ML19276H026
| ML19276H026 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 08/28/1979 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML19276H025 | List: |
| References | |
| PROC-790828, NUDOCS 7908310464 | |
| Download: ML19276H026 (56) | |
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' PROGRESS REPORT 00 Co.
ON THE i
0 PROGRAM T'O REVIEW
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PRELIMINARY DEVELOPMENT PHASE
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a PRELIMINARY DEVELOPMENT PHASE PROGRESS REPORT O
PROPOSED PROGRAM SCOPE AND PHILOSOPHY.
O PROPOSED CRITERIA, DEFINITIONS AND ASSIGNMENTS FOR CLASSIFYING EQUIPMENT IMPORTANT TO SAFETY.
O PROPOSED GENERAL RULES AND REQUIREMENTS FOR INSPECTING AND TESTING EQUIPMENT ASSIGNED TO THE VARIOUS CLASSIFICATIONS.
O PROPOSED SURVEILLANCE REQUIREMENTS FOR SELECTED PLANT SYSTEMS -
THE RESULTS OF APPLYING THE GENERAL RULES AND REQUIREMENTS DURING THE REVIEW PROCESS FOR THESE SYSTEMS.
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w PROPOSED FORT ST. VRAIN INSERVICE INSEECTION AND TESTING PROGRAM PURPOSE -
THE OVERALL PURPOSE OF THE INSERVICE INSPECTION AND TESTING PROGRAM AT FORT ST. VRAIN IS TO PROVIDE A CONTINUING ASSURANCE THAT COMPONENTS, SYSTEMS, AND STRUCTURES IMPORTANT TO SAFETY, ARE SAFE AND ARE AVAILABLE TO PERFORM THEIR SAFETY FUNCTIONS WHEN REQUIRED.
THE PROGRAM WILL ESTABLISH SPECIFIC SURVEILLANCE RULES AND REQUIREMENTS IN ORDER TO:
O GENERATE OBJECTIVE EVIDENCE ON A CONTINUING BASIS THAT AN ADEQUATE LEVEL OF. NUCLEAR POWER PLANT SAFETY IS BEING MAINTAINED.
O PROVIDE EARLY DETECTION OF DETERIORATION / DEGRADATION OF e
SAFETY-RELATED FACTORS FROM BASELINE CONDITIONS.
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PROVIDE ADDITIONAL ASSURANCE THAT THE PLANT IS BEING MAINTAINED U([
IN A SAFE CONDITION THROUGHOUT ITS LIFETIME.
PHILOSOPHY -
THE DEVELOPMENT OF RULES AND REQUIREMENTS FOR SURVEILLANCE OF EQUIPMENT IMPORTANT TO SAFETY AT FORT ST. VRAIN WILL BE BASED ON A PHILOSOPHY WHICH CONSIDER,S THE CONCERNS FOR OPERATIONAL READINESS OF SAFETY SYSTEMS AS WELL AS THE CON-CERNS FOR INTEGRITY OF THE REACTOR COOLANT PRESSURE BOUNDARY. THIS PHILOSOPHY RECOGNIZES THE IMPORTANCE OF VERIFYING PRESSURE BOUNDARY INTEGRITY TO PREVENT THE OCCURANCE OF A FISSION PRODUCT RELEASE ACCIDENTJ BUT IN ADDITION, IT ALSO RECOGNIZES THE IMPORTANCE OF BEING ABLE TQ MITIGATE THE CONSEQUENCES 0F AN EVENT WHICH COULD ADVERSLY AFFECT PUBLIC HEALTH AND SAFETY.
FURTHERMORE, THE PHILOSOPHY RECOGNIZES THE GENERIC DIFFERENCES BETWEEN LIGHT WATER COOLED REACTORS AND THE FORT ST. VRAIN HIGH TEMPERATURE GAS COOLED REACTOR, PARTI-CULARLY THOSE DIFFERENCES WHICH PROVIDE AN INHERENTLY SUPERIOR LEVEL OF SAFETY.
THE BASIC APPROACH TO BE USED IN DEVELOPING THE RULES FOR FORT ST. VRAIN IS TO ESTABLISH A PROGRAM THAT WILL CHECK THE CONDITION OF PLANT STRUCTURES, SYSTEMS, AND COMPONENTS ON A REGULAR BASIS TO A STANDARD OF ASSURANCE COMMENSURATE WITH THE IMPORTANCE OF THE SAFETY FUNCTION OF THE ITEM.
CLASSIFICATIONS WILL BE j
ESTABLISHED TO PROVIDE THESE LEVELS OF IMPORTANCE AND APPROPRIATE SURVEILLANCE REQUIREMENTS (I.E. TESTS, EXAMINATIONS, OBSERVATIONS, MONITORI!4G, ETC.)
tu SPECIFIED FOR EACH CLASSIFICATION.
THE SURVEILLANCE REQUIREMENTS WILL BE
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BASED ON, DEVELOPED FROM, AND ENHANCE THE EXISTING SURVEILLANCE REQUIREMENTS LJ' CONTAINED IN THE FORT ST. VRAIN TECHNICAL SPECIFICATIONS.
-I SCOPE -
THE INSERVICE INSPECTION AND TESTING PROGRAM PROVIDES RULES AND REQUIREMENTS FOR SURVEILLANCE OF PLANT STRUCTURES, SYSTEMS, AND COMPONENTS AT THE FORT ST.
VRAIN NUCLEAR GENERATING STATION.
THE PROGRAM APPLIES TO THOSE PLANT, EQUIPMENT ITEMS WHICH, IF FAILED, COULD INTERFERE WITH REACTOR SHUTDOWN, INTERFERE WITH REMOVAL OF DECAY HEAT OR RELEASE EXCESSIVE RADIOACTIVITY TO THE ENVIRON-MENT.
SUCH ITEMS ARE GENERALLY CLASS 1FIED AS " SAFETY-RELATED" AND INCLUDE EQUIPMENT DESIGNATED "FSAR SAFETY CLASS I",
" SAFE SHUTDOWN", " ENGINEERED SAFEGUARDS", " STANDBY POWER", " EMERGENCY COOLING", AND "BTCKUP EMERGENCY COOLING".
THE PROGRAM ALSO APPLIES TO OTHER PLANT EQUIPMENT ITEMS WHICH, IF UNAVAILABLE MAY REDUCE OR DEGRADF THE MARGIN OF SAFETY THEY PROVIDE.
THE PROGRAM FURTHER CLASSIFIES SAFETY-RELATED AND OTHER EQUIPMENT ACCORDING TO THEIR IMPORTANCE TO PLANT SAFETY AND PROVIDES THAT EACH EQUIPMENT ITEM BE PERIODI-CALLY TESTED, EXAMINED, OBSERVED, CALIBRATED, OR MONITORED AS APPROPRIATE.
THE PROGRAM PROVIDES CRITERIA FOR ACCEPTANCE OF RESULTS, REPAIR AND REPLACEMENT, AND PERSONNEL QUALIFICATIONS) IT ALSO DEFINES RESPONSIBILITIES, EXAMINATION TECHNIQUES AND RECORD KEEPING / REPORTING REQUIREMENTS.
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- 1 GENERAL SURVEILLANCE REQUIREMENTS (CONTINUED)
O SYSTEM LEAKAGE AND PRESSURE TESTS
- PRESSURE TESTS WILL BE SPECIFIED IN ACCORDANCE WITH APPLICABLE CODE REQUIREMENTS AFTER WELDING TO DEMONS 1 RATE THE STRENGTH AND TIGHTNESS OF NEW WELDS, REPAIR WELDS, OR REPLACEMENT WELDS.
-~ LEAKAGE TESTS WILL BE SPECIFIED TO PERIODICALLY DEMONSTRATE THE TIGHTNESS OF PRESSURE. RETAINING SYSTEMS.AND COMPONENTS.
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- GENERAL REQUIREMENTS FOR PRESSURE TESTS AND LEAKAGE TESTS WILL BE DEVELOPED FOR INCLUSION IN THE PROGRAM.
O RECORDS AND REPORTS
- RECORDS AND REPORTS SHALL CONTINUE TO BE PREPARED AND RETAINED IN ACCORDANCE WITH EXISTING APPLICABLE REQUIREMENTS.
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PROPOSED SURVEILLANCE CLASSIFICATIONS CLASSIFICATION CRITERIA SURVEILLANCE CLASSIFICATIONS SHALL BE DEFINED FOR ALL SAFETY-RELATED,AND OTHER PLANT STRUCTURES, SYSTEMS, AND EQUIPMENT TO REFLECT AN ORDERLY GRADATION OF SAFETY'IMPORTANCE TO THIS EQUIPMENT.
THE CLASSIFICATIONS WILL BE DEFINED IN ACCORDANCE WITH THE FOLLOWING CRITERIA:
A.
EQUIPMENT ITEMS CONSIDERED OF HIGHEST SAFETY PRIORITY ARE TO BE DESIGNATED SURVEILLANCE CLASS I AND ARE THOSE PRO-VIDING ULTIMATE PROTECTION FOR'THOSE EXTREME SITUATIONS INVOLVING FAILURE OF MAJOR SAFETY-RELATED EQUIPMENT WHICH, ALTHOUGH HAVING A LOW PROBABILITY OF OCCbRRENCE, HAVE THE POTENTIAL FOR CAUSING ABNORMAL OFF-SITE DOSES DUE TO FISSION PRODUCT RELEASE, AGGRAVATED BY THE POTENTIAL FOR CORE DAMAGE.
B.
EQUIPMENT ITEMS CONSIDERED OF NEXT HIGHEST PRIORITY ARE TO DESIGNATED SURVEILLANCE CLASS II AND ARE THOSE PROVIDING jy{
ULTIMATE PROTECTION FOR THOSE EXTREME SITUATIONS INVOLVING FAILURE
[G OF MAJOR SAFETY-RELATED OR OTHER PLANT EQUIPt1ENT WHICH, AL-THOUGH HAVING A LOW PROBABILITY OF OCCURENCE, VE THE POTENTIAL
{;f FOR CAUSING ABNORMAL Of?-SITE DOSES DUE TO FISSION PRODUCT RELEASE.
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CLASSIFICATION CRITERI A (CONTINUED)
C.
EQUIPMENT ITEMS CONSIDERED OF NEXT HIGHEST PRIORITY ARE TO BE DESIGNATED SURVEILLANCE CLASS III AND INCLUDE ALL OTHER SAFETY-RELATED ITEMS NOT INCLUDED IN SURVEILLANCE CLASSES I*
AND II, BUT WHICH PROVIDE PROTECTION FOR NORMAL AND ABNORMAL PLANT OPERATING MODES.
D.
EQUIPMENT ITEMS CONSIDERED OF NEXT HIGHEST PRIORITY ARE TO bE '
DESIGNATED SURVEILLANCE CLASS IV AND ARE THOSE OTHER PLANT SYSTEMS AND COMPONENTS WHICH MAY PROVIDE ADDITIONAL PROTECTION, -
EITHER DIRECTLY OR INDIRECTLY; AND THEREBY ASSIST IN PREVENTING OR MITIGATING THE CONSEQUENCES'0F ABNORMAL SITUATIONS OR ASSIST IN PROTECTING THE HEALTH AND SAFETY OF THE PUBLIC.
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PROPOSEDSURVEILIkNCECLASSIFICATIONS SURVEILLANCE CLASS DEFINITIONS -
USING THE CLASSIFICATION CRITERIA AND THE ACCIDENT SCENARIOS EVALUATED IN, THE FSAR, THE FOLLOWING DEFINITIONS HAVE BEEN DEVELOPED WHICH WILL ALLOW ALL EQUIPMENT IMPORTANT TO SAFETY TO BE FURTHER CLASSIFIED, FOR PURPOSES OF SURVEILLANCE, ACCORDING TO THE IMPORTANCE OF THEIR SAFETY FUNCTIONS..
SURVEILLANCE CLASS I SURVEILLANCE CLASS I APPLIES TO THOSE ITEMS OF SAFETY-RELATED PLANT EQUIPMENT REQUIRED TO COPE WITH THE CONSEQUENCES OF DESIGN BASIS ACCIDENT NO. 1, PERMANENT LOSS OF, FORCED CI,RCULATION.
THIS ACCIDENT IS DEFINED AS A WORST CASE FAILURE OF THE REACTOR FORCED CIRCULATION EMERGENCY COOLING SYSTEM.
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EUEVEILLANCE CLASS DEFINITIONS (CONTINUED)
SURVEILLANCE CLASS II SURVEILLANCE CLASS II APPLIES TO THOSE ITEMS OF SAFETY-RELATED PLANT EQUIPMENT REQUIRED TO COPE WITH THE CONSEQUENCES OF:
0 DESIGN BASIS ACCIDENT ~NO. 2, RAPID DEPRESSURIZATION/ BLOWDOWN.
THIS ACCIDENT IS DEFINED AS THE WORST' CASE FAILURE OF THE REACTOR CONTAINMENT SYSTEM OR, O
THE MAXIMUM CREDIBLE F:EACTIVITY ACCIDEtJT, ROD PAIR WITHDRAWAL.
THIS ACCIDENT IS DEFINED AS THE WORST CASE FAILURE OF THE REACTOR REACTIVITY CONTROL SYSTEM OR, O
THE MAXIMUM CREDIBLE STEAM LEAK, RUPTURE OF A STEAM GENERATOR TUBE OR SUB-HEADER.
THIS ACCIDENT IS DEFINED Ar, THE WORST CASE FAILURE OF THE REACTOR SECONDARY COOLANT 6V3 TEM OR,
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O THE MAXIMUM CREDIBLE ENVIRONMENT DISTURBANCE, SAFE SHUTDOWN LJ, EARTHOUAKE OR MAXIMUM TORNADO.
THIS EVENT IS CONSIDERED TO na BE THE WORST CASE FAILURE OF NON-SAFETY RELATED STEAM OR
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ELECTRIC PLANT EQUIPMENT.
i SURVEILLANCE CLASS DEFINITIONS (CONTINUED)
SURVEILLANCE CLASS III SURVEILLANCE CLASS III APPLIES TO THOSE ITEMS OF SAFETY-RELATED PLANT EQUIPMENT WHICH PROVIDE STRUCT!!RAL SUPPORT, CONTAIN THE REACTOR AND REACTOR COOLANT SYSTEM, AND TO THOSE REACTOR AUXILIARY SYSTEMS WHICH HANDLE AND STORE RADI0 ACTIVE SPENT FUEL ELEMENTS.
SURVEILLANCE CLASS IV SURVEILLANCE CLASS IV APPLIES TO THOSE OTHER ITEMS OF PLANT EQUIPMENT WHICH PROVIDE ADDITIONAL PROTECTION, SUCH AS THOSE THAT CONTAIN RADIO-ACTIVE WASTES, PROVIDE FIRE-PROTECTION FOR SAFETY-RELATED EQUIPMENT, OR c3$
PROVIDE ADDITIONAL INDICATION AND CONTROL, ETC.
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PROPOSED SURVEILLANCE CLASSIFICATIONS APPLICATION CRITERIA O
SURVEILLANCE CLASSES I AND II APPLY TO THOSE SYSTEMS AND COMPONENTS WHICH ARE PROVIDED WITH ACTIVE SAFETY FUNCTIONS TO PROTECT THE IN-TEGRITY OF THE CORE AND/OR THE CONTAINMENT UNDER ACCIDENT CONDITIONS, THUS INSURING THAT THE PLANT SAFETY OBJECTIVE IS ACHIEVED DURING EXTREME SITUATIONS.
O SURVEILLANCE CLASS III APPLIES TO THOSE STRUCTURES, SYSTEMS, AND COMPONENTS WHICH ARE PROVIDED WITH ACTIVE OR PASSIVE SAFETY FUNCTIONS TO PROTECT AGAINST THE UNCONTROLLED RELEASE OF RADI0 ACTIVE FISSION PRODUCTS UNDER NORMAL OR ABNORMAL CONDITIONS, THUS INSURING THAT THE PLANT SAFETY OBJECTIVE IS ACHIEVED DURING ALL OTHER TYPES OF SITUATIONS.
O SURVEILLANCE CLASS IV APPLIES TO THOSE OTHER SYSTEMS AND COMPONENTS T3 WHICH CAN PERFORM ACTIVE OR PASSIVE SAFETY FUNCTIONS, SUCH AS THO3E hII WHICH CONTROL OPERATIONAL RELEASES OF RADI0 ACTIVITY, PROTECT SAFETY-RELATED EQUIPMENT FROM THE EFFECTS OF FIRE, AND CONTROL.0R MONITOR THE n
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OPERATION OF SYSTEMS AND EQUIPMENT.
APPLICATION CRITERIA (CONTINUED)
O STRUCTURES, SYSTEMS, OR COMPONENTS ARE ASSIGNED ONLY TO THE HIGHEST OF ANY CLASSIFICATIONS TO WHICH THEY APPLY.
O AUXILIARY SUPPORT SYSTEMS REQUIRED TO FUNCTION ALONG WITH THE MAJOR EQUIPMENT / SYSTEMS CLASSIFIED ABOVE SHALL BE INCLUDED IN THE SAME SURVEILLANCE CLASS AS THE MAJOR EQUIPMENT / SYSTEM.
TYPICAL AUXILIARY SUPPORT SYSTEMS INCLUDE:
ESSENTIAL ELECTRIC POWER, HELIUM CIRCULATOR AUXILIARY SYSTEM, INSTRUMENT AIR SUPPLY SYSTEM, AND HYDRAULIC ACTUATOR SUPPLY SYSTEM.
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PROPOSED SURVEILLANCE CLASSIFICATIONS MAJOR EQUIPMENT / SYSTEM CLASSIFICATIONS SURVEILLANCE CLASS EQUIPMENT / SYSTEM
-SAFETY FUNCTION I
RESERVE SHUTDOWN SYSTEM CORE REACTIVITY CONTROL BACK-UP EMERGENCY COOLING CONTAINMENT TEMPERATURE EQUIPMENT CONTROL REACTOR BUILDING ACTIVITY AND RADIATION. CONTROL HELIUM PURIFICATION CONTAINMENT PRESSURE /
SYSTEM TEMPERATURE CONTROL II CONTROL ROD DRIVES CORE REACTIVITY CONTROL REACTOR SCRAM LOGIC CORE REACTIVITY CONTROL SAFE SHUTDOWN EMERGENCY CORE TEMPERATURE CONTROL COOLING EQUIPMENT STEAM WATER DUMP SYSTEM CONTAINMENT PRESSURE CONTROL PCRV SAFETY VALVES CONTAINMENT PRESSURE CONTROL d
LOOP TRIP / CIRCULATOR TRIP CORE TEMPERATURE / CONTAINMENT U
LOGIC PRESSURE CONTROL w
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MAJOR EQUIPMENT / SYSTEM CLASSIFICATI0fl1 (CONTINUED)
SURVEILLANCE CLASS EQUIPMENT / SYSTEM SAFETY FUNCTION III PCRV STRUCTURE ACTIVITY AND RADIKTION CONTROL PCRV LINER ACTIVITY AND RADIATION CONTROL PCRV PENETRATIONS AND ACTIVITY AND RADIATION CONTROL' CLOSURES CORE SUPPORT STRUCTURE REACTIVITY CONTROL CORE TEMPERATURE CONTROL STEAM GENERATORS ACTIVITY CONTROL CORE TEMPERATURE CONTROL FUEL HANDLING MACHINE ACTIVITY AND RADIATION CONTROL FUEL TEMPERATURE CONTROL FUEL STORAGE FACILITY ACTIVITY AND RADIATION CONTROL FUEL TEMPERATURE CONTROL IV EQUIPMENT CONTROL PLANT CONTROL SYSTEMS EQUIPMENT INSTRUMENTATION PLANT CONTROL g
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SURVEll1ANCE CLASS II REACTIVITY CONTROL EQUIPMENT
- CONTROL ROD DRIVES (12)
- PLANT PROTECTIVE SYSTEM - SCRAM LOGIC (93)*
(INCLUDING INTERFACE WITH ROD CONTROL SYSTEM)
CORE COOLING EQUIPMENT
- HELIUM CIRCULATORS AND AUXIL ARY SYSTEM (21-)*
- SECONDARY COOLANT SYSTEM (22)*
(INCLUDING INTERFACE WITH REACTOR BUILDING VENT AND DRAIN SYSTEM)
- FEEDWATER SYSTEM (31)"
PCRV PROTECTION EQUIPMENT
- STEAM-WATER DUMP SYSTEM (22)*
- PCRV SAFETY VALVES (11)*
- PLANT PROTECTIVE SYSTEM - LOOP / CIRCULATOR TRIP LOGIC (93)*
- PLANT INSTRUMENTATION SYSTEM - NUCLEAR /IN-REACTOR / PIPE RUPTURE INSTRUMENTS (93)*
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- INSTRUMENT AIR SYSTEM (82)*
SR-6-1 DRAWINGS.
- HYDRAULIC POWER SYSTEM (91)*
- HYDRAULIC SNUBBERS (98)
SURVEILLANCE CLASS III
/CTIVITY/RADIAT10p CONTROL EQUIPMENT
- PCRV STRUCTURE (11)
- PCRV LINER (ll)
- PCRV PENETRATIONS AND CLOSURES (11)
- PCRV THERMAL BARRIER (ll)
- PCRV INTERNAL STRUCTURE (CORE SUPPORT) (11)
- PCRV AUXILIARY SYSTEM (11)*
- FUEL HANDLING MACHINE (13).
- FUEL STORAGE FACILITY (14)
- STEAM GENERATOR (22)
SPENT FUEL COOLING EQUIPMENT
- FUEL STORAGE FACILITY AUXILIARY SYSTEM (14)*
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RADIOACTIVE WASTE MANAGEMENT EQUIPMENT
- RADI0 ACTIVE LIQUID WASTE STORAGE SYSTEM (62)
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EIRE PROTECTION EQUIPMENT
- FIRE WATER SYSTEM - DELUGES /SPPAYS/ HOSE REELS (45)
- CONTROL COMPLEX FIRE DETECTION AND ALARM SYSTEM (XX)
- CONTROL COMPLEX HALON SYSTEM (45)
- CONTROL COMPLEX EMERGENCY BREATHABLE AIR SYSTEM (45)
'- CONTROL COMPLEX FIXED WATER SPRAY SYSTEM (45)
- CONTROL COMPLEX CABLE COATING AND SEAL SYSTEM (XX)
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OPERATIONAL READINESS (CONTINUED) 2.
COMPONENT TESTING 0
PUMPS
- SURVEILLANCE CLASS I - THE OPERATIONAL READINESS OF PUMPS ASSIGNED TO SURVEILLANCE CLASS I SHALL BE DEMONSTRATED ONCE EACH QUARTER BY SURVEILLANCE TESTING.
THE RULES AND RE-QUIREMENTS FOR SURVEILLANCE TESTING OF THESE PUMPS WILL BE BASED ON ARTICLE IGP OF THE DRAFT ASME CODE.(SECTION XI, DIVISION 2).
- SURVEliLANCE CLASS II - THE OPERATICNAL READINESS OF PUMPS ASSIGNED TO SURVEILLANCE CLASS II SHALL BE DEMONSTRATED BY NORMAL SYSTEM OPERATION OR BY SURVEILLANCE TESTING TO EXERCISE T. HOSE PUMPS NOT NORMALLY IN OPERATION ONCE EACH QUARTER.
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- SURVEllLANCE CLASS III AND IV - THERE ARE NO PUMPS ASSIGNED TO SURVEILLANCE CLASSES I!! AND IV.
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III - THERE ARE NO COMPRESSORS ASSIGN 00 TO SURVEILLANCE CLASSES I AND III.
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PRESSORS ASSIGNED TO SURVEILLANCE CLASSES II AND IV SHALL BE DEMONSTRATED BY NORMAL OPERATION OR BY SURVEILLANCE TESTING TO EXERCISE THOSE COMPRESSORS NOT NORMALLY IN OPERATION ONCE EACH QUARTER.
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COMPONENT TESTING (CONTINUED)
O VALVES
- SURVEILLANCE CLASS I - THE OPERATIONAL READINESS OF VALVES
- ASSIGNED TO SURVEILLANCE CLASS I SHALL BE DEMONSTRATED BY SURVEILLANCE TESTING.
THE RULES AND REQUIREMENTS FOR SURVEILLANCE TESTING OF THESE VALVES WILL BE BASED ON ARTICLE IGV 0F THE DRAFT ASME CODE (SECTION XI, DIVISION 2). -
- SURVEILLANCE CLASS II, III, AND IV - THE OPERATIONAL READI-NESS OF VALVES ASSIGNED TO SURVEILLANCE CLASSES II, III, AND IV SHALL BE DEMONSTRATED BY NORMAL OPERATION OR BY SURVEILLANCE TESTING TO EXERCISE THOSE VALVES WHICH DO NOT NORMALLY OPERATE.
ISOLATION VALVES SHALL BE TESTED AT LEAST ONCE EACH YEAR AND SAFETY / RELIEF VALVES SHALL BE TESTED AT LEAST ONCE EVERY FIVE YEARS.
3.
INSTRUMENTATION AND CONTROL TESTING
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0 THE OPERATIONAL READINESS OF INSTRUMENTATION AND CONTROL CIRCUITS
[L SHALL BE DEMONSTRATED BY SURVEILLANCE TESTING.
GENERALLY, INSTRU-
'T' MENT ACCURACY SHALL BE DEMONSTRATED ONCE EACH YEAR BY A CALIBRATION ij TEST.
APPLICABLE INDICATION, ALARM, CONTROL, AND PROTECTIVE CIRCUIT
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PERFORMANCE SHALL BE DEMONSTRATED BY A FUNCTIONAL TEST AT LEAST ONCE EACH YEAR DEPENDING ON THE IMPORTANCE OF THE SAFETY FUNCTION.
B.
STRUCTURAL INTEGRITY 1.
PRESSURE BOUNDARY LEAKAGE TESTING 0
SYSTEM LEAKAGE TESTING - STRUCTURAL INTEGRITY OF ALL ACCESSIBLE SAFETY RELATED PIPING SYSTEM PRESSURE BOUNDARIES SHALL BE VERIFIED f
BY EXAMINATION FOR LEAKAGE ONCE EACH YEAR WHEN THE SYSTEM IS AT OR NEAR NORMAL WORKING PRESSURE.
O PCRV PENETRATION LEAKAGE TESTING - STRUCTURAL INTEGRITY OF PCRV PENETRATION PRESSURE BOUNDARIES SHALL BE VERIFIED BY LEAKAGE MONITORING.
PENETRATION CLOSURE SEAL LEAKAGE SHALL BE MONITORED CONTINUOUSLY FOR ALL PENETRATION GROUPS AND MEASURED ONCE EACH MONTH FOR EACH PEN':TRATION GROUP.
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OPERAT10tfAL READ _U1ESS (CONTINUED) 2.
COMPONENT TESTING A'
RESERVE SHUTDOWN HOPPERS - CONTINUE EXISTING SR 5.1.2C WHICH REQUIRES ONE RESERVE SHUTDOWN HOPPER TO BE TESTED IN THE HOT SERVICE FACILITY AT EACH OF THE FIRST FIVE REFUELING SHUTDOWNS AND THEN AT EVERY OTHER REFUELING SHUTDOWN TO DEMONSTRATE THAT THE RUPTURE DISC BURSTS AT THE CORRECT SET PRESSURE AND THAT THE POISON MATERIAL RELEASES PROPERLY f
I FROM THE HOPPER AND HAS NOT DETERIORATED.
B)
HOPPER PRESSURIZING VALVES - ADD A NEW SR WHICH REQUIRES EACH OF THE AIR-0PERATED HOPPER PRESSURIZING VALVES TO BE EXERCISED AT EACH RE-FUELING SHUTDOWN TO DEMONSTRATE THAT THE VALVE OPERATOR STROKES PROPERLY.
C)
P_ENEIBATION CHECK VALVES - ADD A NeW SR WHICH REQUIRES EACH OF THE HOPPER PRESSURIZING LINE CHECK VALVES TO BE TESTED EACH TIME THE PENETRATION IT IS CONNECTED TO IS OPENED FOR REFUELING TO DEMONSTRATE THE ABILITY OF THE CHECK VALVE TO FUNCTION PROPERLY IN THE REVERSE j
DIRECTION.
D)
ACM OUICK-DISCONNECT VALVES - ADD A NEW SR WHICH, REQUIRES EACH OF THE ACM QUICK-DISCONNECT VALVES TO BE CONNECTED AND DISCONNECTED ONCE EACH QUARTER TO DEMONSTRATE THAT THIS VALVE IS CAPABLE OF FUNCTIONING PROPERLY.
A.
OPERATIONAL REAlllRE1S. (CONTINUED) 3.
INSTRUMEDIATION AND CONTROL TESTitlG A)
REEERVE SHUTDOMI1 HOPPER - CONTINUE SR 5.1.2A WHICH REQUIRES THE RESERVE SHUTDOWN HOPPER PRESSURE ALARM CIRCUIT TO BE TESTED ONCE EACH QUARTER IN CONJUNCTION WITH THE SYSTEM TEST TO DEMONSTRATE THAT THE PRESSURE SWITCH AND ALARM FUNCTION PROPERLY.
CONTINUE SR 5.1.2E WHICH REQUIRES THE RESERVE SHUTDOWN HOPPER PRESSURE SWITCH TO BE CALIBRATED WHENEVER THE CONTROL AND ORIFICE ASSEMBLY IS REMOVED FROM THE REACTOR FOR MAIN-l TENANCE TO DEMONSTRATE THAT THE PRESSURE SWITCH OPERATES AT THE CORRECT SET PRESSURE.
B)
NORMAL PRESSURIZING LINE - CONTINUE SR 5.1.2D WHICH REQUIRES THE l
PRESSURIZING LINE PRESSURE ALARM CIRCUIT TO BE TESTED ONCE EACH QUARTER IN CONJUNCTION WITH THE SYSTEM TEST AND CALIBRATED ONCE EACH YEAR TO DEMONSTRATE THAT THE PRESSURE SWITCH AND ALARM CIRCUIT FUNCTIONS PROPERLY.
C)
TEST PRESSURIZING LINE - CONTINUE SR 5.1.2B WHICH REQUIRES THE TEST GAS PRESSURIZING LINE PRESSURE INDICATION AND ALARM CIRCUIT TO BE CALIBRATED ONCE EACH YEAR TO DEMONSTRATE THAT THE PRESSURE INDICATOR, THE PRESSURE INDICATING SWiiCH, AND THE ALARM CIRCUIT FUNCTION PROPERLY.
IN D)
PRESSURIZING VALVES - MODIFY EXISTING SR 5.1.2A TO REQUIRE THE PRES-SURIZING VALVE CONTROL CIRCUIT BE TESTED ONCE EACH QUARTER TO DEMON-n
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STRATE CONTINUITY BETWEEN THE CONTROL ROOM AND THE LOCAL CONTROL PANEL.
(NOTE:
THIS TEST IS PRESENTLY PERFORMED).
ADD A NEW SR WHICH REQUIRES THE PRESSURIZING. VALVE CONTROL CIRCUIT TO BE TESTED AT EACH REFUELING SHUTDOWN TO DEMONSTRATE THAT THE CONTROL ROOM SWITCHES AND CONTROL RELAYS FUNCTION PROPERLY TO OPERATE THE HOPPER PRESSURIZING VALVES.
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PROPOSED SURVEILLANCE REQUIREMENTS REACTOR BUILDING VENTILATION EXHAUST SYSTEM A.
OPERATIONAL READINESS 1.
SYSTEM TESTING A)
LC0 4.5.1 REQUIRES THE REACTOR BUILDING TO BE MAINTAINED SLIGHTLY BELOW ATMOSPHERIC PRESSURE WHENEVER THE REACTOR IS BEING OPERATED OR REFUELED.
REACTOR BUILDING PRESSURE IS MONITORED CONTINUOUSLY AND ALARMED IF ABNORMAL TO ENSURE THAT THE REACTOR BUILDING IS CAPABLE OF PERFORMING ITS CONFINEMENT FUNCTION.
NO NEW SR IS RE0uIRED TO DEMONSTRATE THE CAPABILITY OF THE VENTILATION EXHAUST SYSTEM TO MAINTAIN THE REACTOR BUILDING AT A NEGATIVE PRESSURE.
B)
CONTINUE EXISTING SR 5.2.21 WHICH REQUIRES THE EXHAUST FAN ACM POWER BUS TO BE ENERGIZED ONCE EVERY SIX MONTHS TO DEMONSTRATE THAT THE ACM FEED BREAKERS AND TRANSFER SWITCHES ARE OPERABLE AND TilAT THE 25 EXHAUST FANS ARE CAPABLE OF OPERATION FROM THIS EMERGENCY POWER SOURCE.
Da oc C)
ADD A NEW SR WHICH REQUIRES THE NITROGEN STORAGE BOTTLE PRESSURE TO BE MONITORED ONCE EACH WEEK TO ENSURE THAT THE REQUIRED ACTUATING PRESSURE IS MAINTAINED FOR THE EXHAUST FAN DAMPERS DURING ACM SYSTEM OPERATION.
i A.
OPERATIONAL READIrlELS. (CONTINUED) 2.
COMPONENT TESTING A)
HEPA FILTERS - CONTINUE EXISTING SR 5.5.3E WHICH REQUIRES THE HEPA FILTER PRESSURE DROP TO BE MONITORED ONCE EACH WEEK TO ENSURE THEY ARE CAPABLE OF PASSING DESIGN AIR FLOW AND ARE NOT EXCESSIVELY' PLUGGED.
CONTINUE EXISTING SR 5.5.3C WHICH REQUIRES THE HEPA FILTER EFFICIENCY BE D0P TESTED ONCE EACH YEAR OR WHENEVER A FILTER IS REPLACED OR ITS HOUSING REPAIRED TO DEMONSTRATE THAT THE CAPACITY FOR REMOVAL OF PARTICULATES IS ACCEPTABLE.
CONTINUE EXISTING SR 5.5.3D WHICH REQUIRES THE 11 EPA FILTER BE TESTED WHENEVER THE FILTER HOUSING IS MODIFIED TO DEMONSTRATE THAT THE AIR FLOW IS PROPERLY DISTRIBUTED ACROSS THE FILTER.
B)
CHARC0AL FILTERS - CONTINUE EXISTING SR 5.5.3E WHICH REQUIRES THE CHARC0AL FILTER PRESSURE DROP TO BE MONITORED ONCE EACH WEEK TO ENSURE THEY ARE CAPABLE OF PASSING DESIGN AIR FLOW AND ARE NOT EXCESSIVELY PLUGGED.
CONTINUE EXISTING SR 5.5.3A WHICH REQUIRES A CHARC0AL SAMPLE TO BE LAB TESTED ONCE EVERY 4400 HOURS (ABOUT SIX MONTHS) TO DEMONSTRATE THAT THE CAFaCITY FOR REMOVAL OF RADI0 ACTIVE
{y METHYL IODIDE IS ACCEPTABLE.
CONTINUE EXISTING SR 5.5.3B WHICH REQUIRES THE CHARCOAL FILTERS TO BE TESTED ONCE EACH YEAR OR WHENEVER h2f A FILTER BED IS REPLACED OR ITS HOUSING' REPAIRED TO DEMONSTRATE THAT
'O THE CAPACITY FOR REMOVAL OF HYDROGENATED HYDROCARBONS IS ACCEPTABLE.
CONTINUE SR 5.5.3D WHICH REQUIRES THE CHARCOAL FILTER TO BE TESTED WHENEVER THE FILTER HOUSING IS MODIFIED TO DEMONSTRATE THAT THE AIR FLOW IS PROPERLY DISTRIBUTED ACROSS THE FILTER BEDS.
2.
COMPONENT TESTIllE (CONTINUED)
C)
EXHAUST FAtlS - CONTINUE EXISTING SR 5.5.3E WHICH REQUIRES THE REACTOR BUILDING EXHAUST FANS TO BE OPERATED AT DESIGN FLOW ONCE EACH WEEK l
FOR THE FILTER PRESSURE DROP CHECKS TO DEMONSTRATE THAT THE FANS ARE FUNCTIONING PROPERLY.
D)
EXHAUST FAN DAMPERS - ADD A NEW SR WHICH REQUIRES THE EXHAUST FAN DAMPERS TO BE TESTED ONCE EVERY SIX MONTHS TO DEMONSTRATE THAT THE VALVE OPERATOR STROKES PROPERLY AND FAILS IN THE PROPER POSITION ON LOSS OF POWER.
CONTINUE EXISTING SR 5.2.21 WHICH REQUIRES THE DAMPERS TO BE ACTUATED USING THE ACM NITROGEN BOTTLES ONCE EVERY SIX MONTHS TO DEMONSTRATE THAT THE BACKUP INSTRUMENT AIR HEADER FUNCTIONS PROPERLY.
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INSTRUMENTATION AND CONTROL TESTLRE (CONTINUED)
E)
EXHAUST STACK - CONTINUE EXISTINs SR 5.8.1 WHICH REQUIRES THE EXHAUST STACK RADIATION MONITORING CIRCUIT TO BE TESTED ONCE EACH WEEK, ONCE EACH MONTH, AND CALIBRATED ONCE EACH QUARTER TO DEMONSTRATE.THAT THE MONITORS, ALARMS, AND ISOLATION CONTROLS FUNCTION PROPERLY.
ADD A NEW SR WHICH REC"'RES THE EXHAUST STACK FLOW INDICATION CIRCUIT TO BE CALIBRATED ONCE EACH YEAR TO DEMON'.rRATE THAT THE SENSING ELEMENT AND INDICATORS ACCURATELY MEASURE EXHAUST STACK FLOW.
B.
STRUCTURAL INTEGRITY - SYSTEM TESTING AND COMPONENT TESTING. PROVIDE ADEQUATE INFORMATION TO ASSURE THAT THE SYSTEM DUCTWORK IS INTACT.
NO NEW SR IS REQUIRED TO VEP.IFY THE STRUCTURAL IN-TEGRITY OF THE SYSTEM DUCTING.
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PROPOSED SURVEILLANCE REQUIREMENTS REACTOR BUILDING OVERPRESSURE PROTECTION SYSTEM A.
OPERATIONAL READINESS 1.
SYSTEM TESTING
.A)
CONTINUE EXISTING SR 5.5.2 WHICH REQUIRES THE REACTOR BUILDING PRESSURE RELIEF LOUVERS TO BE EXERCISED ONCE EACH YEAR TO DEMONSTRATE OPERA-BILITY.
MODIFY SR 5.5.2 TO REQUIRE TilAT THE REACTOR BUILDING PRESSURE RELIEF LOUVERS BE EXERCISED USING THE BACKUP INSTRUMENT AIR HEADER (NITROCEN BOTTLES) ONCE EACH YEAR TO DEMONSTRATE OPERABILITY WITH BACKUP POWER.
(NOTE:- THIS TEST IS PRESENTLY BEING PERFORMED).
2.
COMPONENT TESTING A)
PRESSURE RELIEF LOUVERS - MODIFY SR 5.5.2 TO REQUIRE THE PRESSURE RELIEF LOUVERS To BE TESTED ONCE EACH YEAR IN CONJUNCTION WITH THE 23 SYSTEM TESTS TO DEMONSTRATE THAT THE ACTUATOR STROKES FULLY AND
[ff RAPIDLY.
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3.
INSTRUMENIATION AND CONTROL TESTING A)
REACTOR BUILDINE - CONTINUE EXISTING SR 5.5.2 WHICH REQUIRES THE REACTOR BUILDING PRESSURE SENSING LOGIC TO BE TESTED ONCE EACH MONTH AND CALIBRATED ONCE EACH YEAR TO DEMONSTRATE THAT THE PRES-SURE TRANSMITTERS AND CONTROL LOGIC FUNCTION PROPERLY.
B)
SUPPLY FAN - MODIFY SR 5.5.2 TO REQUIRE THE SUPPLY FAN INTERLOCK CIRCUIT TO BE TESTED ONCE EACH YEAR IN CONJUNCTION WITH THE SYSTEM TESTS TO DEMONSTRATE THAT THE SUPPLY FAN IS SHUT DOWN WHEN THE LOUVERS ARE ACTUATED.
(NOTE:
THIS TEST IS PRESENTLY BEING PERFORMED).
C)
INSTRUMENT AIR HEADERS - ADD A NEW SR WHICH REQUIRES THE PRESSURE INDICATION AND ALARM CIRCUITS FOR THE NORMAL AND BACKUP INSTRUMENT AIR HEADERS TO BE TESTED AND CALIBRATED ONCE EACH YEAR TO DEMONSTRATE THAT THE PRESSURE.INDICATORSs PRESSURE SWITCHES, AND ALARMS FUNCTION PROPERLY.
aa
[I D)
LOUVER GROUP HEADERS - ADD A NEW SR WHICH REQUIRES THE PRESSURE n
ALARM CIRCUITS IN EACli 0F THE TWENTY LOUVER GROUP HEADERS TO BE m
)[
CALIBRATED ONCE EACH YEAR TO DEMONSTRATE THAT THE~ PRESSURE SWITCHES AND ALARMS FUNCTION AT THE CORRECT SET PRESSURE.
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PROPOSED SURVEILLANCE REQUIREMENTS PURIFICATION COOLING WATER SYSTEM A.
OPERATIONAL READINESS SYSTEM TESTIt{E - CONTINUE EXISTING SR 5.2.21 WHICH REQUIRES THE PURIFICA-1.
TION PUMP ACM POWER BUS TO BE ENERGIZED ONCE EVERY SIX MONTHS TO DEMONSTRATE THAT THE ACM FEED BREAKERS AND, TRANSFER SWITCHES ARE OPERABLE AND THAT THE PURIFICATION PUMPS ARE CAPABLE OF OPERATION FROM THIS EMERGENCY POWER SOURCE.
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A.
OPERATIONAL READINESS (CONTINUED) 2.
COMPONENT TESTIt{H A)
PURIFICATION PUMPS - ADD A NEW SR WHICH REQUIRES THE PURIFICATION PUMPS TO BE TESTED ONCE EACH QUARTER TO DEMONSTRATE THAT APPLICABLE PUMP PERFORMANCE PARAMETERS ARE ACCEPTABLE.
B)
CDDLING LOOP ISOLATION VALVES - CONTINUE EXISTING SR 5.2.21 WHICH REQUIRES THE COOLING LOOP ISOLATION' VALVES TO BE MANUALLY. EXERCISED ONCE EVERY SIX MONTHS TO DEMONSTRATE THAT THE HAND JACK FUNCTIONS PROPERLY.
ADD A NEW SR WHICH REQUIRES THE COOLING LOOP ISOLATION VALVES TO BE EXERCISED ONCE EVERY SIX MONTHS TO DEMONSTRATE THAT THE AIR OPERATOR STROKES PROPERLY AND FAILS IN THE PROPER POSITION ON LOSS OF POWER.
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C)
C00 LING' LOOP RELIEF VALVES - ADD A NEW SR WHICH REQUIRES THE COOLING LOOP RELIEF VALVES TO BE TESTED ONCE EVERY FIVE YEARS TO DEMONSTRATE
()[
THAT THE VALVES OPEN AT THE CORRECT SET PRESSURE.
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A.
OPERATIONAL READINESS (CONTINUED) 3.
INSTRUMENTATION AND CONTROL TESTING A)
PURIFICATION PUMPS - ADD A NEW SR WHICH REQUIRES THE PURIFIdATION PUMP DIFFERENTIAL PRESSURE INDICATION CIRCUIT TO BE CALIBRATED ONCE EACH YEAR TO DEMONSTRATE THAT THE DIFFERENTIAL PRESSURE INDICATOR AND SWITCH FUNCTIONS PROPERLY.
B)
ISQLATION VALVES - ADD A NEW SR WHICH REQUIRES THE ISOLATION VALVE POSITION INDICATION CIRCUIT TO BE TESTED ONCE EACH YEAR TO DEMONSTRATE THAT THE POSITION SWITCHES AND INDICATORS FUNCTION PROPERLY.
C)
PURIFICATION COOLER LOOP - ADD A NEW SR WHICH REQUIRES THE PURIFICA-TION COOLER HIGH PRESSURE LOOP ISOLATION CIRCUIT TO BE TESTED ONCE EACH QUARTER TO DEMONSTRATE THAT THE PRESSURE SWITCH FUNCTIONS TO CLOSE THE ISOLATION VALVES AT THE CORRECT SET PRESSURE.
a B.
STRUCTURAL INTEGRITY
.3 b) 1.
SYSTEM PRESSURE BOUNDARY LEAKAGE TESTING - ADD A NEW SR WHICH REQUIRES na THE SYSTEM PIPING TO BE EXAMINED FOR LEAKAGE ONCE EVERY YEAR DURING
]$.
OPERATION TO VERIFY THE INTEGRITY OF THE SYSTEM PRESSURE BOUNDARY.
PROPOSED SURVEILLANCE REQUIREMENTS PCRV SAFETY VALVES I
A.
OPERATIONAL READINESS l.
SYSTEM TESTING - COMPONENT TESTING IS ADEQUATE TO VERIFY SYSTEM PERFORMANCE.
2.
COMPONENT TESTING A).
RUPTURE DISCS - CONTINUE EXISTING SR 5.2.1A WHICH REQUIRES ONE OF THE TWO RUPTURE DISCS TO BE BENCH' TESTED EACH YEAR AT SHUTDOWN ON AN ALTER-NATING BASIS TO DEMONSTRATE THAT THE BELLEVILLE WASHERS DEFLECT AT THE CORRECT SET PRESSURE.
B)
SAFETY VALVES - CONTINUE EXISTING SR 5.2.1A WHICH REQUIRES ONE OF THE TWO SAFETY VALVES TO BE TESTED IN PLACE EACH YEAR AT SHUTDOWN ON AN ALTERNATE BASIS TO DEMONSTRATE THAT THE VALVE OPENS AT THE CORRECT SET PRESSURE.
a
.3 UN C)
SAFETY ISOLATION VALVES - ADD A NEW SR WHICH REQUIRES EACH ISOLATION VALVE TO BE EXERCISED THROUGH A PARTIAL STROKE SEMI-ANNUALLY AND r-
[O THROUGH A FULL STROKE ONCE EACH YEAR AT SHUTDOWN TO DEMONSTRATE THAT THE VALVE OPERATOR IS FUNCTIONING CORRECTLY.
ADD A NEW SR WHICH RE-QUIRES EACH ISOLATION VALVE TO BE TESTED IN PLACE ONCE EVERY TWO YEARS AT SHUTDOWN TO DEMONSTRATE THAT SEAT LEAKAGE IS ACCEPTABLE.
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t A.
OPERATIONAL READINESS (CONTINUED) 3.
INSTRUMENTATION AND CONTROL TESTING i
A)
SAFETY ISOLATION VALVES - CONTINUE EXISTING SR 5.2.1C2 WHICH REQUIRES THE POSITION INDICATION AND ALARM CIRCUIT TO BE TESTED AND CALIBRATED ONCE EACH YEAR AT SHUTDOWN TO DEMONSTRATE THAT THE POSITION SWITCHES, INDICATORS, AND ALARMS FUNCTION PROPERLY.
B)
RUPTURE DISC - CONTINUE EXISTING SR 5.2.1C1 WHICH REQUIRES THE ~ RUPTURE -
t DISC / SAFETY VALVE INTERSPACE PRESSURE ALARM CIRCUIT TO BE TESTED O EACH MONTH AND CALIBRATED ONCE EACH YEAR TO DEMONSTRATE THAT THE PRESSURE SWITCHES AND ALARMS FUNCTION PROPERLY.
C)
CONTAINMENT TANK - ADD A NEW SR WHICH REQUIRES THE CONTAINMENT TANK PRESSURE ALARM CIRCUIT To BE TESTED AND CALIBRATED ONCE EACH YEAR TO DEMONSTRATE THAT THE PRESSURE SWITCH AND ALARM FUNCTION PROPERLY.
7b
};Q D)
SAFETY VALVE-ADD A NEW SR WHICH REQUIRES THE SAFETY VALVE BELLOWS RUPTURE ALARM CIRCUIT TO BE TESTED PRIOR TO SAFETY VALVE TESTING T0 DEMONSTRATE THAT THE PRESSURE SWITCH AND ALARM FUNCTION PROPERLY.
c3 c2 E)
RADIATION SHINE MONITOR - CONTINUE SR 5.4.9 WHICH REQUIRES THE DIS-CHARGE PIPING RADIATION SHINE MONITOR TO BE TESTED ONCE EACH WEEK AND CALIBRATED ONCE EACH YEAR TO DEMONSTRATE THAT THE MONITOR FUNCTIONS PROPERLY.
s B.
STRUCTURAL INTEGRITY 1.
SYSTEM PRESSURE BOUNDARY LEAKAGE TESTING A).PCRV PEQETRATION PIPING - CONTINUE EXISTING SR 5.2.16 WHICH REQUIRES PCRV PENETRATION INTERSPACE LEAKAGE TO BE MONITORED CONTINU0USLY AND i
MEASURED'ONCE EACH MONTH TO VERIFY THE INTEGRITY OF THE PCRV SAFETY VALVE PENETRATION PIPING.
B)
SYSTEM PIPINE - ADD A NEW SR WHICH REQUIRES THE NORMALLY UNPRESSURIZED SYSTEM PIPING (BETWEEN THE RUPTURE DISC AND. SAFETY VALVE) TO BE EXAMINED FOR LEAKAGE ONCE EVERY TWO YEARS DURING THE SAFETY VALVE SET POINT TEST TO VERIFY THE INTEGRITY OF THIS PIPING.
THE INTEGRITY OF NORMALLY PRESSURIZED SYSTEM PIPING IS VERIFIED BY THE CONTAINMENT TANK PRESSURE ALARM CIRCUIT, WHICH CONTINUOUSLY MONITORS FOR LEAKAGE.
2.
STRUCTURE INSPECTIONS A)
PCRV SAFETY VALVE TANK - MODIFY EXISTING SR 5.2.1 TO REQUIRE THAT THE TANK CLOSURE FLANGE SEAL LEAKAGE BE DETERMINED ONCE EACH YEAR FOLLOWING TANK CLOSURE TO DEMONSTRATE LEAK TIGHTNESS OF THE CLOSURE SEAL.S.
CU (NOTE:
THIS TEST IS CURRENTLY BEING PERFORI'ED).
MODIFY THIs SR TO ALSO REQUIRE THAT THE TANK CLOSURE BOLTING BE EXAMINED ONCE EACH
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YEAR TO VERIFY THE ABSENCE OF VISIBLE SURFACE DEFECTS AND THAT THE TANK WELD JOINTS BE EXAMINED FOR LEAKAGE ONCE EVERY FIVE YEARS DURING THE COVER FLANGE LEAK TEST.
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l PROPOSED SURVEILLANCE REQUIREMENTS PRE-STRESSED CONCRETE REACTOR VESSEL A.
OPERATIONAL READINESS 1.
INSTRUMENTS AND CONTROLS A). PENETRATION INTERSPACES - CONTINUE EXISTING SR 5.2.15 AND SR 5.2.16 WHICH REQUIRE THE PCRV PENETRATION INTERSPACE PRESSURE AND FLOW IN-DICATING CIRCUITS TO BE TESTED ONCE EACH MONTH AND CALIBRATED ONCE EACH YEAR TO DEMONSTRATE THAT I: INSTRUMENTS FUNCTION PROPERLY.
B)
TENDONS - CONTINUE EXISTING SR 5.2.3 WHICH REQUIRES THE TENDON LOAD CELLS TO BE TESTED AFTER 1, 3, 8, 13, 18, 22. 28 YEARS OF OPERATION 2
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TO DEMONSTRATE THAT THE LOAD CELL REFERENCE POINTS HAVE NOT SHIFTED.
ADD A NEW SR WHICH REQUIRES THE LOAD CELL ALARM CIRCUIT TO BE TESTED in ONCE EACH YEAR TO DEMONSTRA7E THAT THE ALARM FUNCTIONS PROPERLY.
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B.
STRUCTURAL INTEGRITY 1.
PRESSURE BOUNDARY LEAKAGE TESTING A)
EENETRATION INTERSPACES
- CONTINUE EXISTING SR 5.2.16A WHICH, REQUIRES THE PENETRATION INTERSPACE LEAK RATE TO BE MEASURED ONCE EACH MONTH TO MONITOR AND VERIFY THE INTEGRITY OF THE PENETRATIONS AND CLOSURES.
THE INTERSPACE LEAK RATES ARE ALSO MONITORED CONTINUOUSLY AND ALARMED IF ABNORMAL TO PROVIDE ADDITIONAL ASSURANCE OF INTEGRITY.
2.
STRUCTURE INSPECTIONS
, A)
OVERALL STRUCTURE - ADD A NEW SR WHICH REQUIRES THE PRESSURE VS.
DEFLECTION CHARACTERISTICS OF THE OVERALL PCRV STRUCTURE TO'BE MEASURED AFTER 1, 3, 5 10,15, 20, AND 25 YEARS OF OPERATION TO
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VERIFY THAT THE RESPONSE IS ELASTIC AND THAT NO SIGNIFICANT PERMANENT STRAINS EXIST.
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2.
STRUCTURE INSPECTIONS (CONTINUED)
B)
CONCRETE SURFACES - CONTINUE EXISTING SR 5.2.4 WHICH REQUIRES THE TOP, BOTTOM, AND SIDE SURFACES OF THE PCRV CONCRETE TO BE VISUALLY EXAMINED AFTER 1, 3, 13, AND 23 YEARS OF OPERATION TO VERIFY STRUCTURAL INTE-GRITY BY ASSESSING THE SURFACE CRACKING PATTERNS AND SIZES.
C)
CONCRETE HEADS AND WALL - CONTINUE EXISTING SR 5.2.13 WHICH REQUIRES THE HELIUM PERMEATION RATE OF THE CONCRETE IN THE PCRV HEADS AND SIDE WALL TO BE MEASURED AFTER 3, 8,13,18, 23, AND 281: YEARS.0F :0PERATION, AND THAT ANY CHANGES IN THIS RATE BE ASSESSED TO VERIFY STRUCTURAL INTEGRITY.
D)
PCRV LINER - CONTINUE EXISTING SR 5.2.5 WHICH REQUIRES THE CHARPY IMPACT SPECIMENS, PLACED ADJACENT TO THE OUTSIDE SURFACE OF THE TOP HEAD LINER, T.0 BE TEE ED AFTER 5, 15, AND 25 YEARS OF OPERATION TO VERIFY THAT CHANGES IN NOTCH TOUGHNESS DUE TO IRRADIATION ARE CONTINUE EXISTING SR 5.2.14 WHICH REQUIRES SELECTED ACCEPTABLE.
AREAS OF THE PCRV LINER WALL THICKNESS TO BE MEASURED BY ULTRASONIC TESTING AFTER 3, 5, 15, AND 25 YEARS OF OPERATION TO VERIFY THAT CHANGES IN WALL THICKNESS DUE TO CORROSION ARE ACCEPTABLE.
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2.
STRUCTURE INSPECTIONS (CONTINUED)
E)
PCRV TENDON ANCHORS - ADD A NEW SR WHICH REQUIRES 5% OF THE PCRV
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TENDON END ANCHOR ASSEMBLIES TO BE VISUALLY EXAMINED AFTER i
1, 3, 8, 13, 18, 23, AND 28 YEARS OF OPERATION TO VERIFY THAT.N0 CORROSION DAMAGE OR OTHER EVIDENCE OF CHANGES IN. STRUCTURAL INTE-l GRITY EXISTS.
F)
PCRV TENDON WIRES - CONTINUE EXISTING SR 5.2.2 WHICH REQUIRES 1% OF THE TENDON TUBE WIRE SAMPLES TO BE VISUALLY EXAMINED AFTER 1, 3, 8, 13, 18, 23, AND 28 YEARS OF OPERATION TO VERIFY THAT NO CORROSION DAMAGE EXISTS.
G)
PCRV TENDON TUBEE - CONTINUE EXISTING SR 5.2.2 WHICH REQUIRES A SAMPLE OF THE ATMOSPHERE IN A REPRESENTATIVE NUMBER OF TENDON TUBES (WITH AND WITHOUT LOAD CELLS) BE TAKEN AND ANALYZED AFTER 1, 3, 8, 13, 18, 23, AND 28 YEARS OF OPERATION TO VERIFY THAT CORROSION PRO-a j{
DUCTS DO NOT EXIST.
en H)
TENDON LOADS - SELECTED TENDON PRESTRESS FORCES ARE MONITORED t~
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CONTINUOUSLY AND ALARMED IF ABNORMAL TO ENSURE THAT THE REQUIRED LOADS ARE MAINTAINED AND THAT AN OVERLOAD CONDITION DOES NOT EXIST.
NO NEW SR IS REQUIRED TO ASSURE THAT TENDON LOADS ARE ACCEPTABLE.
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