ACCOMPLISHED BY LOCKING BOTH RECIRCULATION PUMP M-G SET SCOOP TUBES IN POSITION, SO THAT RECIRCULATION RUNBACK CANNOT OCCUR 28 AUGUST 1985
TEST NUMBER 31 - DRYWELL PIPING VIBRATION TEST SIMPLIFICATION REQUIREMENT:
VERIFY BY OBSERVATIONS AND MEASUREMENTS THAT PIPING AND COMPONENT MOVEMENTS, VIBRATIONS AND EXPANSIONS ARE ACCEPTABLE OBJECTIVE:
VERIFY THAT MAIN STEAM AND RECIRCULATION PIPING VIBRATION IS WITHIN ACCEPTABLE LIMITS SIMPLIFICATION:
ELIMINATE THE REMOTE VIBRATION AND DEFLECTION MEASUREMENTS TAKEN DURING RECIRCULATION PUMP TRIPS AND RESTARTS, AND FOR TURBINE STOP OR CONTROL VALVE CLOSURES RESPONSE OF THE MAIN STEAM AND RECIRCULATION PIPING DURING OPERATING TRANSIENT LOAD TESTING IS DETERMINED BY ANALYZING TEST DATA AND COMPARING THE RESULTS TO ACCEPTANCE CRITERIA PREVIOUS PLANT STARTUP RESULTS INDICATE THAT VIBRATION AND DEFLECTION MEASUREMENTS OF MAIN STEAM AND RECIRCU PIPING DURING RECIRCULATION PUMP TRIPS AND RESTARTS AND DURING TURBINE STOP OR CONTROL VALVE CLOSURES ARE WELL BELOW THE PRESCRIBED CRITERIA LIMITS DETERMINING THE OPERATING TRANSIENT LOADS ON THE MAIN STEAM AND RECIRCULATION PIPING WITH THE REDUCED TEST REQUIEMENTS WILL SATISFY THE CRITERIA OF REGULATORY GUIDE 1.68 28 AUGUST 1985
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TEST NUMBER 32 - REACTOR WATER CLEANUP SYSTEM TEST SIMPLIFICATION - REDUCED NUMBER OF TESTS REQUIREMENT:
DEMONSTRATE THE OPERABILITY OF THE REACTOR COOLANT SYSTEM PURIFICATION AND CLEANUP SYSTEMS DURING LOW POWER TESTING OBJECTIVE:
OPERATION OF THE RWCU SYSTEM WILL BE DEMONSTRATED BY RECORDING PROCESS VARIABLES WITH THE REACTOR AT RATED TEMPERATURE AND PRESSURE DURING STEADY STATE OPERATION OF THE RWCU IN THREE MODES:
HOT STANDBY, NORMAL AND BLOWDOWN SIMPLIFICATION:
DELETE THE RWCU NON-REGENERATIVE HEAT EXCHANGER (NRHX) MAXIMUM COOLING WATER FLOW REQUIREMENT AND THE BOTTOM HEAD FLOW RATE CALIBRATION THE RWCU MAXIMUM COOLING WATER FLOW REQUIREMENT DOES NOT NEED TO BE PERFORMED TO PROVE THE NRHX CAPABILITIES ARE WITHIN THE DESIGN LIMITS THE BOTTOM HEAD FLOW RATE: CALIBRATION CAN BE ACCOMPLISHED AT ANY POINT IN THE PREOPERATIONAL TEST PROGRAM 28 AUGUST 1985
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