L-88-366, Changes,Tests & Experiments Made W/O Prior Commission Approval for Jul 1987 - June 1988
| ML20153G510 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 06/30/1988 |
| From: | Conway W FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| L-88-366, NUDOCS 8809080187 | |
| Download: ML20153G510 (163) | |
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IlmEIIITEM This nport is submitted in accettlance with 10 CTR 50.59 (b), Wtich requires that raports off i) changes in the facility as described in the 75AR
- 11) changes in the procedures as desTibed in the FSAR, ard 111) tests ard experiments not described in the 75AR Wtich aru corrhacted without prior r==immica asfawal be reported to the
! Omraissicx1 at least amually. This report is intanded to most this requirement for the period July 1,1987 throur,h June 30, 1944.
l Titis report is dividsd into three sectims; the first, Plant Change /Modifica-i tiene, covering changen in the facility as described in the 75 arf the secord,
, Prw*ttro Charges cxwaring changes in the gh as descriked in the FSAR/
and the third, Tests and Experiments, czwering tests and experiments not j - in .
Appeniix A to this iW is a list of safety ard power operated relief valve actuations, Wtich is =*=lttad in accordance with FWs ocusaitaant to etmply i
with the requirusents of Itsu IIK.3.3 of M.5tR3 0737.
period frus July 1, 1987 to June 30, 1944.
This iW coven the j Aspanilx 5 to this swi is a samary of the finiings of the Stam Generator i J
tube inspecticri performed cut Unit 3 å the swi period trta July 1,1987 '
I thrum #1 Jun 30,1988. ,
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] Agfanilx c to this iwi cantains the summary of the tkilt 3 Cycle 1.1 reload evaluatica that m perfcriand for that relout. (ktit 4 did not ruftaal daring 1 this i w i period.
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'IMIG3r IUDff FUdff IMPIB 3 ADO 4 D000T IMEERS 50-250 NO 50-251 QUH2B, 'ITHIS, MO EXHRDENIS NME WIDDIP IRIGt CDGESSIM ARWNAL RR 19RICO JUIE 1,1987 DRIKM JtBE 30, 1988 IN CDELTANN WrIN TI11210, SICPICM 50.59(b) cxxx or nusAL manATIcnei
l TITLE 10, SECTION 50.59 CFR REPORT COMPLETED PC/M LIST JULY 1, 1987 THROUON JUNE 30, 1988 a
PC/M NO. PC/M .. TITLE .. DESCRI PTION UNIT ;87-296 UTILIZATION OF C-BUS BATTERY FOR TESTING 3&4 OF STATION BATTERY 3A 87-098 INSTALLATION OF UNDERVOLTAGE TRIP DEVICE 4 FOR POLAR CRANE BREAKER
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85-121 PLANT COMMUNICATION SYSTEM - UNDERVOLTAGE 3&4 f CONDUIT ,83-086 GROSS MVAR TELEMETERING 3 I l
87-100 AUXILIARY POWER UPGRADE TRANSFER OF LOADS 3 j 1 82-101 AUXILIARY POWER UPGRADE TRANSFER OF LOADS, 4 i UNIT 4 87-348 INSTALL.'\ TION OF PORTABLE BATTERY CHARGER FOR 3 l 4 STATION BATTERIES, 3A, 3B, 4A & 4B EQUALIZERS l 4 87-344 BATTERY CHARGER 3B, 4A, AND 4S VENDOR WIRING 0 ,
MODIFICATIONS l
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(87-243 TRANSFER SWITCH UPGRADE FOR DP-312A AND DP-412A 3&4 j 87-093 ACCEPTANCE CRITERIA AND INSTALLATION DETAILS 3 [
J FOR RAYCNEM SPLICES .
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4 87-008 NRC IE BULLETIN 85-03 MOV POSITION INDICATION 3 l
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85-064 GENERAL ELECTRIC SAM RELAY MODIFICATION P.C. 3 !
CARD REPLACEMENT i 1
85-031 4100V SWITCHGEAR CONTROL MODS 3 I 85-029 4160V SWITCHGEAR SYNCHRONIZING CIRCUIT 3 '
j MODIFICATIONS l
} 86-073 MAIN TRANSFORMER TIE LINE INSUIATORS CHANGE OUT 4
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1 i TITLE 10, SSCTION 80.89 CFR REPORT COMPLETED PC/M LIST i j JULY 1, 1987 THROUGN JUNM 30, 1988 ;
i PC/M NO. PC/M_ TITLE. DESCRIPTION EMI2 1
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85-125 CONTROL BUILDING ELEVATOR VESTIBULE POWER 0 i RECEPTACLE
) i 57-005 I&E BULLETIN 85-03 MOV SWITCH SETTINGS 3 !85-178 ADDITIONAL COMPONENT LIGHTING FOR AUXILIARY 4 FEEDWATER AREA i !
i l 87-355 ICW PUMP 4-C MOTOR TERMINATION 4 ;
i j 85-177 ADDITIONAL COMPONENT LIGHTING FOR AUXILIARY 3 ;
j FEEDWATER AREAS l
I 86-072 MAIN TRANSFORMER TIE LINE INSULATORS CHANGE OUT 3 !
l l j 87-328 REDESIGN OF SUPPORTS FOR MAIN STEAM FLOW 3
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- TRANS"ITTER LINES e I ,87-230 MISCc6,\NEOUS GAS SYSTEM: TUBING / SUPPORT 3 !
I-REPLACE.4ENT l
86-028 AUXILIARY FEEDWATER INDICATION UNDER THE 3 J
MAIN TEEDWATER PLATFORM l i '
l 85-176 NITROGEN S'."TION ADDITIONS AND RELOCATION 4 l 85-173 AUXILIARY FEEDWATER PUMP / TURBINE RPM MONITORING 3&4 I
] 88-048 STEAM-TO-MSR "C' BYPASS FLOW CONTROL 3 [
j SOLENOID VALVE REPLACEMENT l i
1 87-056 DEAREATOR VACUUM PUMP SOLENOID VALVE 3 !
j REPLACEMENT l
87-048 !
4 P1-4-1454 ROBERT SHAW VS. ASHCROFT 4 ,
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i 87-035 SSGFW PUMP DISCHARGE PI REPLACEMENT 0 j 1
f 87-032 ICW BASKET STRAINER DP GAUGE REPLACEMENT 4 l
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i TITLE 10, SECTION 50.59 CFR REPORT COMPLETED PC/M LIST JULY 1, 1987 THROUGM JUNE 30, 1988 j PC/M NO. PC/M TITLE DESCRIPTION UMIT 87-047 PI-1453, 1454 ROBERT SHAW GAUGES VS. ASHCROFT 3 i 86-231 L.P. HTR PI-1564 REPLACEMENT 4 L 86-221 FEECWATER CONTROL BYPASS SOLENOID VALVE 4 j COIL REPLACEMENT 87-217 RCS SAMPLE HX OUTLET PRE ~SURE GAUGE 4 '
j REPLACEMENT l 1 i
.87-173 CHANGE OUT OF POSITIONER ON CV-1606, 4 !
1607, 1608, STEAM DUMP TO ATMOSPHERE [
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87-172 CHANGE OUT OF POSITIONER ON CV-1606, 3 l 1607, 1608, STEAM DUMP TO ATMOSPHERE
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i 87-216 RCS SAMPLE HX OUTLET PRESSURE GAUGES 3 l REPLACEMENT 3
j 8P-112 APRI DETECTOR AND CABLE UPGRADE 4 i a l i 85 001 MAIN CONTROL ROOM EMERGENCY LIGHTING O h 84-005 CABLE TRAY MODIFICATIONS 4 !
- 84-004 CABLE TRAY MODIFICATIONS 3 t l
84-003 CABLE TRAY MODIFICATION IN THE CABLE 3
- SPREADING ROOM !
i 83-221 SECURITY LIGHTING UPGRADE O l
- i i 80-019 INSTALLATION OP FLOW & PRESSURE INDICATION 3&4 l
! INSTRUMENTATION FOR SSGP PUMPS i
)85-090 CONTAINMENT PURGE SOLENOID VALVES 3 !
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83-199 INSTALIATION OF REACTOR EX-CORE 3 r NEUTRON FLUX MONITORING SYSTEM l i
l i 83-030 ADDITION OF RCP NO. 2 SEAL LEAKOFF MEASUREMENT 3&4 i
j 83-031 ADDITION OF RCP NO. 2 SEAL LEAKOFF MEASUREMENT 3&4 j
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TITLE 10, SECTION 50.59 CFR REPORT COMPLETED PC/M LIST JULY 1, 1987 THROUGN JUNE 30, 1988 PC/M NO. PC/M TITLE DESCRIPTION EMIT 85-097 S/G LEVEL CONTROL ALTER!! ATE / NORMAL CONTROL 3 85-098 S/G LEVEL CONTROL ALTERNATE / NORMAL CONTROL 4 84-195 ADDITION OF RHR TEMPERATURE ALARM 3 84-196 ADDITION OF RHR TEMPERATURE ALARM 4 88-011 NIS SOURCE RANGE DETECTOR HIGH VOLTAGE 3 SKUTOFF CIRCUIT MODIFICATION 87-105 CRDM CONNECTOR AllD CABLE REPLACEMENT 4 87-118 SOLENOID VALVE FOR RCDT ISOLATION TO PUMPS 3 87-119 SOLE!10ID VALVE FOR RCDT ISOLATIO!! TO PUMPS 4 87-060 PRMS MONITOR DRAWER REPLACEMEllT 3 87-082 UPGRADE OF APRI CABLES AllD CO!!NECTORS 3 87-083 UPGRADE OF APRI CABLES AllD CON!!ECTORS 4 87-011 PRESSURIZER HEATER AC POWER CollTROL METERING 3 86-251 PRESSURIZER LIQUID / STEAM SAMPLE CONTAINMENT 3 ISOLATIO!! SOLEllOID VALVE REPLACEMENT 86-239 REPLACEMEliT OF REACTOR PROTECTION SYSTEM TEST 3 SELECTOR SWITCH 86-224 PASS TLOW LINERIZER REPLACEMENT 3&4 86-050 N2 REGULATORS FOR OMS 3 86-123 REPLACEMENT OF HIGH-RANGE GAMMA RADIATION 3 READOUT MODULES86-118 FLEX HOSE REPLACEMENT CV-200A 3&4 86-014 REACTOR CAVITY SEAL REPLACEMEllT 3 87-194 CONTAINMENT SPRAY RESTRICTING ORIFICE 3
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! TITLE 10, SECTION 50.59 CFR REPORT COMPLETED PC/M LIST j JULY 1, 1987 THROUON JUNE 30, 1988 [
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) h PC/M Mo. PC/M TITLE DESCRIPTIOM UMIT !
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I 87-121 NORMAL CONTAINMENT COOLER DRIP PANS 3 !
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l 87-122 EMERGENCY CONTAINMENT COOLER DRIP PANS 3 l l -
i 47-346 UNIT 4 TEMPORARY SUPPORT FOR SI ACCUMULATOR LINE 4 l I
j 87-353 RMR PUMP RECIRC. INSTALLATION 3 ;
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!87-384 CONTAINMENT AIR SAMPLE SYSTEM MODIFICATION 4 i
)87-171 REACTOR VESSEL HEAD INSULATION PERMANENT 3&4 i REPLACEMENT 87-223 REACTOR HEAD VENT PIPE SUPPORT H-2 MODIFICATION 3 !
< t l 87-164 GREASE KIT REPLACEMENT - EMERGENCY CONTAINMENT 3&4 !
! Co0LERS AND FILTERS j l
,86-045 AUXILIARY TEEDWATER TURBINE EXHAUST SILENCER 3&4 !
j CONDENSATE REMOVAL j 1
85-172 AUXILIARY FEEDWATER PUV Ne STEAM TRAP AND 3&4 l I DRAINAGE PIFING 86-104 AUXILIARY FEEDWATER Pt
,,tPLACEMENT IMPELLER 3&4 I
- JPE-M-86-046 I 86-011 AUXILIARY FEEDWATER STEAM SUPPLY VALV2 REPLACEMENT 3 4
86-009 AUXILIARY TEEDWATER STEAM SUPPLY VALVE REPLACEMENT 4 i
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)84-089 CONTAINMENT PURGE VALVE BOLTS 3 I 4
84-144 REPLACEMENT OF VALVE 3-89eT FOR CTMT SPRAY 3 1 j RECIRCULATION TEST LINE 4 l j 85-072 SPENT FUEL PIT BUILDING WALL JOINT REFAIR 4 t
j 85-129 CONTAINMENT TEMPERATURE RECORDED REPLACEMENT 4 86-115 NIS SOURCE RANGE PRE-AMPLIFIER REPLACEMENT 3 86-168 MOV-3-750 AND MOV-3-751 LIMIT SWITCH ADJUSTMENT 3 l -v-l i
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f TITLE 10, SECTION 50.59 CFR REPORT f
, COMPLETED PC/M LIST l
- JULY 1, 1987 TNROUGN JUNE 30, 1988 l
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E!1M Mo. PC/M TITLE DESCRIPTIOW UNIT l E
i 1 87-349 RESOLUTION OF DEFICIENCIES ASSOCIATED 3 ,
l WITH PRESSURIZER INSTRUMENTATION ;
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j 87-138 CCW HEAT EXCHANGER CHANNEL HEAD REPLACEMENT 3 i i 86-183 ACCESS FOR EDG RADIATOR DRAIN VALVES 3&4 i 86-210 ICW CHECK VALVE REPLACEMENT 3 l 87-022 HYORAULIC SNUBBER REPLACEMENT MAIri STEAM SYSTEM 3 l j 87-098 INSTALLATION OF UNDERVOLTAGE TRIP DEVICE 4 l j FOR POLAR CRANE BREAKER i 1 l 87-088 ASHCROFT TEMPERATURE INDICATOR REPLACEMENT 3 ;
i i 86-101 EMERGENCY DIESEL "B" AUXILIARY POWER SUPPLY 3&4 i j REI4 CATION l l I j 85-175 NITROGEN STATION ADDITIONS AND REI4 CATION 3 l
j 83-152 CABLE REROUTING FOR APPENDIX R MODIFICATIONS 4 f
I 81-162 INSTALIATION OF INADEQUATE CORE COOLING SYSTEM 3 !
- INSTRUMENTATION
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j 87-127 ACCUMULATOR SI TEST LINE SOLENOID VALVES 3 ;
REPLACEMENT
86-141 TEST CONNECTIONS FOR SECONDARY PUMPS 3 l 86-172 NIS ROTARY SWITCH KNOBS 4 f 87-207 ICW CHECK VALVES FILTER REGULATOR CUTPUT 3 t
, RANGE SPRING REPLACEMENT l 87-247 CV-3-2026 REPLACEMENT OF STEM CONNECTOR 3 87-298 MODIFICATION OF CCW PIPING AND SUPPORT FOR 3 l 3B RCP OIL COOLER I 1
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TITLE 10, SECTION 50.59 CFR RSPORT '
COMPLETED PC/M LIST i JULY 1, 1987 THROUGN JUNE 30, 1988 i
) PC/M No._ PC/M TITLE.DISCRIPTION UMIT I
j 87-331 HEAT TRACE PANELS 1A, 1B, 9A AND OB REWORK 3&4 l l 87-335 MODIFICATION OF PIPE SUPPORTS SR-36 AND WHIP 3 RESTRAINT !
4 87-407 MESUPPORT OF THERMOSTATS FOR BORIC ACID 3&4 i SYSTEM HEAT TRACING CIRCUITS 6A & 65 ;88-02S VALTEK POSITION FOR FOLLOWER PIN INSTALLATION O 86-105 UNIT 3 ICW PUMP DISCHARGE CHECK VALVE REPLACEMENT 3 i
j 86-106 UNIT 4 ICW PUMP DISCHARGE CHECK VALVE REPLACEMENT 4 >
1 l 87-070 FEEDWATER SOLENO TLNE REPLACEMENT 3 j 87-071 FEEDWATER SOLENOIL .nLVE REPLACEMENT 3 8 i !88-044 AUXILIARY FEEDWATER N2 BACKUP SYSTEM PRESSURE 3 j l INDICATOR REPLACEMENT l 88-045 AUXILIARY FEEDWATER N2 BACKUP SYSTEM PRESSURE 4 ,
INDICATOR REPLACEMENT ,
!88-050 BATTERY CHARGER 3B, 4A & 4S GATE-TILTER MODULE 3&4 I i REPLACEMENT
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{ 85-174 AUXILIARY FEEDWATER PERFORMANCE UPGRADE - REMOVAL 3&4 i
! 0F ABANDONED EQUIPMENT i 1 '
I 86-069 CONTROL ROOM HVAC TEST PENETRATIONS 3&4 i
07-042 SGBD FLOW CONTROL VALVES BODY / SEAT REPLACEMENT 3&4
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h 87-123 PORTABLE VENTILATING FANS F0h THE DC EQUIPMEN'6'/ 3&4 INVERT 0R ROOMS87-178 UNIT 3 REACTOR VESSEL CRDM DUMMY, HOUSING G-7 CAP 3 1
87-181 CRDM VENT SHROUD INSPECTION DOORS 3 i 82-060 COMPUTER ROOM ADDITION 344 l
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TITLE 10, SECTION 50.59 CFR REPORT COMPLETED PC/M LIST JULY 1, 1987 THROUGH JUNE 30, 1988 PC/M NO. PC/M TITLE DESCRIPTION MEIT 87-235 MAIN FEEDWATER VALVE TUBING REPLACEMENT 3 85-117 ADDITIONAL CABLE REROUTING FOR APPENDIX R 3&4 86-171 NIS ROTARY SWITCH KNOB REPLACEMENT 3 87-045 PRMS CHANNELS R4-17A AND R4-17B CABLE REWORK 4 87-185 REACTOR VESSEL CRDM DUMMY HOUSING G-7 AND G-9 CAP 3 I
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PLANT CHANGE / MODIFICATION 87-296 PC/M CLASSIFICATION: SR UNIT: 354 TURNED CVER DATE: 11/17/87 UTILIZATION OF C-BUS BATTERY FOR TESTING OF STATION BATTERY 3A Summary:
Installation of raceway and cable such that non-safety related battery 4C can be used to supply the loads of DC Bos 3A while safety relcted station battery is being load tested.
Safety Evaluation:
This modification does not adversely affect safety related equipment or systems, require any change to plant Technical Specifications, or constitute an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 87-098 PC/M CLASSIFICATION: NSR UNIT: 4 TURNED OVER DATE: 06/26/87 I)[j G2 TRIP DEVICE FOR POLAR CRANE BREAKER summary:
Installation of undervoltage trip device to the 480V Load Center Power Circuit Breaker serving the Unit 4 Containment Polar Crane.
Safety Evaluation:
Failure of the new component will not adversely affect any safety related system or function. In addition the U/V device has been seismically qualified and will be installed in accordance with specifications for safety related work. Therefore, this change does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 85-121 PC/M CLASSIFICATION: NSR UNIT: 3&4 TURNED OVER DATE: 07/13/87 PLANT COMMUNICATION SYSTEM - UNDERVOLTAGE CONDUIT Summary:
This PC/M provides a raceway system for the new plant communication system being installed to replace the two existing telephone systems. The new communication system will be located in the new Administration Building.
Safety Evaluation 1 This PC/M only adds a new racoway system for a new plant communication system. This raceway system does not interface witu the Nuclear Units 3 or 4 nor are they installed within the power block. Also this raceway system is not installed in proximity to any safety related equipment. Therafore, this modification does not require a change to plant Technical Specifications, or constitute an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 83-086 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 04/22/86 GROSS MVAR TELEMETERING Sumaary 3CWI/3C14M-RTU-/4. Cable should not be deleted, therefore the new cable number should be 3GV/3C14M-RTU/6 to keep the cable numbering sequence correct.
gaiety Evaluation This modification is not Nuclear Safety Related Systems or features in the plant. All previous applications of the Data Acquisition package and the RTU will not be affected. Therefore, this change does not create an unroviewed safety question.
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PLANT CHANGE / MODIFICATION 82-100 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 09/04/87 AUXILIARY POWER UPGRADE TRANSFER OF LOADS summary:
This modification transferred existing non-class 1E loads to the new C-bus switchgear, new load centers, existing condensate lead center, and to the new 125 volt non-class 1E DC system for Unit 3, Safety Evaluation:
This PC/M is not safety related and the written safety evaluation was provided under PC/M 82-98. This was done to evaluate the entire auxiliary power upgrade scope against existing licensing commitments and to determine if any unroviewed safety questions are involved.
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PLANT CHANGE / MODIFICATION 82-101 PC/M CLASSIFICATION: NSR UNIT: 4 TURNED OVER DATE: 04/04/88 AUXILIARY POWER UPGRADE TRANSFER OF LOADS, UNIT 4 Summarvt This modification transferred the following loads: SGFP 4B; Cond.
P 4C; LC4E; MCC 4B, 4C; RA; Amortap MCC Unit 4; MCCD, 4E, F; SFPM 4P 12B; 125V DC Emer. B.O.P. 4P30; A.S.O.B.P. 4P38 and 120V AC Security System.
Safety Evaluation:
This PC/M is not safety-related and its design insured minimum interferences with safety related equipment, it does not involve an unreviewed safety question.
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1 PLANT CHANGE / MODIFICATION 87-348 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 04/14/88 INSTALLATION OF PORTABLE BATTERY CHARGER FOR STATION BATTERIES 3A, 3B, 4A E 4B CELL EOUALIBERS summary:
The purpose of this PC/M is to provido details for structural support of the portable battery charger.
Safety Evaluation:
While in use, the portable charger will be securely anchored to preclude potential interaction to safety related syst ams. This
, modification does not involve an unroviewed safety question.
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PLANT CHANGE / MODIFICATION 87-344 PC/M CLASSIFICATION: SR UNIT: 0 TURNED OVER DATE: 12/21/88 BATTERY CHARGER 3B, 4A, AND 48 VENDOR WIRING MODIFICATIONS Summary:
The existing six gating and filter (GFM) cards in each of the three Exide model UPC 130-3-300 battery chargers 3B, 4A, and 4S shall be replaced with level revision H of electronic module card Part #101-071-629.
Safety Evaluation:
The replacement GFM cards are qualified maintenance components procured from the original vendor to perform the same function as the original cards. Therefore, installation of these cards do not create an unroviewed safety question.
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PLANT CHANGE / MODIFICATION 87-243 PC/M CLASSIFICATION: SR UNIT: 3&4 TURNED OVER DATE: 02/19/88 TRANSFER BWITCH UPGRADE FOR DP-312A AND DP-412A Summary:
This modification involves removing the existing obsolete automatic transfer switches located in DP-312A and DP-412A and installing new ones. The new switches are installed in NEMA-12 enclosures located outside DP-312A and DP-412A.
Safety Evaluation:
This modification enhances the operability and reliability of the 120V AC Normal / Emergency power supplied to Distribution Panels DP-412A and DP-312A. This modification does not alter the function of DP-312A and DP-412A. Therefore, replacement of these switches does not create an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 87-093 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 10/21/87 ACCEPTANCE CRITERIA AND INSTALLATION DETAILS FOR RAYCHEM SPLICE 8 Summaryl Design details have been developed to depict the qualified Raychem splice details. These details are being issued to provide clarification for installation and acceptance criteria for existing Raychem splices.
Safety Evaluation:
No modifications to existing plant design are covered with this PC/M. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION __87-008 PC/M CLASSIFICATION: A.._
UNIT: 3 TURNED OVER DATE: 02/05/88 NRC IE BULLETIN 85-03 MOV POSITION INDICATION Summary,L This modification to motor operated valves (MOVs) in the Auxiliary Feodwater System and the High Head Safety Injection System provides for selecting the thermal overload heater sizes for the applicable MOVs.
Safety Evaluation
- This modification will increase the availability of the MOVs during safe shutdown conditions and improves the MOV position indication provided to control room operators. Since the MOVs being modified are classified as 1E, the modification is considered to be safety related and does not involve an unreviewed safety question.
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1 PLANT CHANGE / MODIFICATION 85-064_
PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 01/05/88 GENERAL ELECTRIC SAM RELAY MODIFICATION P.C. CARD REPLACEMENT i
Summarvt.
This PC/M incorporates a design change which replaces the existing printed circuit board in the GE Type SAM timing relay to eliminate the possibility of foreshortening timing by the relay.
safety Evaluation No external wiring changes will be made and the relay's function will remain unchanged. This then precludes any new type of interaction with nuclear safety equipment. Therefore, this modification does not involve an unroviewed safety question.
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PLANT CHANGE / MODIFICATION 85-031 PC/M CLASSIFICATION: _NSR UNIT: 3 TURNED OVER DATE: 09/11/R7 4160V 8WITCHGEAR CONTROL MODS Summary:
This PC/M modifies the control circuit for 4KV Breakers. The 3A and 3B Bus modifications rewire the indicating light circuit and
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add a diode to nrevent false actuation of the breaker failure scheme. The 3C Bud mo6ifications include the above change plus the addition of an interlock to prevent the tripping of each bus feeder i breaker from the C-Bus transformers when tha alternate breaker is i operated in the test position.
i Safety Evaluation:
This modification does not affect the safety function of any of the breakers. This modification does not add any functional interconnection to any safety-related systems. All modifications are internal to the switchgear cubicle. The basic function of the incoming transformer breakers remains unchanged. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 85-029 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 01/05/88 4160V SWITCHGEAR SYNCHRONIZING CIRCUIT MODIFICATIONS Summary (
This modification adds a control switch 'close' contacc in series with the synchronism check relay (Type IJS) to eliminate the possibility of contact welding, thus improvi..g breaker closed circuit reliability.
Safety Evaluation 1 This modification utilizes an existing breaker control switch contact to protect the synchronizing check relay contact from continuous loading and possible welding. The relay contact will carry current only when the breaker control switch is operated to close the breaker. The modifications involve existing devices and internal wiring changes with the addition of fully qualified field cables. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 86-073 PC/M CLASSIFICATION: NSR UNIT: 4 TURNED OVER DATE: 04/14/88 MAIN TRANSFORMER TIE LINE INSULATORS CHANGE OUT Summary:
This modification replaces the dead end insulators attached to the Unit 3 and Unit 4 main transformers with new insulators of the same form, fit, and function.
Safety Evaluation:
These insulators perform no safety related function. Since the new insulators being installed are of equivalent form, fit, and function of tho existing insulators, this modification does not involve an unroviewed safety question.
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PLANT CHANGE / MODIFICATION 86-093 PC/M CLASSIFICATION: NSR UNIT: 3&4 TURNED OVER DATE: 11/11/87 INSTALLATION OF RACEWAY AND CABLE FOR PC/M 86-095 5 096 Summary:
This modifier. tion installs raceway and cabic associated with the repowering of the non-vital sections of MCC 3A, 3 D, and 4A under PC/M 86*095 and 86-096.
Safety Evaluationt This PC/M merely provides direction for the installation of raceway and raceway support and the pulling of cables within the installed raceway. No cable termination or determination is authorized by this PC/M. Based on the preceding, this modification does not constitute an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 85-125 PC/M CLASSIFICATION: _ NSR UNIT: 0 TURNED OVER DATE: 04/14/88 CONTROL BUILDING ELEVATOR VESTIBULE POWER RECEPTACLE Summary:
This PC/M installs cable and conduit from the C-Bus DC Enclosure Building lighting panel No. 80 to the Control Building elevator vestibule at the 18 foot elevation and terminates in a power receptacle. This outlet will provide a permanent power feed to operate a Coke machine now used by the control room personnel.
Safety Eya.luation:
, This additional conduit and power receptacle perform no safety-relaced function. There is no design intent discussed in the FSAR which may be altered by this installation. The conduit shall be mounted in accordance with the requirements for class lE Conduit in the vicinity of safety related components. The lighting panol is fed from a non-vital source. Thoroforo, this PC/M is non-nuclear safety related QA/QC required and does not involve an unroviewod, safety question.
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PLANT CHANGE /MODIFICA1 .A 87-005 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 02/12/08, IEE BULLETIN 85-03 MOV 8 WITCH BETTINGA Summary:
l This modification addresses Item b) of the Bulletin. It provide-the overall MOV switch setting policy for the Bulletin MOVs. This also provides guidelines for use of thermal overloads and space heaters.
Safety Evaluation:
The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR is not increased. This engineering package only provides the necessary design information required to set MOV switch settiras utilizing MOVATS signature analysis techniques.
The recommend (d switch sottings are considered enhancements to the existing sottings to further ensuro valve operability. Therefore, this modification does not involve an unroviewed safety question.
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PLANT CHANGE /HODIFICATION 85-178 PC/M CLASSIFICATION: MSR UNIT: 4 TURNED OVER DATE: 07/28/87 i
1 hQQJTFONAL CORPONENT LIGHTING FOR AUXILIARY FEEDWATER AREA lussME1.
Modi!y and install new component lighting in the Auxiliary Feedwater Areas providing light fixtures and associated raceways ;
for Auxiliary Feedwater Control Valve Platforms & adjacent areas, Auxiliary Steam Supply MOV Platform and the Main Feedwater Platforms for Unit 4.
Safety EvalVationt This modification merely adds new lighting to the existing ,
Auxiliary Feedwater Area, it does not change the operation of any system related to safety, therefore this does not involve an unreviewed safety question. i i
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PLANT CHANGE / MODIFICATION 85-179 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 09/09/87 ADDITIONAL COMMUNICATIONS FOR AUXILIARY FEEDWATER SYSTEM Sumaarv f.
This modification adds a dedicated Alternate Shutdown Communication System on the Auxiliary Feedwater Control Valve Platforms and the Main Feedwater Platforms for Units 3 and 4.
l Safety Evaluation:
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This installs a communication system in areas of the plant that contain equipment required for safe shutdown. This system is designed to upgrade the existing communication system for safe shutdown. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 87-355 PC/M CLASSIFICATION: SR UNIT: 4 TURNED OVER DATE: _1?/21/87 l
l ICW PUMP 4-C MOTOR TERMINATION l
Summary:
l Field fabricated (taped) stress cones on ICW Pump 4-C Motor Leads i are being replaced with Nuclear Class 1E qualified Raychem Connectors.
safety Evaluations r
j The Raychem kits are superior to the existing stress cones in that
, their insta?,lation is more repeatable and their performance is more predictable. Therefore, this modification does not involve an a unreviewed safety question.
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PLANT CHANGE / MODIFICATION 85-177 PC/M CLASSIFICATION: NSR_
UNIT: , 3 TURNED OVER DATE: 07/28/87 ADDITIONAL COMPONENT LIGHTING FOR AUXILIARY FEEDWATER AREAS Summary:
I This modification modified existing lighting and installed new lighting in the Auxiliary Feedwater Areas.
Safety Evaluation:
This modification did not intorface with any safety-relatcl i systems, no now loads were added to the Emergency Diesel Gener.3 tors l or Station: Battery and the margin of safety as defined in the basis for any plant Tech. Spec. was not decreased. This modification was quality related and did not involve an unreviewed safety question.
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PLANT CKANGE/ MODIFICATION 86-072 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 04/14/88 MAIN TRANSFORMER TIE LINE INSULATORS CHANGE UUT Summary:
This modification replaces the dead end insulators attached to the j
Unit 3 and Unit 4 main transformers with now insulators of the same r form, fit, and function.
Safety Evaluations i These insulators perform no safety related function. Since the new insulators being installed are of equivalent form, fit, and J function of the existing insulators, this modification does not involve an unroviewed safety question.
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PLANT CHANGE / MODIFICATION 87-328 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 02/04/88 i
REDESIGN OF SUPPORTS FOR MAIN STEAM FLOW TRAN8MITTER LINES Summarvt This modification enhances the tubing and supports for the Main
, Steam Flow Transmitters (FT-474,-475,-484,-485,-494 and -495) to
- reduce the vibration problem.
Safety Evaluation: ;
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! This modification will enhance the operation of the flow transmitters by reducing the existing vibration in the line. The function of the flow transmitters will not be affected by this.
Therefore, this modification does not involve an unreviewed safety question. !
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l PLANT CHANGE / MODIFICATION 87-230 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 01/04/88 MISCELLANEOU8 GAS SYSTEMt TUBINC/8UPPORT. REPLACEMENT Summary:
This modification replaces damaged tubing with identical tubing, reroute tubing if required, and replace the gang supports.
8afety Evaluat h The support designs hava considered all applicable load combinations for normal and accident conditions. The supports transmit loads to the existing trench structure in a similar manner and magnitude as the existing supports. The mounting of the supports will not affect any of the equipment in the surrounding area. Therefore, this modification does not involvo an unreviewed i
safety question.
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PLANT CHANGE / MODIFICATION 86-028 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 07/31/87
- AUXILIARY FstDWATER INDICATION UNDER THE MAIN FEEDWATER PLATFORM l
summary: i This modification provides details for the installation of flow t indicators for AFW Trains 1 and 2 and Steam Cenorator wide range
- level indicators.
l safety Evaluation:
Installation of new and replacement of existing indicators j introduce no new failure modes to the AFW system. Instruments '
being installed are of higher reliability and improved quality.
Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 85-176 PC/M CLASSIFICATION: NSR UNIT: 4 TURNED OVER DATE: 06/26/87 NITROGEN STATION ADDITIQNS AND RELOCATION Summary:
This modification providos for relocation of an existing N2 bottle station for AFW control valvo and adds a new redundant bottle l station and associated tubing and instruments.
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BAfety Evaluationt This modification is an onhancomont of the e::isting AFW backup nitrogen system, and does not alter the basic function of the system. Thereforo, this does not involve an unroviewed safety question.
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PLANT CHANGE / MODIFICATION 85-173 PC/M CLASSIFICATION: NSR UNIT: 3&4 TURNED CVER DATE: 07/31/87 AUIILIARY FEEDWATER PUMP / TURBINE RPM MONIT.0 RING S.ymnary:
This modification installs RPM indicators on the Overhead Clock l Panel in the Main Control Room, thus informing the operators of the status of the Auxiliary Feedwater Turbines.
Safety Evaluation:
The RPM monitoring equipment is electrically isolated from all other safety related equipment. This does not functionally alter the operation of the AFW syctem. No safety characteristics will J
be affected and existing control functions are unchanged.
Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 88-048 PC/M CLASSIFICATION: __NSR UNIT: 3 TURNED OVER DATE: 04/14/88 STEAM-TO-MSR HCH BYPASS FLOW CONTROL SOLENOID VALVE REPLACEMENT Summary:
This modification will replace the existing ASCO solenoid model 831424 with model 8314C24. This solenoid is installed in the MSR "C" Steam Control Bypass Valve CV-2912.
Safety Evaluation:
The proposed replacement model provides the same function, specifications and piping / electrical connections to that of the existing model. Th tre f ore, installation of this replacement solenoid will not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 87-056 j
PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 01/25/88 DEAREATOR VACUUM PUMP SOLENOID VALVE REPLACEMENT Summary:
. This modification will replace the obsolete ASCO model WP 8210B2LB j with ASCO model 8211C94 on the SV-3420, control of cooling water to the Deareator Vacuum Pump.
Safety Evaluation:
SV-3420 serves no safety function, it is not required for safe shutdown nor is it directly associated with any safety related functions. Therefore, the replacement of the obsolete solenoid valve does not involve an unreviewed safety question.
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i PLANT CHAhe */ MODIFICATION 87-048-__
PC/M CLASSIFICATION: NSR UNIT: 4 TURNED OVER DATE: 04/14/88 i PI-4-1454 ROBERT SHAW V8. ASNCROFT
- Summary 1 This modification replaces the existing Robert Shaw pressure indicator PI-4-1454 with an Ashcroft Duragage Model 1379.
Safety Evaluationt P
The Screen Wash Pump disc.harge pressure gauge PI-4-1454 maintains a non-safety related pressure boundary and it has no safety i
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function. The Q-list does not show this gauge. Therefore, any l modifications to this gauge do not involve an us. reviewed safety L i
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PLANT CHANGE / MODIFICATION 87-035 4
PC/M CLASSIFICATION: NSR UNIT! O TURNED OVER DATE: 01/25/88 i
88GFW PUMP DISCHARGE PI EEPLACEMENT t
j Summary:
i This modification replaces the existing Robert Shaw pressure indicators PI-6511 A & B with Ashcroft Duragage Model 1379.
Safety Evaluation:
The SSGFP are usually required during normal plant startup, shutdown and hot standby modes of operation. They do not serve any safety function, they are not required for safe shutdown of the plant nor are they di*rectly associated with any safety relsted equipment. Therefore, any modifications to these pressure instruments do not involve an unrevleved safety question.
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PLANT CHANGE / MODIFICATION 87-032 PC/M CLASSIFICATION: NSR UNIT: 4 TURNED OVER DATE: 04/04/88 l 3
i ICW BASKET STRAINER DP GAUGE REPLACEMENT *
- Summary
, This modification installs Barton Model 227A in lieu of Barton i Model 227 differential pressure indicators for DPI-1400, 1401, 1 1402, and 1403. DPI-1400 and DPI-1401 provide local indication of !
DP across basket strainers in the intake cooling water lines to the turbine plant cooling water heat exchangers. DPI-1402 and DPI-1403 -
a provide local indication of DP across basket strainers in the intake cooling water lines to the conponent cooling water heat !
exchangers. j i
i i safety Evaluations !
The local indicators do not serve a safety function, however, the indicators wetted parts form part of the safety related pressure !
boundary. Their failure would not cause sufficient intake cooling water flow diversion to impede the ICW safety function since loss ;
of intake cooling water flow is less than one percent. Therefore, !
this modification does not involve an unreviewed safety qu2stion. ;
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PLANT CHAN(['/NODIFICATION 87-047 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 04/14/88 PI-1453, 1454 ROBERT SHAW GAUGES VS. ABMCROFT summary:
This modification replaces the existing Robert Shaw pressure indicators PI-1453 and PI-1454 with an Ashcroft Duragage, Model 1379.
Safety Evaluationt The Screen Wash Pump discharge pressure gauges PI-1453 and PI l 1454 Kaintain the non-safety related pressure boundary and have no safety or control functions. The Q-list does not show these I
gauges. Therefore, any modifications to these gauges does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 85-231 PC/M CLASSIFICATION: . NSR UNITt 4 TURNED OVER DATE: 09/11/87 L.P. ETR 71-1564 REPLACEMENT pummary This modification will replace the existing L.P. HTR PI-1564, a Robert Shaw model 672-B, with an Ashcroft model 1379.
safety Evaluation:
The L.P.H. 5A local pressure gauge PI-4-1564 does not provide a safety related function and is classified as non-safety related.
Therefore, a replacement of the existing model with a better model does not involve an unreviewed safety question.
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i PLANT CHANGE / MODIFICATION 86-221 PC/M CLASSIFICATION: SR UNIT: 4 TURNED OVER DATE: 04/14/88 I
FEEDWATER. CONTROL BYPASS SOLENOID VALVE COIL REPLACEMENT Summary:
This modification repla;'s the existing coil in the ASCO solenoid valve for FW control valve FCV-4-498.
safety Evaluation:
t The substitute coils are identical in form, fit and function to the existing coils, Furthermore, the substitute coils are of a higher temperature rating than the existing coil. Therefore, this modification does not involve an unreviewod safety question. li L
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l l PLANT CHANGE / MODIFICATION 87-217 t
PC/M CLASSIFICATION: NSR i
UNIT: 4 TURNED OVER DATE: 04/06/88_
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RC8_5 AMPLE._EX_ OUTLET PRESSURE GAUGE REPLACEMENT summary:
This modification replaces U.S. Gaugo model 1933 with Ashcroft 1377 for PI-902, PI-906, and PI-908.
i safety Evaluationt :
The subject pressure gauges do not perform any safety function, and they have no input to safety related systems. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 87-173 PC/M CLASSIFICATION: SR UNIT: 4 TURNED OVER DATE: 09/11/87 CHANGE OUT OF POSITIONER ON CV-1606, 1607, 1608. STEAM DUMP TO ATMQH NERE i
summary:
- l This repl cos the existing Fisher model 3560 r.odification ,
. positioner with seismically qualified Fisher model 3582G '
positioner.
- Safety Evaluation: L j The replacement positioner in equal to or better than the existing ,
i positioner in quality, form, fit and function. Both have the same accuracy, repeatability, range and cam characteristics. Therefore, this modification does not involve an unreviewed safety question. !
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i PLANT CHANGE / MODIFICATION 87-172
- PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 09/11/87 i
- CHANGE QUT OF POSITIONER ON CV-1606, 1607. 1608. STEAM DUMP TO ATMOSPHERE Summary
I
,l This modification replaces the existing Fisher model 3560 positioner with seismically qualified Fisher model 3582G positioner.
Safety Evaluat h i The replacement positioner is equal to or better than the existing positioner in quality, form, fit and function. Both have the same accuracy, repeatability, range and cam characteristics. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CRANGE/ MODIFICATION 87-216 l
PC/M CLASSIFICATION: NSR UNIT: . 3 t TURNED OVEP. DATE: 04/06/88 l
RC8 SAMPLE HI OUTLET PRES 8URE GAUGES REPLACEMENT J
Summary , !
This modification replaces the existing U.S. Gauge model 1933 with ;
Ashcroft model 1377 fort l PI-902, Pressurizer steam sample line HX outlet pressure indicator I PI-906, Pressurizer liquid space sample line HX outlet pressure indicator PI-908, Hot leg /RHR sample line HX outlet pressure Indicator i
i Safety Evaluationt The subject pressure gauges do not perform any safety functions, I and they do not have input to enrety related sy;; ems. Therefore, this modification does not involve an unreviewed safety question.
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t PLANT CNANGE/ MODIFICATION 87-112 PC/M CLASSIFICATION: NSR UNIT: 4 TURNED OVER DATE: 12/09/87 [
APRI DETECTOR AND CABLE UPGRADE summarya This acdification will replace the cables and connectorP for the APRI detectars.
I j Safety Evaluationt The replacement parts are equal to or better than the existing f
cable and connectors in quality, fit, form, and function.
Therefore, this modification does not create an unreviewed safety i question, j
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PLANT CHANGE / MODIFICATION 85-001 PC/M CLASSIFICATION: NSR UNIT: 0 TURNED OVER DATE: 11/06/87 MAIN. CONTROL ROOM. EMERGENCY LIGHTING summary:
This modification consists of installing additional DC, battery powered, emergency lights; and relocating certain others in the control room to ensure adequate lighting needs.
safety Evaluationt This PC/M provides supplemental emergency DC lighting in the main control room. These modifications are non-nuclear safety related and arr,not connected to any safety features equipment other than the station batteries. Therefore, this modification does not constitute an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 84-005 PC/M CLASSIFICATION: SR UNIT: 4 _
TURNED OVER DATE: 12/03/87 CABLE TRAY MODIFICATIONS Summary:
1 Evaluation and modification of existing safety related and seismic II/I Unit 4 cable tray supports (excluding those in the Cable Spreading Room) are performed to establish fill load allowables.
1 safety Evaluationt 2
All work associated with this PC/M is safety related, i i Modifications to the cable tray support systems will not affect the i
operating function of the cable trays. This PC/M upgrades existing cable tray supports for the future addition of cable which will be ,
evaluated under future PC/Ms .
Therefore, no unreviewed safety ,
- question exists. l i
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PLANT CHANG 81/ MODIFICATION 84-004 ,
PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 12/03/87 i t
CABLE TRAY MODIFICATIONS 1 Summary: '
l l Evaluation and modification of existing safety related and seismic j II/I Unit 3 cable tray supports (excluding those in the Cable .,
Spreading Room) are performed to establish fill load allowables. ;
i Safety Evaluation: [
All work associated with this PC/M is safety related. !
j Modifications to the cable tray support systems will not affect the l operating function of the cable trays. This PC/M upgrades existing cable tray supports for the future addition of cable which will be t I
evaluated under future PC/Ms. Therefore, no unreviewed safety l l questions exist. t 1 ;
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PLANT CNANGE/ MODIFICATION 84-003-PC/M CLASSIFICATION: SR UNIT 3 _,
TURNED OVER DATE: 12/03/s7 CABLE TRAY MODIFICATION IN THE CARLE SPREADING ROOM summary Evaluation and modification of existing safety related and seismic II/I cable tray supports in the Cable Spreading Room are performed to establish fill load allowables, safety Evaluation:
All work associated with this PC/M is safety "elated.
Modifications to the cable tray support syrtems will not c ,ect the operating function of the cable trays. This PC/M upgrades axisting cable tray supports for the future addition of cable, which will be evaluated under future PC/Ms. Therefore, no unreviewed safety questions exist.
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I PLANT CHANGE / MODIFICATION 83-221-PC/M CLASSIFICATION: NSR UNIT 0 TURNED OVER DATEt 09/03/87 f
i SECURITY LIGNTING UPGRADE i 4
l Summary: ,
a i l This PO/M modifies the security lighting for PTP Units 1, 2, 3, and
- 4.
2 safety Evaluationt The security lighting upgrade circuits in this PC/M are classified t
, as non-safety related because ti.ey do not perform, or interface !
- with, any nuclear function. Therefore, this modification does not i
- involve an unreviewed safety question.
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J PLANT CHANGE / MODIFICATION 86-019 ;
PC/M CLASSIFICATION: NSR UNIT 3&4 TURNED OVER DATE: 03/07/88 INSTALLATIQM.OF FLOW & PRESSURE i.
INDICATION IMBTRUMENTATION FOR SSGF PUMPS
- 3.usmaryt This modificction installs pressure indicators and DP flow sensors l and flow indicators to measure flow in the discharge and recirculation lines and suction pressure of the SSGF pumps.
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Safety Evaluations r i
This modification is non-safoty related and will not degrade the existing installation. The Standby Steam Generator Feedwater Pump i System flow and pressure indication are completely independent and :
have no affect on the operability of any safety system. Therefore, l
I this modHication does not involve an unreviewed safety question.
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i PLANT CHANGE /NODIFICATION 85-090 ,
l PC/M CLASSIFICATION: NSR UNIT 3 TURNED OVER DATE: 12/14/87 f
CONTAINMENT PURGE SQLENCID VALVES Summaryt This modification replaces the existing scienoid valves with better (
temperature rating and environmentally qualified valves.
Safety Evaluationt There is no unreviewed safety question, this modification will !
improve the performance of the equipment, and there is no physical or dimensional changes. l b
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l PLANT CKANGE/ MODIFICATION 83-199 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 04/25/88 3
INSTALLATION OF REACTOR EI-CORE NEUTRON FLUX MONITORIMG SYSTEM a
j Summary: ;
This modification installs two now, redundant safety grade -
instrument loops which will provide source and power range neutron .
flux monitoring. !
j Safety Evaluation This system does not interface with the existing NSSS supplied nuclear instrumentation. All outputs from this new system which ;
I interface with non-safety related systems are isolated. This new i system does not provide any protective or control functions and -
) does not interface with any reactor protection circuitry. ,
J Therefore, this installation does not involve an unreviewed safety question. ;
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PLANT CHANGE / NODI?ICATION 83-030 t
PC/M CLASSIFICATION: NSR UNIT 3&4 TURNED OVER DATE: ,,,, 01/ 2 5/ a s
, I 4 i a n, j ADDITION OF RCP MO. 2 SEAL LEAROFF MEASUREMENT
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This modification installs additional RCP seal leakoff flow 1 measurement devices on the No. 2 seal. !
i Safety Evaluationt l
1 This modification is non-safety related as it has no !
! interconnection with any nuclear safety related system and does j not perform any nuclear safety related function. Therefore, this .
i modification will not involve an unreviewed safety question. [
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( PLANT CNANGE/ MODIFICATION 83-031 l 1
PC/M CLASSIFICATION: NSR UNIT 3&4 TUR!iED OVER DATE: 01/25/88 ADDITIOM.0F RCP MO, 8 SEAL LEAKOFF MEASUREMENT
- summary
This modification installs additional RCP seal leakoff flow
}
1 measurement devices on the No. 2 seal.
! safety Evaluatient
- l This modification is non-safety related as it has no j interconnection with any nuclear safety related system and does not i perform any nuclear safety related function. Therefore, this j modification will not involve an unreviewed safety question.
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l PLANT CHANGE / MODIFICATION 85-097 ,
i i PC/M CLASSIFICATION: NSR
. UNIT: 3 TURNED OVER DATE! 09/11/87 L
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I 3/G... LEVEL CONTROL ALTERMATE/ NORMAL CONTROL !
L j summary j This modification will replace the existing S/G Alternate / Normal I control selector switches with Westinghouse OT-2 switches with OT- l j 2V contact blocks.
i i l safety Evalvation
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d The Alternate / Normal selector switch pertains to control function
! only and is completely isolated from protection circuits. There ,
, is no modification or e.lteration in the system, and the replacement l switches will not impact any safety related equipment. Therefore, -
l this modification does not involve an unreviewed safety question. i I !
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! F PLANT CHANGE / MODIFICATION 85-098 i
1 PC/M CIASSIFICATION: J SR l UNIT: 4 TURNED OVER DATE: 09/11/87 f
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S/G_ LEVEL. CONTROL ALTERNATE / NORMAL CONTROL pummary ;
This modification will replace the existing 3/G Alternate / Normal l control selector switches with Westinghouse OT-2 switches with OT- l 2V contact blocks. ,
Safety Evaluatient l The Alternate / Normal selector switch pertains to control function
! only and is completely isolated from protection circuits. There >
is no modification or alteration in the system, and the replacement -
j switches will not impact any safety related equipment. Therefore, r this modification does not involve an unreviewed safety question.
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PLANT CNANGE/ MODIFICATION 84-195 l PC/M CIASSIFICATION: NSR _
4 UNIT 3 f TURNED OVER DATE 12/21/s7 l I
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- i ADDITION OF RMR TEMPERATURE ALARM [
j l pummaryI l This modificatior, will install the "Alarm Option Kit" to existing Recorder TR-3-604. The alarm option kit will provide a high and low alarm setpoint for each of the three pens on TR-3-604. ,
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Safety Evaluationt_
This change does not involve a safety related function, does not :
interface with or affect any nuclear safety related system. j
'!' Therefore, this modification does not involve an unreviewed safety r question. ,
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PLANT CRANGE/ MODIFICATION 84-196 PC/M CLASSIFICATION: NSR J UNIT: 4 TURNED OVER DATE: 12/21/s7 ADDITION OF RER TEh; '5ATURE_ ALARM t Summarya i 4
! This modification will install the "Alarm option Kit" to existing Recorder TR-4-6'J4. The alarm option kit will provide a high and
]- low alarm seth int for each of the three pens on TR-4-604.
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4 Rafety Evaluation
] This change does not involve a safety related function, does not
. interface with or affect any nuclear safety related system. ,
Therefore, this modification does not involve an unreviewed safety question.
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4 PLANT CRANGE/ MODIFICATION 88-011 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 04/04/88 NIS SOURCE RANGE DETECTOR HIGH VOLTAGE SHUTOFF CIRCUIT MODIFICATION Summary:
This modification will replace the existing electronic high voltage shutoff circuit in the Source Range Drawer with an improved relay circuit.
Safety Evaluatigni This modification does riot change the function of the Source Range
, detectors and eliminutes the probability of failures with the improved circuit. Therefore, this modification does not involve an unroviewed safety question.
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PLANT CHANGE / MODIFICATION 87-105 PC/M CLASSIFICATION: NSR UNIT: 4 TURNED OVER DATE: 12/09/87 l CRDM CONNECTOR AND CABLE REPLACEMENT Summary:
This modification replaces existing connectors and cables associated with the control Rod Drive Mechcnisms.
Safety Evaluation:
The cables and connectors are not considered safety related because the electrical power is not required to be transmitted to the CRDM in order for the control rods to perform their safety function.
Therefore, this modification does not involve an unreviewed. safety question.
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PLANT CHANGE / MODIFICATION 87-119 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 01/05/88 SOLENOID VALVE FOILRt** JSOLATION TO PUMEE SummtIX1, This modification replaces the existing ASCO model LB 83146 SV-1003A, RCDT Pump Isolation, with ASCO model HC 8314C6.
i Safety Evaluation:
The proposed ASCO HC 8314C6 is identical in quality, form, fit and function to the existing ASCO LB 83146. SV-1003A is located in non-safety, non-seismic piping. SV-1003A does not serve any safety function, and is not required for safe shutdown of the plant.
Therefore, this modification'does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 87-119 PC/M CLASSIFICATION: NSR _
UNIT: 4 , _ _
TURNED OVER DATE: 01/05/88 SOLENOID VALVE FOR RCDT ISOLATION TO PUMPS Summary:
This modification replaces the existing ASCO model LB 8314 6 SV~ '
1003A, RCDT Pump Isolation, with ASCO model HC 8314C6.
Safety Evaluation:
The proposed ASCO HC 8314C6 is identical in quality, form, fit and-function to the existing ASCO LB 83146. SV-1003A is located in non-safety, non-seismic piping. SV-1003A does not serve any safety function, and is not required for safe shutdown of the plant.
Therefore, this modification does not involve an unreviewed safety question.
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PLANT CRANGE/ MODIFICATION 87-060 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 12/21/87 PRMS MONITOR. DRAWER REPLACEMENT RMBBtrY1 This modification replaces the existing PRMS monitor drasers for channels R-11, R-12, R-14, R-15, R-17A, R-17B, R-18 and R-19.
Safety Evaluation:
The replacement drawers are equivalent in form, fit, anc function with the existirig system. Therefore, replacement of these drawers does not involve an unroviewed safety question.
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PLANT CHANGE / MODIFICATION 87-082 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 12/09/87 UPGRADE OF APRI CABLES 7214. CONNECTORS Summary:
This modification replaces the existing cablev and connectors for the APRI system with improved cables and connectors.
Safety Evaluation:
The replacement connectors and cables are equal to the existing cables and connectors in fit, form, and function. The APRI system is not considered safety related. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGB/ MODIFICATION 87-083 PC/M CLASSIFICATION: NSR UNIT: 4 TURNED OVER DATE: 12/09/87 UPGRADE OF APRI CABLES AND CONNECTORS Summary:
This modification replaces the existing cables and connectors for the APRI system with improved cables and connectors.
Safety Evaluation:
The replacement connectors and cables are equal to the existing crioles and connectors in fit, form, and function. The APRI system is not considered safety related. ,Therefore, this modification does not involve an unroviewed safety question.
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PLANT CHANGE / MODIFICATION 87-011 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 12/21/87 PRESSURIZER HEATER AC POWER CONTROL METURIMG Summary:
This modification provides a new Pressurizer Heater AC power metering instrumentation system.
Safety Evaluatious The Pressurizer Heater group wattmeter instrumentation does not perform a safety related function or effect the operation of any safety related equipment. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 86-251 l
PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 09/11/Ql_,
l l PRESSURIZER LIOUID/ STEAM SAMPLE CONTAINMENT ISOLATION SOLENOID VALVE REPLACEMENT Summary,L This modification replaces the ASCO model no. LB 831614 solenoid valves SV-956A&B with ASCO model no. NP 831654E. These solenoid valves are requred fc- operation of containment isolation valves, CV-956A&B.
HAG'tv Evaluatioitt The 19 placement ASCO is identical to the existing ASCO in fit, form, and function. Therefore, this modification does not involve an unrestewed safety question.
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PLANT CHANGE / MODIFICATION 86-239 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 04/06/88 REPLACEMENT OF REACTOR PROTECTION SYSTEM TEST SELECTOR SWITCH Summary:
Thj' modification replaces the existing two RPS selector switches, one each located in Train-A and Train-B reactor protection racks.
Safety Evaluation:
The implementation of the change does not alter the functional or operational requirements of the existing system as required for normal plant operation or plant safety. Therefore, this modification does not involve an unroviewed safety question.
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PLANT CHANGE / MODIFICATION 86-224 PC/M CLASSIFICATION: NSR UNIT: 3&4 TURNED OVER DATE: 09/11/87 PASS FLOW LINERIBER REPLACEMENT Sundary:
This modification replaces the existing PASS turbine flowmeters' '
flow linearizer "ith an upgrade model.
Safety Evaluation:
The PASS does not perform a safety function and is not required for safe shutdown of the plant. The new flow linearizer is identical in form, fit, and function ot the existing model. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 86-050 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 04/14/88_
N2 REGULATOR 8.FOR OMS Summary:
This modification replaces the pressure regulator on the N2 backup ;
system for the Power Operated Relief Valves.
Safety Evaluation The new regulator meets the original design and material specification requirements of the existing regulator. The installation of the replacement regulator does not adversely affect the integrity of the existing nitrogen back-up system. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 86-123 )
1 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 09/11/87 REPLACEMENY OF HIGH-RANGE GAMMA RADIATION READOUT MODULES Summary:
This PC/M provides for design modifications to the Containment High Range Gamma Radiation Roadout Modules rat-3-6311A and tat-3-6311B.
Safety Evaluation:
The replacement of the existing High-Range Gamma Radiation Modules will not change the design function of the system. This modification does not change the inherent function of any safety related systems. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 86-118 PC/M CLASSIFICATION: NSR UNIT: 3&4 TURNED OVER DATE: 04/14/88 FLEX HOSE REPLACEMENT CV-200A Summarvt This modification replaces existing black rubber hoses and bronze unions with flexible stainless steel braided hoses and fittings.
31(ety Evaluation:
This change does not alter the ability of the letdown isolation valves to perform their intended function, nor any other component in the area adjacent to the hose installation. Therefore, this modification does not involve an unroviewed safety question.
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PLANT CRANGE/ MODIFICATION 86-014 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 09/18/87 REACTOR CAVITY SEAL REPLACEMENT Summary:
This Engineering package provided a replacement for the Unit 3 Presray Paruma-Scal Model 585, Reactor Cavity Seal. The new seal design provides a redundant, passive, safety related means to limit reactor cavity leakage to less than 50 gpm. Furthermore, this PC/M provided a nan-safety related inflatable seal to reduce leakage flows to as low as practical. This change was committed to by FPL in their revised response to IE Bulletin 84-03.
Safety Evaluation:
The reactor cavity seal system is safety related and performs the function of maintaining reactor cavity water inventory so that the fuel can be cooled and is shielded during refueling operations.
The replacement seal system uses redundant safety related passive compression seals to eliminate the possibility of a high volume loss of refueling water from the reactor cavity. The replacement seal retains the original design concept of two passive seals and also includes the inflatable seal concept added in 1974.
Accordingly this change does not involve an unreviewed safety a
question. It does not increase the probability of an accident or the consequences of an accident.
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PLANT CHANGE / MODIFICATION 87-194 PC/M CLASSIFICATION: SR UNIT: 3 _
TURNED OVER DATE: 07/31/87 CONTAINMENT SPRAY RESTRICTING ORIFICE Summary:
This modification directs the installation of flow orifices in the discharge piping of cach CS punip.
Safety Evaluation: ,
This modification will reduce flows and determine the rise in the RWST Lo Level alarm setpoint. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 87-121 PC/M CLASSIFICATION: .
SR UNIT: 3 TURNED OVER DATE: 09/11/87 NORMAL CONTAINMENT COOLER DRIP PANS Summary:
The Unit 3 Normal Containment Cooler drip pans were replaced with duplicate drip pans made of stainless steel. The original pans were made of galvanized sheet steel and had corroded.
Safety Evaluation:
The use of stainless steel will increase the corrosion resistance of the drip pans. The new material is considered to be equal or better in strength characteristics.
This project does not involve a physical design change and will only increase the functional reliability of the drain pans.
Therefore, the proposed change does not involve an unroviewed safety question pursuant to 10 CFR 50.59.
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PLANT CHANGE / MODIFICATION 87-122 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 09/11/87 EMERGENCY CONTAINNENT COOLER DRIP PANS Summaryi The Unit 3 Emergency Containment Cooler drip pans were replaced with duplicate drip pans made of stainless steel. The original pans were made of galvanized sheet steel and had corroded.
Safety Evaluation:
The use of stainless steel will increase the corrosion resistance of the drip pans. The new material is considered to be equal or better in strength characteristics.
This project does not involve a physical design change and will only increase the functional reliability of the drain pans.
Therefore, the proposed change does not involve an unroviewed l safety question pursuant to 10 CFR 50.59. t l
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PLANT CHANGE / MODIFICATION 87-346 PC/M CLASSIFICATION: NSR UNIT: 4 TURNED OVER DATE: 12/08/87 UNIT 4 TEMPORARY SUPPORT FOR SI ACCUMULATOR LINE Rwamary:
This modification evaluates the installation of a temporary support which will enable the removal of a portion of support SR-450.
Safety Evaluation:
The temporary support will provide the equivalent function of the existing support during Mode 5, therefore having no effect on the existing stress analysis of record. The support will be removed prior to leaving Mode 5. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 87-353 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 03/07/88 RER PUMP RECIRC. INSTALLATION i summary: ;
During the select safety system review for RHR, it was discovered l that the existing mini-recirc design configuration was inadequate.
This modification installs the new design configuration to meet 1 minimum recirculation requirements.
Safety Evaluations ,
1 This change is classified as Nuclear Safety Related. The safety evaluation concludes an unreviewed safety question does not result from this change.
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PLANT CHANGE / MODIFICATION 87-384 PC/M CLASSIFICATION: SR UNIT: 4 TURNED OVER DATE: 04/28/88 CONTAINMENT AIR SAMPLE SYSTEM MODIFICATION Summary: '
This Engineering Package provides a backup means of sampling the containment atmosphere. The modification includes the addition of a seismically mounted, non-safety related pump, two safety related valves and various non-safety related fittings and tubing.
Safety Evaluationt_
The pump will be seismically mounted to preclude potential interaction with safety related equipment. This modification will not effect the normal operation of the existing sampling system.
The additional required flow has been evaluated as having no impact on RD-4-11 and. RD-4-12. The safety evaluation concludes that no unreviewed safety concerns exist as a result of this modification.
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PLANT CHANGE / MODIFICATION 87-171 PC/M CLASSIFICATION: OR UNIT: 3&4 TURNED OVER DATE: 07/28/87 REACTOR VE8SEL HEAD INSULATION PERMANENT REPLACEMENT Summ4Xy_l, The existing insulation around CRDM penetrations G-7 and G-9 was damaged and in poor condition due to its age. This insulation was replaced to obtain access to the reactor head and to increase its I thermal performance. The insulation is in two perpendicular layers between the rows of CRDM's with cutouts for the CRDM's.
Safety Evaluation:
The replacement of the insulation is Quality Related and does not involve an unreviewed safety question pursuant to 10 CFR 50.59.
The new insulation meets the requirements of FP&L Specification MN-2.72 "Rx Vessel Head Permanent Insulation" which provides requirements such that the replacement insulation is equivalent or better as compared to the original insulation.
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PLANT CHANGE / MODIFICATION 87-223 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 09/04/87 REACTOR HEAD VENT PIPE SUPPORT H-2 MODIFICATION summary:
The Reactor !!ead Vent System piping support H-2 was replaced to better distribute its resultant load over the reactor cavity liner plate embedded attachment and in the support itself. The new support is in the same location and is identical to the original support except for additional reinforcement.
Safety Evaluwtion: ;
This modificacion is Nuclear Safety Related and does not involve an unreviewed safety question. The new support is better able to perform its intended function than the original support, therefore the margin of safety as defined in the basis of any Technical Specification will not be reduced, the possibility of an accident or malfunction of a different type and the probability of :
occurrence or the consequences of an accident or malfunction of equipment important to safety will not be increased.
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PLANT CHANGE / MODIFICATION 87-164 PC/M CLASSIFICATION: SR UNIT: 3&4 TURNED OVER DATE: 09/11/87 GREASE KIT REPLACEMENT - EMERGENCY CONTAINMENT COOLERS AND FILTERS Summary:
The modification replaced the original grease fittings and lines that were removed due to deterioration. The replacement parts were obtained from the original manufacturer and installed per their instructions. The grease fittings and lines are used to lubricate the E.C. Coolers and Filter Fan Units.
AAlety Evaluation:
The replacement of the grease fittings and lines were procured and installed por the original manufacturer instructions, thus returning the E.C. Coolers and Filter Fan Units to a configuration similar to the original equipment. The installation of these parts is classified as Nuclear Safety Related and does not involve an unreviewed safety question pursuant to 10 CFR 50.59 since the replacement is equal to or better than the original installation.
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PLANT CHANGE / MODIFICATION 86-045 PC/M CLASSIFICATION: NNSR-OA/OC UNIT: 3&4 TURNED OVER DATE: 07/30/87 AUXILIARY FEEDWATER TURBINE EXHAUST SILENCER CONDENSATE P.2MOVAL Summary:
The modifications consist of locking the existing manual isr,lation <
valves in the open position, enlarging the discharge piping downstream of the existing steam orifices, and connecting the discharges to a nev 1\ inch drain header. These modifications are required to ensure adequate condensate removal from the turbine exhaust lines to preclude the discharge of hot condensate from the silencers upon AFW pump actuation. The modifications direct the turbine exhaust piping drain discharge to a storm drain in the Unit 3 Steam Generator Blowdown Area. "
Safety Evaluation:
E The possibility of an accident occurring due to this modification :
will not be increased because this modification does not alter the basic function of the AFW system or other safety related systems.
This modification does not involve an unroviewed safety question l as directed by 10 CFR 50.59. >
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PLANT CHANGE / MODIFICATION 85-172 PC/M CLASSIFICATION: NSR UNIT: 3&4 TURNED OVER DATE: 08/13/87 AUXILIARY FEEDWATER PUMP AREA STEAM TRAP AND DRAINAGE PIPING 6ummary:
This modification provides for the connection of selected steam trap outlets of the Auxiliary Feedwater (AFW) System to a new 6 inch discharge header and storm drain.
The modifications for connecting selected steam trap and turbine caring drains discharge piping to a new 6 inch drain header was required to prevent the condensato released by these lines from flashing into steam in an area which may be occupied by operation and maintenance personnel.
Safety Evaluation:
The modifications to the discharge piping of the steam traps and turbine casing drains do not alter the basic function of the AFW System or other safety related systems. This modification does not involve an unroviewed safety question as directed by 10 CFR 50.59.
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FLANT CHANGE / MODIFICATION 85-104 PC/M CLASSIFICATION: NSR UNIT: 3&4 TURNED OVER DATE: ___ 02/05/88 ,
i AUXILIARY FEEDWATER PUMP A REPLACEMENT IMPELLER JPE-N-86-046 l Summaryt ;
This PC/M replaced the Auxiliary Feedwater pump "A" impeller i l assembly (rotating element) with a spara assembly recently removed r from Plant Stores. The assembly' removed from Stores was returned to Ingersoll-Rand, Phillipsburg, New Jersey facility to have the ,
impeller vanes underfiled. This would achieve a minimum of 4 to
! 5 percent head increase in pump performence.
> i Safety Evaluation This modification did not increase the probability of occurrence or the consequences of a design basis accident or malfunction as 1 evaluated in the FSAR; did not introduce the possibility of an '
accident or malfunction not previously analyzed for; and did not reduce the margin of safety as defined in the Technical Specifications. A performance test was performed upon completion '
of this PC/M which verified the minimum 4 to 5% increase in pump head was met. The amount of metal removed during underfiling was l negligible; hence the seismic characteristics were not changed.
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PLANT CHANGE / MODIFICATION 86-011 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 03/21/88 AUXILIARY FEEDWATER STEAM SUPPLY VALVE REPLACEMENT l Summary
' i This PC/M replaces the existing motor operated solid wedge gauge l valves of the Auxiliary Foodwater Steam Supply System with motor operated globe valves. This PC/M also installs tilting disc check valves both upstream and downstream of the motor operated globe '
valves, removes the existing downstream stop check valves, and i converts the existing upstream stop check valves into manually operated globe valves. T i
I l Safety Evaluationj, l The 900# Class Globe Valvos are suitable replacements for the 600#
Class Gate Valvos and are considered superior in precluding seat erosion and thermal binding. Opening and closing times have been reviewed and verified to be within design limits.
All valves are seismically qualified and have boon manufactured to -
ASME Section III, Class 2, which moots the requirements of ANSI B31.1 and Quality Group B. The existing upstream stop check valves are to be modified to globo valvos according to manufacturer's !
recommendations. The modified valvo is suitable for steam service por the valvo manufacturor. Dolotion of the downstream stop function on tho downstream chock valva has no adverse effect on i
l l plant safety. The replacement tilting disc chock valve is suitab.1e 1
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for steam servico. '
l Pressure drop calculations havo boon performed to verify that J adequate steam conditions (flow /prosauro) will exist at the AFW i
, turbinos to provide the required foodwater flows to the steam generators.
This modification doos not present an unroviewod safety question i; na required by 10 CFR 50.59.
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PLANT CHANGE / MODIFICATION 86-009 PC/M CLASSIFICATION: NSR UNIT: __,3 TURNED OVER DATE: 08/05/87 AUIILIARY FEEDWATER STEAM SUPPLY VALVE REPLACEMENT i
4 I summary:
This PC/M replaces the existing motor operated solid wedge gauge i'
valves of tra Auxiliary Feedwater Steam Supply with motor operated glove valve,. This PC/M also installs tilting disc check valvos both upstrets and downstream of the motor operated glove valves, rcmoves the existing downstream stop check valves, and converts the existing upstream stop check valves into manually operated globe valves.
31fety Evaluation The 900f Class Globe Valves are suitable replacements for the 6004 Class Gate Valves and are considered superior 1.. precluding seat a erosion and thermal binding. Opening and closing times have been reviewed and verified to be within design limits.
{ All valves are seismically qualified and have been manufactured to ASME Section III, Class 2, which meets the requirements of ANSI '
4 B31.1 and Quality Group B. The existing upstream stop check valves are to be modified to globe valves according to manufacturer's recommendations. The modified valve is suitable for steam service i
per the valve manufacturer. Deletion of the downstream stop function on the downatream chock valve has no adverse effect on plant safety. The replacement tilting disc check valve is suitable i for steam service. I Prossure drop calculations have been performed to verify that ,
adequate steam conditions (flow / pressure) will exist at the AFW turbines to provido the requis Sd feedwater flows to the steam generators.
, This modification does not ;recent an unreviewed safety question i
as required by 10 CFR 50.59. ,
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PLANT CHANGE / MODIFICATION 84-089 pC/M CLASSIFICATION: NS UNIT: 3&4 TURNED OVER DATE: 05/03/85 CONTAINMENT PURGE VALVE POLTs ,
summary:
This modification replaced the existing operator and trunion bolts, including respective nuts, on the 54" containment purge valves POV-3-2602, POV-3-2603, POV-4-2602 and POV-4-2603. The replacement bolts were of SAE Grade 8 carbon steel and the replacement nuts were heavy hex os ASTM A194 Grade 2H carbon steel. The original i bolts and nuts were SAE Grade 2 carbon steel. l safety Evaluationt This design package is nuclear safety related because containment purge valves function to perform / maintain containment isolation. !
Stress reports show that the new components are better than the ,
originals and appropriate for substitution. Tnerefore, the use of ;
the new bolts and nuts is acceptable and does not constitute an i unreviewed safety question. !
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PLANT CHANGE / MODIFICATION 84-ifL PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 08/13/87 REPLACEMENT OF Vi.fVE 9 3-G96T FOR OTMT SPRAY RECIRCULATION TEST LINE puamaryt The purpose of this PC/M is to replace the existing recirculation test line isolation valve with a valve that will not cavitate under l pump test recirculation conditions. The replacement valve is an :
ASME Section III, Class 2, 2" globe valve.
Safety Evaluationt
, The replacement valve is larger than the original valve and the piping stress analysis has been reviewed and revfsed to verify the existing supports are adequate. The replacement valves are r identical in fit, form and function to the existing valves and therefore, this modification is nucinar safety related with no unreviewed safety question since the probability / consequences of an accident previously evaluated in the FSAR has not increase nor was the possibility of an equipment malfunction / accident important to safety previously evaluated in thq FaAR. This modification will not decrease the margin of safety as defined in the bases of any Technical Specification, i
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I PLANT CHANGE / MODIFICATION 85-072 1 PC/M CLASSIFICATION: NNS-OA/OC UNIT 4 TURNED OVER DATE: 12/16/87 SPENT FUEL PIT BUILDING WALL JOINT REPAIR summary:
, This design package covers the repair of the expansion / contraction joint in the walls of the Spent Fuel Pit Building (SFPB) .
l Safety Evaluation The purpose of the joint materici is to prevent joint deter:, oration, protect reinforcing and stop foreign material from entering the joint. It doesn't perform a safety related function.
Therefore, walls do not pose an unreviewed safety question pursuant to 10 CFR 50.59.
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PLANT CHANGE / MODIFICATION 85-129 PC/M CLASSIFICATION: NSR UNIT: 4 TURNED OVER DATE: 12/16/87 CONTAINMENT TEMPERATURE RECORDER REPLACEMENT Sundary:
This modification replaces the existing Main Control Room containment temperature recorder with an upgraded model.
Safety Evaluation The temperature recorder is required to provide data for plant performance records only, it will be seismically supported to avoid interaction with safety related equipment. The recorder's function does not affect the operation of any safety related components.
Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE /MODIFICFTION 86-115 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 09/14/87, f
NIS.50URCI. RANGE PRE-AMPLIFIER REPLACEMENT l
summary This modification installs a new excore neutron flux monitoring system in order to meet the requirements of Reg. Guido 1.97 Revision 3.
Rafety Evallationt ,
4 The new low noise preanplifier is electronically compatible with the existing source range drawer electronics. Installation dimensions and seismic responses are essentially unchanged. The temperature, pressure, and humidity capability of the new amplifier bounds its expected operating environment. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 86-168-PC/M CLAE.5IFICATION: SR UNIT: 3 TURNED OVER DATE: 01/14/88 MOV-3-750 AND MOV-3-751 LIMIT SWITCH ADJUSTMENT
- summary
This modification will relocate the close limit switch LS-8 wiring from Rotor f2 to a spare limit switch LS-15 on Rotor 64 on RHR Inlot Isclation Valves MOV-3-750 and MOV-3-751.
sai'ety Evaluation:
This modification will eliminate the misadjustment of the open bypass or closed limit switch setting, which could result in 1
failure of the disk to properly seat. The relocation of the limit
! switch will improve the reliability of the isolation valves. This
, does not affect the integrity operation or function of any safety i
related systems. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 87-349 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 12/08/87 1
a RESOLUTION OF DEFICIENCIES ASSOCIATED WITE PRESSURIBER INSTRUMENTATION Summary:
This modification identifies the material replacement and addition of conduit suppor?,s to maintain capability of RTD's and acceleromoters for the pressurizer.
9 Safety Evaluation:
1 Raceway supports naya been designed in accordance with Class I 1
requirements. The replacement cable is qualified for Class 1E application. The'ce fore , this modification does not involve an unreviewed safety question.
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PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 09/11/87 CCW HEAT EXCHANGER CNANNEL MEAD REPLACEMENT Summaryn This modification replaces the existing channel heads with other
, heads less susceptible to corrosion, safety Evaluation:
The only change being made per this modification is to provide channel heads of less corrosive material. Therefore, this
! modification does not involve an unreviewed safety question. j l i
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PLANT CRANGE/NODIFICATION 86-183_
PC/M CLASSIFICATION OR UNIT: 3&4 TURNED OVER DATE 09/04/87 ACCESS _FOR.EDG RADIATOR DRAIN VALVES summary:
This modification installs two access panels in the EDG Radiator cooling System to allow operation and maintenance to drain valves 392A&B and 293A&B.
Safety Evaluation:
The safety evaluation concludes that this modification does not constitute an unreviewed safety question and does not require any changes to Technical Specifications.
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PLANT CHANGE / MODIFICATION 86-210 PC/M CLASSIFICATION: NSR UNIT 3 TURNED OVER DATE: 01/29/88 ICW CEECE VALVE REPLACEMENT l summary,1, This modification replaces the existing check valves with a new i folding disc type check valve.
1 Bafety Evaluations i The replacement valve is a one-for one replacement and the function 3 of the system is unchanged. Theret' ore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 87-022 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 09/24/87 RfDRAULIC SNUBBER REPLACEMENT KAIN STUAM SYSTEM summary:
This modification replaces hydraulic snubbers on the Main Steam system, with mechanical snubbers, safety Evaluation:
The replacement snubbers are equal to or better than the existing snubbers and will not affect nuclear safety. This modification is considered a one-for-one replacement and does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 87-098 PC/M CLASSIFICATION: SR UNIT: 4 TURNED OVER DATE: 06/26/87 INSTALLATION OF VNPERVOLTAGE TRIP DEVICE FOR POLAR CRANE BREAKER Summary 1 i
This modification covers breaker accessory addition to the 480V
! Load Center Power Circuit Breaker serving the Unit 4 Containment Polar Crane. <
3afety Evaluation:
The failure of this component will not adversely affect any safety system or function. The U/V device is seismically qualified, it 1 is being incorporated into an existing safety related circuit and l
the added tripping function upon an undervoltage condition isolates .
non-vital load. Therefore, this modification does not involve an unreviewed safety question. ;
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PLANT CHANGE / MODIFICATION 87-088 PC/M CLASSIFICATICN: NSR UNIT: 3 TURNED OVER DATE: 05/12/88 i
ASICROFT TEMPERATURE INDIQATOR REPLACEMENT summary:
l The existing Ashcroft model no. 506060EHT56 is obsolete, this modification will replace the affected indicators with Ashcroft Model 50-EI42E060.
d
$ safety Evaluationt t
The subject indicators are not part e t safety related boundary,
, serve no safety function, and are not w ed in conjunction with any ;
j other safety related device or system. The replacement indicators are equal to the original indicators in quality, form, fit and function. Therefore, this modification does not involve an l unreviewed safety question. l t
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PLANT CHANGE / MODIFICATION 86-101_
PC/M CLASSIFICATION: NSR UNIT: 3&4 TURNED OVER DATE: 08/04/87 i
EMERGENCY DIESEL HRH AUXILIARY POWER SUPPLY RELOCATION i
! summary:
This modification relocates certain auxiliary of EDG-B from EDG-A associated MCC 4 A to EDG-B associated MCC-4B. '
Safety Evaluation:
This modification will eliminate the possibility of losing EDG-B at a time when it is the only emergency power source available, l hence increasing the reliability of the Emergency Diesel Generator
! System. Therefore, this nodification does not involve an j unreviewed safety question.
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PLANT CHANGE / MODIFICATION 85-175 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 09/11/87 i
NITROGEN STATION ADDITIONS AND RELOCATION Summary:
i This modification relocates an existing backup Nitrogen bottle :
! station for AFW control valve and adds a new bottle station and
- associated tubing and instruments. j t
Safety Evaluations '
?
t This ensures a more reliable source of backup supply and separation of two independent trains of supply of AFW to the Steam Generators.
Therefore, this modification does not involve an unreviewed safety ;
question.
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i PLANT CHANGE / MODIFICATION 83-152 PC/M CLASSIFICATION: SR UNIT: 4 TURNED OVER DATE: 09/03/87 CABLE REROUTING FOR APPENDIX R MODIFICATION 5 .
I Summary:
i This modification provides physical protection between channels for those devices required to ensure hot and/or cold shutdown i
capability.
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Safety Evaluationt t
, This change improves plant safety by providing separation between channels. All new or relocated equipment is seismically supported I and qualified and will not degrade the safety function of other l systems. Therefore, this modification does not involve an ,
unreviewed safety question. '
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l PLANT CMANGE/NODIFICATION 81-162 PC/M CLASSIFICATION: SR ,
UNIT: 3 TURNED OVER DATE: 02/09/88 INSTALLATION OF INADEQUATE CORE COOLING SYSTEM INSTRUMENTATION summary:
) This modification installs silicon dioxide mineral insulated cable to bring the core exit thermocouple signals and heated unction thermocouple signals from the reactor to the coniainment penetrations.
safety Evaluation 1 c The installation of mineral insulated cable does not involve an
- unreviewed safety question because the addition does not affect the pressure boundary or any other safety system. ,
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PLANT CHANGE / MODIFICATION 87-127 PC/M CLASSIFICATION: NSR UNIT: 3 ,
TURNED OVER DATE: 02/12/88 ACCUMULATOR SI TEST LINE SOLENOID VALVE 8 REPLACEMENT l SummaryI
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- This modification replaces existing ASCO model LB831654 for SV-850A,C,&E with ASCO model NP831654E.
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I Safety Evaluationt !
l This modification replaces existing solenoid valves with solenoid valves that are equal to or better in fit, form, and function.
Therefore, this modification does not involve an unreviewed safety i question.
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1 PLANT CKANGE/NODIFICATION 86-122 PC/d CLASSIFICATION: SR UNIT: 0 TURNED OVER DATE: 04/14/88 LOW AIK P.S. TO START AIR GAUGE ON PANEL
- summary
1 The modification replaces the 12" X \" rubber hose for the low air i pressure switch with \" -
.030 wall thickness copper tubing approximately 12" long.
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} Safety Evaluat(2B1 1 '
The replacement tubing is acceptable for all anticipated operating i conditions, therefore, this modification does not involve an !
unreviewed safety question. !
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PLANT CHANGE / MODIFICATION 86-141-_
PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 08/04/87 TRAT CONMTCTIONS FQR SECONDARY _ PUMPS Summary:
This modification is to provide evaluation and documentation for existing pressure test connections for the Feedwater, Condensate, and Heat Drain Pump performance testing.
Safety Evaluatient i This modification is non-safety related where the test connections j for pump performance testing are required, and do not perform any safety function. Therefore, this modification does not involve an i I
unreviewed safety question. i
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PLANT CHANGE / MODIFICATION 88-172 PC/M CLASSIFICATION: SR UNIT: 4 TURNED OVER DATE: 09/11/87 i
MIG ROTARY SWITCM KNOBS
! Summary This modification replaces the existing NIS and PRMS rotary a selector switches with a point or shape knob to alleviate human
- factors concerns.
Safety Evaluationi i Replacing the existing NIS, PPRS , rotary switch knobs with the new knobs will not degrade either system. Therefore, this modification does not involve an unreviewed safety question. <
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PLANT CHANGE / MODIFICATION 87-207 ,
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PC/M CLASSIF.! CATION: SR UNIT: 3 TURNED OVER DATE: 09/11 E t
ICW_CEECK YALVES FILTER REGULATOR OUTPUT RANGE APRING REPL7. CEMENT summarya
}
i This modification will replace the existing control springs with
! ones suitable for the regulator.
Safety Evaluation 1 i
The replacement regulator is equal to or better than the existing ,
i quality, fottm, fit and function. This does not change the '
operating function or condition of the plant. Therefore, this modification does not involve an unreviewed safety question.
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l PLANT CHANGE / MODIFICATION 87-2 4L l l i
. PC/M CLASSIFICATION! SR UNIT! 3 TURNED OVER DATE 09/11/87 ,
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C?-3-2826 REPLACEMENT OF STEM CONNECTOR summary This modification installs a stem connector made of INeut 200, for a replacement of the existing stem connector made of ASTM A-316.
i safety Evaluationt ;
The replacement part will perform the same function as the existing with equivalent or better quality and will not compromise system integrity. Therefore, this modification does not involve an '
unreviewed safety question.
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PLANT CHANGE /NODIFICATION 87-298-- ,
PC/M CLASSIFICATION: SR UNIT 3 TURNED OVER DATE: 12/22/s7 l MODIFICATION OF CCW PIPING AND SUPPORT FOR 3B RCP OIL CCOLER
) MM This modification will make minor pipe routing and support changes
! to component Cooling Water piping for the 3B Reactor Coolant Pump
- lower bearing lube oil cooler.
safety Evaluationt j This modification is only minor rerouting of safety related piping ;
and associated supports. Therefore, this n *ification does not l involve an unreviewed safety question. '
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l PLANT CNANGE/NODIFICATION 87-331 :
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,1 i' PC/M CLASSIFICATION: NSR UNIT 3&4 l l TURNED OVER DATE: 11/24/s7 '
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EXAT. TRACE PANELS 11. 13, 9A AND 9B.REWORE Summarya f
This modification identifies the material replacements and mounting i requirements to assure seismic capability of heat trace power l panels 1A, 1B, 9A and 98. :
j safety Evaluations i
.a ;
This modification replaces two electrical type devices with '
equivalent rated material having appropriate documentation, and i
will assure the seismic qualifications of the installations.
Therefore, this modification does not involve an unreviewed safety .
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PLANT CHANGE / MODIFICATION 87-335 PC/M CLASSIFICATION: SR I UNIT 3 TURNED OVER DATE: 11/02/87 L
MODIFICATION OF PIPI SUPPORT BR-36 AND WMIP RESTRAINT Summary:
This change modifies the support location and method of attachment for Support SR-36 and support configuration for Restraint SI-13.
(
- Safety Evaluationt L i
This modification enhances the existing support system and ,
therefore, does not involve an unreviewed safety question. :
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PLANT CRANGE/ MODIFICATION 87-407 PC/M CLASSIFICATION: SR UNIT 3&4 TURNED OVER DATE: 01/25/88 RESUPPORT OF THERMOSTATS FOR BOR'.!C ACID SYSTEM MEAT TRACIMG CIRCUITS (h & GB Summary This modification is requ.\ red to provide appropriate documentation and assurancs that the cupport for the thermostats meets the requirements for Class I str'tetures.
Safety Evaluations This modification is an enhancement to the existing system. This has no in; pact on the functioning of the system. Therefore, this modificat;,on does not involve an unrevj wed safety question.
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PLANT CHA!!GE/MODIF;iCATION 88-018 FC/M CLASS.TFICATION: SR UNIT: 0 TURNED OVER DATE: 04/24/88 VALTEK POSITION FOR FOLLOWER PIN INSTALLATION Summary:
This modification installs 80 and 80R positioner follower pins on the Auxiliary Feedwater control valves, and other similar installations.
Safety Evaluationt This modification is to provide details that will assure the proper installation of the follower pin assemb1les in accordar e with vendor requirements. Therefore, this modification does not involve an unroviewed safety question. ,
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PLANT CHANGE / MODIFICATION 86-105 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 01/05/88 UNIT 3 ICW PUMP DISCHARGE CH3CK VA(.,VE REPLACEMENT Sumaary:
This modification is for replacement of valves 3-50-311, 3-50-321, 3-50-331, TEC check valves. The replacement valves have been redesigned to incorporate a new seal arrangement and a square keyway for the shaft diak key, safety Evaluation This modification will not alter the function of the system, its seismic response, or compromise system integrity. Therefore, this modification does not invol"1 an unraviewed safety question.
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PLANT CHANGE / MODIFICATION 86-106 PC/M CLASSIFICATION: SR UNIT: 4 TURNED OVER DATE: 01/05/08 UNIT 4 ICW PUMP DISCHARGE CHECK VALVE REPLACEMENT SummaryL This modification is for replacement of valves 4-50-311, 4-50-321, 4-50-331, TEC check valves. The replacement valves have been redesigned to incorporate a new seal arrangement and a square keyway for the shaft disk key.
Safety Evaluation:
This modification will not alter the function of the system, its seismic response, or compromise system integrity. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 87-070-PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 10/16/87 FEEDWATER SOLENOID VALVE REPLACEMENT Summary:
This modification replaces the existing ASCO solenoid valves for SV-478A,C, 498A and C with an upgraded ASCO model solenoid valve.
Safety Evaluation This modification is a one-for-one replacement with an upgraded solenoid valve. Therefore, this modification does not involve an uriceviewed safety question.
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PLANT CHANGE / MODIFICATION 87-071 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 10/16/87 FEEDWATER SOLENOID VALVE REPLACEMENT Summary:
This modification replaces the existing ASCO solenoid valves for SV-478B, 488B, and 498B with an upgraded ASCO model solenoid valve.
Safety Evaluation:
This modification is a one-for-one replacement with an upgraded solenoid valve. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 88-044 PC/M CLAStiIFICATION: SR UNIT: 3 TURNED OVER DATE: 04/04/88 AUXILIARY FEEDWATER N2 BACKUP SYSTEM PRESSURE INDICATOR. REPLACEMENT Summary:
This modification provides for the replacement of the existing indicators with seismically qualified indicators and will permit the isolation valve for each indicator to remain in the "normal open" position Safety Evaluation:
This modification replaces the existing pressure indicators seismically qualified indicators which meet the same functional requirements as the original indicators. This has no adverse effect on safety related components.
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l PLANT CHANGE / MODIFICATION _.88-045_ j PC/M CLASSIFICATION: SR UNIT: 4 TURNED OVER DATE: 04/14/88-AUZILIARY FEEDWATER N2 BACKUP SYSTEM PRESSURE INDICATOR REPLACEMENT Summary:
This modification provides for the replacement of the existing indicators with seismically qualified indicators and will permit the isolation valve for each indicator to remain in the "normal open" position Safety Evaluation:
This modification replaces the existing pressure indicators seismically qualified indicators which meet the same functional requirements as the original indicators. This has no adverse effect on safety related components.
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PLANT CHANGE / MODIFICATION 88-050 PC/M CLASSIFICATION: SR UNIT: 3&4 TURNED OVER DATE: 04/14/88 BATTERY CHARGER 3B, 4A & 48 GATE-FILTER MODULE REPLACEMENT Summary:
This change in selection of a capacitor to install in the original charger has resulted in a revision level "K" to the old part no.
101-071-629 for gate-filter modules and is noted in the Exide letter dated 02/08/88.
Safety Evaluation:
This modification is an improvement to the existing battery chargers. It has no adverse effect on safety related systems and therefore, does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 85-174 PC/M CLASSIFICATION: NSR UNIT: 3&4 TURNED OVER DATE: 09/11/87 AUXILIARY FEEDWATER PERFORMANCE UPGRADil..
REMOVAL OF ABANDONED EQUIPMENT _
Summary This modification provides for the removal of components and equipment that have been abandoned and are no longer required for plant operation.
Safety Evaluation:
This modification does not degrade the plant safety, the changes are not safety related. Therefore, this modification does not involve an unroviewed safety question.
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PLANT CHANGE / MODIFICATION 86-069 PC/M CLASSIFICATION: NSR UNIT: 3&4 TURNED OVER DATE: 09/11/87 CONTROL ROOM HVAC TEST PENETRATIONS 4
Sunnary:
This modification drills 12 holes, each 3/8" diameter on the return duct for the Control Room HVAC air handlers. These holes will be used to gather flow data.
Safety EvaluatigA1, The resultant short circuiting will not change the seismic, fire protection, environmental characteristics of the HVAC duct.
Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 87-042 PC/M CLASSIFICATION: SR UNIT: 3&4 TURNED OVER DATE: 09/11/87 8GBD FLOW CONTROL VALVE Summary: >
This modification replaces the Chrome-Moly valve bodies on the Unit 3 SGBD FCV's with stainless steel bodies. Also, diffuser type seat rings will be installed in the Unit 3 and Unit 4 FCV's to replace the existing seat rings.
Safety Evaluation:
The S.S. replacement bodies are a direct replacement for the Chrome-Moly valve bodies. The diffuser seat ring is also a direct
- replacement for the existing seat ring. Therefore, this modification does not involve an unreviewed safety question.
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l PLANT CHANGE / MODIFICATION 87-123 PC/M CLASSIFICATION: SR :
UNIT: 3&4 TURNED OVER DATE: 09/18/87 PORTABLE VENTILATING FANS FOR THE DC EOUIPMENT/ INVERTOR ROOM 8 Summarvt This modification installs the following: 1) Portable ventilation fans for storage locations, 2) Power receptacles in DC Equipment /
Invertor rooms, 3) Dial thermometers in DC Equipment / Invertor rooms and 4) Emergency Lighting in the DC Equipment / Invertor rooms.
Safety Evaluation:
This modification is to assure adequate ventilating capability for the DC Equipment / Invertor rooms. The electrical supp:,y is Class 1E, the fan storage racks are seismically qualified, and the thermometers and lights do not perform a safety function.
Therefore, this modification does not involve an unreviewed safety question.
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i PLANT CHANGE / MODIFICATION 87-178 l
PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 07/28/87 UNIT 3 REACTOR VESSEL CRDM DUMMY, HOUSING G-7 CAP Summary:
This modification installs a dummy can over the vertical pipe at location G-7 to maintain proper air flow around the CRDM.
Safety Evaluation Analysis has shown that securing the dummy can to an adjacent housing will not change the conclusion that the stresses within the CRDM pressure housing or the reactor vessel penetration are within 1 acceptable limits. Therefore, this modification does not involve an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 87-181 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 07/28/88 CRDM VENT SHROUD INSPECTION DOORS Summary:
This modification will install doors in the CRDM Shroud to allow inspection of RV head and CRDM penetration.
Safety Evaluation Per the evaluation of seismic concerns, dynamic loading and operating variances, this modification does not involve an unreviewed safety question, l
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PLANT CHANGE / MODIFICATION 82-060 PC/M CLASSIFICATION: NSR UNIT: 3&4 TURNED OVER DATE: 02/12/88 COMPUTER _ ROOM ADDITION Summary:
This modification provides instruction to spare six breakers that were used to feed original plant air conditioners for the hot and cold locker room. The hot and cold locker _ rooms are to be converted into a Computer Room and this modification adds a permanent air conditioning system.
Safety Evaluation This modification replaces the original air conditioners for the hot and cold locker rooms which are to be converted into a Computer Room. This PC/M does not involve an unreviewed safety question, and does not affect the conclusion of the original Safety Evaluation.
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PLANT CHANGE / MODIFICATION 87-235 PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 10/12/87 ,
MAIN FEEDWATER VALVE TUBING REPLACEMENT Summary:
This modifiertion invo.1"es the replacing of the existing 3/8" OD tubing with 1/2" OD stainless tubing. The results will be a decrease in the maximum closing time as controlled by SV-478A, 488A, and 498A.
3.afety Evaluation:
This modification replaces existing instrument air tubing with a larger diameter as to decrease maximum closing times of the above S.V. Therefore this modification adds no adverse effects or constitutes an unreviewed safety question.
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l PLANT CKANGE/ MODIFICATION 85-117 PC/M CLASSIFICATION: SR UNIT: 3&4 TURNED OVER DATE: 09/03/87 ADDITIONAL CABLE REROUTING FOR APPENDIX R Bummarvt This modification provides for the rerouting of cables as required by Appendix R. This involves addressing: physical separation, environmental service conditions and seismic criteria.
Safety Evaluation:
This modification consists of only pulling and routing of new cables to meet fire protection requirements, and does not represent a change in the way the systems are operated or function. This modification does not adversely affect safety related equipment or systems, require any change to plant Technical Specifications, or constitute an unreviewed safety question.
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PLANT CHANGE / MODIFICATION 86-171 PC/M CLASSIFICATION: NSR UNIT: 3 TURNED OVER DATE: 09/14/87 NIS ROTARY SWITCH KNOB.. REPLACEMENT Summarvt This modification provides for the replacement of the round knobs on the existing Westinghouse NI and PRMS racks 59, 60, 61, 62, 66, and 67 with similar but pointed knobs to alleviate human factors Concern.
dafety Evaluation:
The knobs are both made of plastic with nearly identical weight and size. The mounting of the new knobs is identical to the old round knobs. The new knobs add no adverse effect on the system or constitute an unreviewed safety question.
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l PLANT CHANGE / MODIFICATION 87-045 PC/M CLASSIFICATION: NSR UNIT: 4 TURNED OVER DATE: 09/11/87 PRMS CHANNELS R4-17A AND R4-17B CABLE REWORK Sumaary This modification provides instructions to add a splice at an existing pull box, PB4314, in the cabling for detectors R4-17A and R4-17B. This repair has become necessary due to R4-17A cable failure and R4-17B being highly prone to failure.
Safety Evaluation:
F The only modification to the PRMS is the addition of the splice on !
the detector cable in the existing pull box, the operational and
, physical characteristics of the system remain the same. Therefore, this modification does not require a change to the plant Technical Specifications, or constitute an unroviewed safety question.
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! PC/M CLASSIFICATION: SR UNIT: 3 TURNED OVER DATE: 07/28/87
This modification provides for design changes involving the reactor vessel head, penetrations at locations G-7 and G-8. The existing head adapter plug is to be cut off and replaced with a welded pipe cap design. In addition, this modification also provides for the addition of dummy cans over locations G-7 and G-8 to maintain proper air flow.
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Safety Evaluation:
This modification does not constitute an unreviewed safety question as defined in 10 CFR 50.59.
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- 11) PROGIHtB QENGES & SAFEW EVAIIRFIGE !
The following procedures were changed, reviewed, and a; proved and reissued during the reporting period. The prMwe changes are as described below and only those procedure changes constituting changes in the procedures as described in the Final Safety Analysis Report (FSAR) are reported. Minor or routine procedure changes not affecting procedures as described in the FEAR are not reportal. In addition other safety evaluations that did not result in procedure changes are included in this section.
- 1) The setpoint for the COf punp auto start was changed frun 75 i 1.5 psi to 60.0 i 1.5 psi to prevent rn M nce auto starts. The following procedure was revised:
AP 0140.2 - Charging Setpoints Safety Evaluation Sumary:
Due to changes in the available Cof heat sink taperatures and system flow balancirq requiranents, Cof flow rata and pressure have changed frun '
two pu::p to one punp operation. The new setpoint still assures the mininn required flow rates to essential cwv;rdsits needed to mitigate the consequences of an accident. The probability of malfunction of equipnent will tot be incz=w since no equipaant will be nailfied.
Special test 86-05 deconstrated that single Cof pmp operation just below the proposed setpoint value of 60 psig provides adequate Caf to essential coriponents. No margin of safety as defined in the basis for any Technical Specification is decreased.
Date of Change: January 6, 1988
- 2) 7b irprove backflush, a new method was reviewed. This methcd incrm W backflush flow by closing the inlet valve arri cpening the strainer drain valve. This reched still requires enterirg an ICO but for a noch shorter duration than original backflush method or mamal cleanirg. The following precature was changed to reflect the new backflush method:
TP - 430 ICH/COf Basket Strainer Fullflow Backwash Safety Evaluation Sumary:
The prcbability of occurrence or the acosequences of an accident or malfunctico of equipnent important to safety previously evaluated in the safety analysis will not be increased. This is assured by stationirn an 1
cperator in the vicinity of the strainer drain valve. Full ICW flow will be restored in such a short time frama that an accident or malfunction of a different type than any evaluated previously in the safety e.nalysis will not be created. The aquinments placed on the procedure will ensure that the safety margin as defined in the basis for any 1bchnical Specif1:ation is not rtduced.
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In conclusion, there is no unreviewed safety questions.
Date of Change: Martti 17, 1988
- 3) The review of the nonthly maintenance records cn station battery "4B" indicated that over the period of several months, the float voltages of a few cells have drifted dowrward to the mininum acceptable value of 2.13 volts. h following prn= tim which provides instructions to perform !
individual call equalizing charge was reviewed: :
TP 415 Individual Cell Equalization Charge for Station Batteries 3A, 3B, 4A and 4B Safety Evaluation Stmma W:
No new equipnent or ocmponent (except the temporary use of a portable battery charger) N been aMari to the systemi. The portable charger is to be located and seismically supported outside the respective battery rooms. Therefore, the probability of occurrence or the consequences of an accident or malfuncticn of equipnent inportant to safety previously evaluated in the IEAR has not been incrmanari.
7he portable battery will be temporarily av sfced in parallel to the iniividual cell of the battary. During this process should a design basis event occur, the 125 VDC battery systen has adequate capability to 3 supply the vital DC loads without any adverse effects. 7herefore, the possibility of an accident or malfunction of a different type than any eval.uated previously in the EEAR has not been created.
The iniividual equaliziry of the batter cell (s) is intended to elevate the low voltage of the weak cell, thus inproving the margin of safety noted in the 7bchnical Specificaticos.
Date of Charge: March 17,1988
- 4) Ib correct the electrolyte level of the low specific gravity cells on a one time basis, the following procedure was prepared and reviewed:
TP 414 One Time Electrolyte level Cbrrection of Station Batteries 3A, 3B, 4A, and 4B Safety Evaluatico Suman 1
No new equipnent or cxmponent (except the tamporary use of a portable battery charger) has been aMari to the systan. The portable charger is to be 1ccated and seismically supported outside the respective battery recrs. Therefore, the prcbability of emtvrince or the ccnsequences of an accident or malfunction of equipment important to safety previously evaluated in the FEAR has not been incrmamari.
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h portable battery will be tam 5crarily w.-cted in pc tallel to the 11 - 2 l
individual cell of the battery. During this process should a design basis event occur, the 125 VDC battery systen has adequate capability to supply the vital Dc loads without any adverse effects. Therefore, the possibility of an accident or malfunction of a different type than any evaluated previously in the FSAR has not been created.
The individual equalizing of the batter cell (s) is intended to elevate the low voltage of the weak cell, thus inproving the margin of safety noted in the 7%chnical Specifications.
Date of Change: March 18, 1988
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- 5) Tb fill condenser hotwells of both units with the stan@y steam generator i feedwater ptmp systen. The following & b4 change was written and ;
reviewed:
0-OP-074.1 Standby S/G W Systen Safety Evaluation Su-avy Iccation, configuration and operation of the new Standby Steam Generator Feedwater Punpa (SSGFPs) have no effects on the accidents analyzed in the FSAR. This addition of providing bachp in case of a fire in the Auxiliary W punp area increases the inherunt ruliability of that area.
The SSGFPs are located sufficiently remote from the Auxiliary N pungs and are powered fran the C-has 4KV systen, 5hich can be fed by the thit 1 and 2 cranking diesel generator tpon loss of offsite power. Therefore, ,
the proposed pro *al change will not increase the probability or consequerces of an accident analyzed in the FSAR, nor will it impact the functioning of any safety related equipnent inportant to safety. No new accident or ralfunction of a different type will be created and no margin of safety as defined in the basis for any Technical Specification is decreased. '
- 6) EIX' loadirq was reviewed against the conflict with the operability of the control rocn ventilation syntan and the chr.rging pung W requirement which was higher than originally evaluated. As a result, the following precedures were revised:
a) 3 (4)-IDP-E-0 Reactor Trip or Safety Injection i b) 3 (4)-EDP-ES-0.2 Natural ciru11ation Cooldown i l
c) 3(4)-LOP-ES-o.4 Natural Cirtx11ation Cooldown With steam Void in i Vessel (Without RVDE) d) 3 (4)-DOP-ES-0. 3 Natural Cirullaticm Cooldown With Steam Void in Vessel (With RVUE) ,
e) AP-0103.32 Reactor Cold Shutdown Otniitions ,
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f) 3 (4)-GOP-305 Unit Standby to Cold Shutdown Safety Evaluation Sun == W With the ocmpressor for Control Rocn Air Otmpressor (CRAC) Unit C disabled for the special case of a unit in cold shutdown less than 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> with the other unit at power, the control rocn will remain habitable and EDG loading will be acceptable even with a single failure.
'Ibe details are described in JPE-PIN-SEIJ-88-024 (Rev. 0) and JPE-Ie86-74 (Rev. 2).
Tests were conducted to show that average tanparatures in the control tecn will not avnand allowables. Accordingly, cperation with two control roca air handlers ard one ocaprussor would be within the h=nted design basis for ocntrol roemi ventilatica systant operation post-IDCA. Using test data obtained from the plant for the charging punps, a value of 114 W was calculated for =v4 == punp power requirements. 'Ihis value has been irwigrated into the calculation for EDG loading and has been determined that diesel loadirg runnins acceptable. 'Ibereform, the pr*_ prmanmal charge will not increase the probability or consequences of an accident analyzed in the FSAR, nor will it impact the functioning of any safety related equipnent inportant to safety. No new accident or malfunction of a different type wi21 be created and no margin of safety as defined in the basis for any Technical Specification is decr h .
Date of Changes June 8, 1988
- 7) Steam Generator W control valves acceptance criteria was changed frun 5 seconds to 6.8 seconds. 'Ihis includes the consideration of a conservative time between the SI actuation ard the W isolation signal.
'Ihis charge was made through the followirg pw-alure:
3 (4)-<6P-074.2 S/G W Centrol Valves Operability 'Nst Safety Evaluation Sumary Main Steam Line Break (MIB) is tbs only FSAR safety analysis for which I the W isolation response time is critical. 'Ibe delay time for W isolation a =
- in the current 'Nrkey Point MIB analysis is 7 seccods which was typically viewed as ocosisting of two seconds for signal '
processing and logic delay plus 5 seccods of valve stroke. 'there are no unreviewed safety questions because the prtposed procedural charyfe will ;
not increase the probability or consequences of an accident analyzed in i the TSAR, nor will it irpact the functionity of any safety related equipment important to safety. No new accident or malfunction of a different type will be created ard no margin of safety as defined in the basis for any 'Nchnical Specificaticn is decreased.
I Date of Charges Septanbar 24, 1987 l 11 - 4
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- 8) Operation of Main Steam (E) radiation monitor (RAD-6426) zwquires that E sanple line valves be open during normal cperation. However, FSAR requires these valves to be normally closed. In addition, blowdown !
sanple line isolation valves are open during plant operation but a single i failure can cause one of these valves to rumain open during accident conditicos. The following pFc tim charges are made to allow the opening of these valves dur:ng normal operation with operator action specified in case of an accident:
3 (4)-IDP-E-3 Steam Generator Tube cupturu Safety Evaluation Sumary A detailed evaluaticn adiresser. i that opening of the isolation valves and blowdown valves is acceptable with ocupensatory operator action because:
- 1. The probability of occurrence or the ocnsequences of an accident or malfunction of niir J inportant to safety previously evaluated in the FSAR has not been incraaaad since any accident involving the sanple lines would be bounded by the accident analyses diani===d in the FSAR.
- 2. The possibility of an accident or malfunction of a different type than any previously evaluated in the FEAR has not been created because any postulated failure of the 76 or SG blowdown sanple tubing is similar to and bounded by accidents previcmasly analyzed in the FSAR.
I
- 3. The margin of safety, as defined in the basis for any Technical Specification, has not been increased because the operation of any equipnent addraaad in the Technical Specificaticos is not I adversely affected. l Date of Change March 25, 1988
- 9) A safety evaluation was provided to allow the electrical conduit i installatico for monitoriry PCs leaks in Unit 3 reactor head area. This I evaluation provides )ctificaticn and rostrictim for Unit 3 in Modes 5 or 6. PC/M 88-046 ard 88-193 provided additieral evaluation to sqport cperation in other Modes for both units.
- 10) Instructicos were prtnided for mcnitoring CCW heat exchangers so that cleaning of heat exchangers could be dcne in a timely inanner. The following p wooduru was reviewed:
TP-419 CCW Heat Excharger Performance Monitoring Safety Evaluation Smmary The CCM heat exchanger cleaning program assares adorpate heat transfer 11 - 5 i
- - - -r--- -v-e-------,,-w-,, , , , , - - - - - - - , - - - - - - , , . , - - - - - , - - - - - - < -
, - - - _ - - - - -, ,---r- - + r-- ,___- aw-,r-
capability ====4ng CV-2201 fails to close. If ICN operability camot be demonstrated with a failure of CV-2201 to close, an operator will be prepared to isolata ICM flew to TPCW heat exchargers. Therefore, the probability of occurrence or the ocmaequences of an accident or malfunction of agiimant inportant to safety previously evaluated in the safety analysis has not irc ===A.
With valve 406 open, a single failu::s will not cause a loss of ICN flow to the CCM heat exchangers. Therefore, the possibility for an accident ,
or malfunction of a different type than any evaluated previously in the safety analysis report has not been created.
The basis for the ICM systeel Technical Specification is that one puup provides sufficient flow to the CCW heat exstangers to renove heat created by a IDCA. Sirce gening valve 406 aneures a single failure will not obstruct ICM flow to the COf heat exchangers, the margin of safety as defined in the basis for the ICN '14chnical Specification is not reduced.
Date of Charge Decenbar 31, 1987
- 11) Instructions were provided to perform the testing, analysis and data i reporting of the contalment structure post-tensicning systen (15 year surveillance). 'Ihe folicwing procedures were reviewed to ensure that the '
instructions contained in the precetres do not involve any unroviewed safety questions: '
a) PrWire 18712-106-CP-1 inndon Surveillance Prdim for ,
(Rev. 2) Containment Structure Post-Tensioning l Systen (U-3)
I b) Prmachim 18712-106-CP-1 14ndcm Surveillance Prmarhire for !
(Pav. 2) Containment Structure Post-Tensicning i System (U-4)
Safety Evaluation Surmarv 1he use of the achile crans for lifting the platforms and rams ard the use of the PSAs for tardon surveillance do not <tama9a any safety related 1
equipnent. Lifted loads by use of safe load paths were prevented frta l affecting any safety related equipnent design features, and additicnal j testirg was bourded by the existing 14chnical Specificaticns ard remain i
within the limits of FSAR provisions. Therefore, the prtposed prmerhiral change will not increase the probability or consequences or an accident analyzed in the FSAR, nor will it impact the functicnity of any safety related equipnent inportant to safety. No new accident or malfunction i' of a different type will be created ard no margin of safety as defined in the basis for any 1bchnical Specificaticn is decreased.
i Date of change: April 29, 1988 I
i 11 - 6 1
! I l
- 12) 7b stardardize the setpint for auxiliary oil punp autostart switch (PS-
- -3607), emergency oil gap DC autostart switch (PS-*-3608) and turning gear oil pmp autostart switch (PS-*-3609), the following prNma change was subnitted and reviewed:
AP 0150.3 Changing Setpoints Safety Evaluation Sumary This setpoint charge will be perforined in a non nuclear safety related systen in the secondary plant. It cannot affect the probability of equipnent malfunction nor increase the acome@ences of any accident .
Whether or not described in the FSAR. It cannot affect the consequences I of equipnent malfunction as described in the FSAR and it will not decrease the margin of safety of any Technical Specification. L This setpoint change does not create an unrirviewed nuclear safety question.
Date of Change: June 23, 1988 I
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_ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ . _ _ _ _ . . . _ _ ~ - _ _ _ . _ , . _ .. _
(iii) 'IESIS NO EXPERDE! NIB
'Ihis section contains the results aM ocoelusions for special tests that were ocmpleted during the reporting period. Special tests still in progress at the eM of the reporting period are also described.
No special tests wers ocmpleted during the reporting period.
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l APEBEX A NMRL REPGU OF SAFEIY AND RELIEF VALVE ORIIDCES i
By letter dated June 18, 1980 (Ir80-186), Florida Power and Light stated the '
intent to oceply with the requirments of item IIK.3.3 of Enclosure 3 to the ocmission's letter of May 7,1980 (Five Additional 'IMI-2 Delated Requirments for Operating Reactors) .
'Ihe following is a list of safety valve and power operated relief valve (Itav) actuations for 'Ibrksy Point Units 3 and 4 frua July 1,1987 to June 30, 1988. !
i l
axzounE mu xry i i
3-OP 041.4 and 4-OF-f.41.4 "Overprorsure Mitigating System" !
3-06P-041.4 aM 4-CSP-011.4 "Overproscure Mitigating Systen Nitztgen Backup i Isak and A r.~t! mal 'Dast" ,
OP 0009.1 "Valvt c Ach.aq PWire" Unit 3 t L
July 1, 1987 TORV 455C aM 456 were cycled per 3-CP-041.4. ICRV l cperation was satisfactory. '
1 July 24, 1987 IWV 455C and 156 were cycled per 3-<EP-041.4. ICRV operation was satisfactory. f j
August 7, 1987 ICRV 455C aM 456 ware cycled per 3-CP-041.4. PORV {
operation was satisfactory. I August 11, 1987 PORV 455C was opened per OP 0209.1 after maintenance was ;
performed to correct cksal iniication (limit switcts out). !
IWV cperaticri was satisfactory. [
l a August 15, 1987 3-06P-041.4 was performed satisfactorily, however, IW V (0410 to 0510) 455C aM 456 annunciators were locked in, eg... Annunciator A4/1 not clearad. Valves were cpen for a vent path per cannants made in the pWim, 3-OP-041.4 was performed over the same time period. PORV 155C and 456 were cycled satisfactorily. -
Septater 27, 1967 ICRV 455C and 456 were cycled per 3-CP-041. 4 ICRV l cperation was satisfactory.
PORV 455C aM 456 were also cycled per GP 0209.1. ICRV {
operation was satisfac'.ory. l L
l 4
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'I\trkey Point Units 3 and 4 Decket Nos. 50-250, 50-251 Reoort of Safety and Relief Valve Cha11ernes October 0, 1987 PORV 455C and 456 were cycled per 3-OP-041. 4 PORY (0100 to 0200) operation was satisfactory. 3-06P-041.1 was perfor1ned over the same time period. PJRV cperation was satisfactory.
Novater 3, 1987 PORY 455C and 456 were cycled per 3-OSP-041.4 PDRV cperation was satisfactory.
M r 8, 1987 PCRV 455C and 456 waru cycled per 3-OSP-041.4 ICRV operation was satisfactory.
January 15, 1988 PORV 455C and 456 were cycled per 3-OP-041.4 ICRV cperation was satisfactory. PCRV 455C and 456 were also cycled per OP 0209.1. PCRV cperation was satisfactory.
January 31, 1988 ICRV 455C and 456 were cycled par 3-OSP-041.4 ICRV cperation was satisfactory. PCRV 455C and 456 were also cycled per 3-OP-041.4. KRV cperation was satisfactory.
l March 25, 1988 ICRV 455C and 456 were cycled per 3-OP-041.4 PCRV
]'
cperation was satisfactory.
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Turkey Point Units 3 and 4 Docket Nos. 50-250, 50-251 Raoort of Safety and Relief Valve Challances Unit 4 October 13, 1987 ICRV 455C and 456 were cycled per OP 0209.1. PORV operation was satisfactory.
October 19, 1987 PORV 456 was cycled per OP 0209.1 as part of post-maintenance testing. Valve was leakiry through and required a spring bencts adjustaent. ICRV cperation was satisfactory.
October 21, 1987 ICRV 455C and 456 were cycled per 4-06P-041.4. KRV (0930 'IO 2150) operation was satist . 4-OP-041.4 was also perfomed on ICRV 455C aM 456 dar this period. ICRV operation was satisfactory.
October 29, 1987 ECR'
- 456 was cycled gar OP 0209.1 as part of poot-maintenance testing. Valve was leaking through aM had the internals replaced. PORY cperation was satisfactory.
ICRV 456 was also cycled per 4-06P-041.4. ICRV operation j was satisfactory.
Nevernber 2,1987 ICRV 456 was led per OP 0209.1 as part of post-maintenance . Valve was leaking and was repacked.
PORV operation was satisfactory.
Noverber 5, 1987 ICRV 455C and 456 were cycled per 4-03P-041.4. FORV operation was satisfactory.
i
] Noveober 20, 187 ICIN 455C and 456 were cycled per 4-CP-041.4. PORV cperation was satisfactory.
Noveraber 27, 1987 PORV 455C and 456 were cycled per 4-CP-041.4. ICRV cperation was satisfactory.
February 8,1988 ICRV 455C arx1 456 warm cycled per 4-OP-041.4. ICRV i cperation was satisfactory.
g February 18, 1988 PORY 455C and 456 warm cycled per OP 0209.1. PORV cperation was satisfactory. ,
l May 1, 1988 ICRV 45SC was cycled per 4-OSP-041.4. ICRV cperation was
! satisfactory.
KRV 456 was not cycled darity this peccedure because POV-
)
4-535 (ICRV stcp valve) calld not be closed. I and C ;
Department was contacted for troubleshooting. Re: Plant Work Order C404738. ICRV 456 was unhaagently cycled per 4-CP-041.4 under CISC 5850 which allowed a one-time-<:nly i
test of PCRV 456 with MT.'-4-535 incperable. PCRV 456 operation was satisfactory.
May 4, 1988 ICR7 455C arul 456 wars cycled per 4-CIH)41.4. ICRV cperation was satisfactory.
i
'Ibrkey Point Units 3 and 4 Docket Noso 50-250, 50-251 Recort of Safety and Relief Valve Challansas May 6, 1988 ICRV 455C and 456 were cycled per 4-CS1H)41.4. PORV cperation was satisfactory. PORY 455C and 456 wara also cycled per OP 0209.1. PGW cperation was satisfactory.
APRNDIX B SIDM GDMWitR 'ItJIE DEFILTIGE tJnit 3 stama y== aim tube IWica results for the inspectica performed hi June 8, 1987 and June 13, 1987. IJnit 4 did rut perform an inspection during this riparting period.
(This ripoet was preriously = *mitted in ammettana with A9EC code regilirteents.)
FORM 4!$ilOu4ER$'OATA'EFORTFCREODYCUPRE4TEIAM!nAi!04RESULis As required by the provisicit of the ASE Code Rules page 1 of 1
- 1
! $UPRARY Cf ECDY CURRENT EIAMINAi!04 RE!UI,TS l l uin u n ni si n n ie n n n nis sa n n inn a s s ani n u n n e;n nie n n e n nu n n u n u n u n u n u n is in en s u i i
1 PLAti TURREY PO!st MUCLIAR P0utR PLAuf Uulf W. 3 !
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! EIAM!nat!0N OATES: JUtt I, 1997 THRU JUNE 13,1997 i
- 5 FEAR 1 TOTAL TOTAL 1 TOTAL 1 TOTAL : TOTAL !
! ! ! ! I l ......I
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! !...... .......! I I l.. .. !
1 3E2109 ! 332 1 18) 4 1 0 1 0 1 0 1
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- GEtERATCR I IARS I 1 THROU6H 6 ! TO 1 OAILLED SUPP0Af I
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t CERT!FICAi!0N OF RfCORD 1 i !
secerttif that the statoesnts le this rxord are correct and the tubes inspected eere tested full lentth !
- in attoriance eith the requirteents of Section 11 of the ASME Code. i 1
I FLOR!M POWER and LllNT COMPANY !
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FOM N!$ il CumER$' OATA RIP 0tf FOR ED0Y CURRE47 EIMIN4fl0N RESULil As requires by the provisions of the AS'E Code Rules p y e 3 of 7
- ED0f CURREtt EIMINAi!CN RESULTS 1
! PLuis TURtti PO!NT NUCLEM POET PLANT tilli be. 3 $ FEM SENERATOR: 3E2104 :
- I
- EIM! hat!0N CATES: A1stI,1997 THRU JUNE 13, 1997 : ,
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! 37 ! 21 1 !! !HOTLES ! A90VE $!ITH $UPPORT I i... .!.. ......!..... ........! I. - .. ..I I ! ! ! 1
- 37 22 1 13 1 HOT LE6 ! A40YE $!ITH $UPPORT I
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e 80AM NIS II ONutAS* DATA MP0AT FOR E00Y CURRENT EIMINAi!ON MSULTS l
As rquired by the provisions of the ASE Code Rules page 4 of 7 a STEM SEEAATOR EDDT CURRENT (IMINAtl0N MSULi$ !
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FORA N!S-DI QuiltRS' DATA REPORT FOR ED0f CURRENT EIMINAi!0N RESULTS As retutred by the UcViticas of the A$ME Code Rules p ge 5 of 7 I !
l STEM 6tutPAf0R EDIT CUEMNT EIMINAi!ON RESULTS :
1:nninin n nn uun unnun aninininnun un u n u n nu n n u n unu n u n n u u n u n u n u n !
- i PLANT
- TURKlf PO!qi IllCLEAR POER PLAsi INIT NO. 3 STEM GEntRATOR: 'E2101 I
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I !!AMlWAi!04 CATES: JUE I, 1997 THRU JUNE 13, 1987 :
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1 40 1 25 1 10 1 COLD LES I A40VE FIFTH SUPPORT !
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I42 1 33 : 13 iHOTLEI ! SLUDGE PILE !
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FORM NIS H OWNER $* DATA REPORT FDR ED0f CUGRENT [IMINAfl04 RESUL,fS As required by the provisions of the ASPC Code Pules page 6 of 7 :
I SitM SENERATOR EDDY CURRENT EIMINAi!CN RESUti$ :
- sum...............................................................................................I P'. MT: TURGT P0luf IEJCLEAR POWR PL4 fit tali NO. 3 SitM 9tNERATOR: (210C 1
- I
! EIMINATIC4 DAf t$1 JU#t I, 1997 THRU JUl(13,1981 !
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FORM MIS 80 OuutR$' DATA REF0tf FOR ED0Y CURRENT EIAM!nAi!DN RESulil As required by the provisions of the ASME Code Rules page 7 of 7
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AFMNDIX C REIDAD SAFErf EVAIIATICH SLM9Rf
'Iurkey Ibint Unit 3 is cperatirq in Cycle 10 with 112 Westingn==a cptimized fuel aanashlim ard 45 Westinfn==a 15 x 15 law parasitic (ID0AR) fbel assemblim. Fbr cycle 11 (expected startup mid-my, 1987) ard aanvynit cycle, it is plamed to rufbel the 'Ibrkey Ibint Unit 3 core with Westinghomo 15 x 15 cptl=Imi fuel maanuhly (OFA) regicns. In a llomsirq submittal to the NRC,agptwal ma requested ard later reonived for the transiti'.m from IDPAR fuel to OFA and the maannlated p ----i cfiarges to the 'Ibrkey Ib'.nt Units 3 ard 4 'Itchnical Specificaticns. 'Ihe liomsirq ra*=lttal justified the acagntibility of Ophinimi Ebel W11es (OFAs) with IDPAR fuel maammhlies in a mixed-fuel core as well as a ib11 OFA care. 'Ihe liamsirg fa*mittal cxntained mechanical, ruclear,thermi-hydraulic, ard acx:icknt evalmticns Wilcts are also applicable to the cycle 11 safety evalmticn. Approval of the llomse agplicaticn for the OFA transiticn as granted by the NRC in a SER, dated Danruber 9,1983.
A sigrtificant rumber of Integral Fuel IMrnable Manrher (IHR) rub are beirn used for the first time in 'Ibrkey Ibint Unit 3* as part of the Regicn 13C ard 13D fuel assablics. A note detailcd rinar'ipticn ard evaltaticn of IHRs for 14 x 14,15 x 15 ard 17 x 17 ibel arrays are given in WCAP-10445-NP-A. 'Ihe NRC has a[prwed the tne of Inns for Westinjhome fuel rtds in 15 x 15 fuel a h lics.
'Ihe effccts of the relcad cn the deign basis ard postulated incidmts amlymi in the ISAR have been examined. In all cases, it as fourd that the effects can be m ------Ated within the cxnservatism of the initial amurticns used in the previcus a[plicable safety aralysis.
- 'Iurkey 1bint Unit 3 did tuve h=Luticn Inw rub in cycles 8 ard 9.
P. O. BOM 14CDO, JUNO BE ACH, F L 334 0 0420 SEPTEMBER 1 1963 L
i , L-88-366 2
1
, U. S. Nuclear Regulatory Commission Attn Document Control Desk Washington, D. C. 20555 i
Gentlemen:
Re Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251
- 10 CFR 50.59 Report
- Florida Power & Light Company's Report on "Changes, Tests and j Experiments Made Without Prior Commission Approval" for the
- period July 1, 1987 through June 30, 1960 is attached.
Very truly yours, l f ,t Q i W. F. Co ty Senior V e President - Nuclear >
WFC/SDF/gp Attachment i cc: Dr. J. Nelson Grace, Regional Administrator, ,
Region II, USNRC >
- Senior Resident Inspector, USNRC, Turkey Point Plant l t
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SDFCFR.RPT l I l j .
J an FPL Group company !