ML20196G285
| ML20196G285 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/31/1987 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8803080041 | |
| Download: ML20196G285 (318) | |
Text
{{#Wiki_filter:_ _ - - _ _ - _ TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT (UNITS 1 AND 2) 10 CFR 50.59 ANNUAL OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION o l
/ j I'I987 - DECEMBER 31> 1987 DOCKET NUMBER 50-327 nd 50-328 LICENSE ~'
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SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING. REPORT. TABLE OF CONTENTS Preface - Acronym List I. Summary of Emergency Core Cooling System Outages 1 L II. Summary of Primary System Relief or Safety Valve 1 Actuation - III. Summary of Facility Changes . Modifications 2 Temporary Alterations 11 IV. Summary of Procedure Changes
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1 Abnormal Operating Instructions 13 ' Emergency Instructions 24 Surveillance Instructions 26 special Test Instructions 107
- V. Summary of Special Tests 122 VI. Occupational Exposure Data 139 l
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SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 NRC ANNUAL OPERATING REPORT 1987 The following criteria establish the bases for the items contained in this report. I. Facility Changes A. Modifications The ECN Closure Group reports to Site Licensing the ECNs that have been closed for inclusion in the annual FSAR update. The same ECNs are reported in the annual operating report. Since the ECN Closure Group reports totally closed ECNs, and field complete ECNs were reported in previous annual operating reports, a cross-check was performed. Only the ECNs not previously reported are included in this report. B. Temperiry Alterations Temporary alterations to the facility are reported based , on how long the alteration has been in existence. Using ' the same criteria used for the FSAR update, an alteration will be reported if it has been, or is expected to.be, in existence for greater than one year. A temporary alteration is documented on a TACF. Previously reported alterations still in existence are listed by their TACF number only. New alterations meeting the above criteria are described and a safety I summary provided. i II. Procedures Technical specification surveillance instructions, abnormal l operating instructions, and emergency instructions have been determined to be as "described in the FSAR." Changes to these procedures are reported if they satisfied one or more , of the following criteria: l A. Procedure Changes Before May 20, 1987
- 1. Made a significant change to the scope, technique, ;
or sequential order of steps affecting results or j nuclear safety.
- 2. Waived or violated technical specification or licensing req 2irements.
- 3. Affected a quality control hold point.
- 4. Changed or revised the review / approval authority or responsibility.
- 5. Implemented a temporary alteration to operate CSSC equipment.
- 6. Changed the acceptance critoria.
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A summary of the safety evaluation for each procedure change reported is included. B. Procedure Changes After May 20,.1987 A USQD was required for all procedure changes prior to . May 20, 1987. SQA-119 was revised on May 20, 1987, ' requiring a "screening review" be performed to provide a record of review for changes to instructions, procedures, the radwaste system or facility, or test and experiments proposed to be considered at SQN. If the screening review determined a USQD was not required, the pr:cedure is not reported. h I 1 d i h l 1 I a
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THE FOLIhWING IS A LIST OF ACRONYMS COMMON TO THIS REPORT. ACRONYM DEFINITION ABG";S AUXILIARY BUILDING GAS TREATMENT SYSTEM AC ALTERNATING CURRENT ACA AUXILIARY CONTROL AIR AFW AUXILIARY FEEDWATER AHU AIR HANDLING UNIT AI ADMINISTRATIVE INSTRUCTION ANSI AMERICAN NATIONAL STANDARDS INSTITUTE AOI ABNORMAL OPERATING INSTRUCTION ASME AMERICAN SOCIETY OF MECHANICAL ENGINEERS ASTM AMERICAN SOCIETY FOR TESTING AND MATERIALS ATWS ATTEMPTED TRIP WITHOUT A SCRAM AUX AUXILIARY AWG - AMERICAN WIRE GAUGE A/C AIR CONDITIONING . BIT BORON INJECTION TANK i CAM CONTINUOUS AIR MONITOR CAQR CONDITION ADVERSE TO QUALITY REPORT CATS COMMITMENT ACTION TRACKING SYSTEM CCP CENTRIFUGAL CHARGING PUMP CCS COMPONENT COOLING SYSTEM CCW COMPONENT COOLING WATER CEB CIVIL ENGINEERING BRANCH CEB CIVIL ENGINEERING BRANCH CFM CUBIC FEET PER MINUTE CFR CODE OF FEDERAL REGULATIONS CP CRANKCASE PRESSURE CPM COUNTS PER MINUTE ' CRDM CONTROL ROD DRIVE MECHANISM CRI CONTROL ROOM ISOLATION CRVI CONTROL ROOM VENTILATION ISOLATION CSP CONTAINMENT SPRAY PUMP CSS CONTAINMENT SPRAY SYSTEM CSSC CRITICAL SYSTEMS, STRUCTURES, AND COMPONENTS CV CHECK VALVE CVCS CHEMICAL VOLUME CONTROL SYSTEM D/G DIESEL GENERATOR DC DIRECT CURRENT DCR DESIGN CHANGE REQUEST DNE DIVISION OF NUCLEAR ENGINEERING DPM DIVISION PROCEDURE MANUALS DPSO DIVISION OF POWER SYSTEM OPERATIONS ' ECCS EMERGENCY CORE COOLING SYSTEM ECN ENGINEERING CHANGE NOTICE EGTS EMERGENCY GAS TREATMENT SYSTEM el ELEVATION , EMSL ELECTRICAL MAINTENANCE SECTION LETTER ! EOI EMERGENCY OPERATING INSTRUCTION i EQ ENVIRONMENTAL QUALIFICATION EQIS EQUIPMENT INFORMATION SYSTEM
J ERCW ESSENTIAL RAW COOLING WATER ESF ENGINEERED SAFETY FEATURE FCR FIELD CHANGE REQUEST FCV FLOW CONTROL VALVE FQE FIELD QUALITY ENGINEERING' , FSAR FINAL SAFETY ANALYSIS REPORT FW FEEDWATER
- HCI HAZARD CONTROL INSTRUCTION HJWT HIGH JACKET WATER TEMPERATURE HVAC HEATING, VENTILATION, AND AIR CONDITIONING ICF INSTRUCTION CHANGE FORM IMI INSTRUMENT MAINTENANCE INSTRUCTION I/P CURRENT TO PNEUMATIC kW KILOWATT LCO LIMITING CONDITION OF OPERATION LER LICENSEE EVENT REPORT LLRW LOW LEVEL RAD WASTE LOP LUBE OIL PRESSURE -
MA MILLIAMPERE MCC - MOTOR CONTROL CENTER MFIVs MAIN FEEDWATER ISOLATION VALVES MFW MAIN FEEDWATER MPC MAXIMUM PERMISSIBLE CONCENTRATION MS MAIN STEAM MSIV MAIN STEAM ISOLATION VALVE MVAR MILLIVOLT AMPERES REACTIVE M&TE MEASURING & TEST EQUIPMENT NBS NATIONAL BUREAU OF STANDARDS NCR NONCONFORMANCE REPORT NDE NONDESTRUCTIVE EXAMINATION NEB NUCLEAR ENGINEERING BRANCH NQAM NUCLEAR QUALITY ASSURANCE MANUAL NRC NUCLEAR REGULATORY COMMISSION PD POSITIVE DISPLACEMENT PM PREVENTATIVE MAINTENANCE PMP PREVENTATIVE MAINTENANCE PROGRAM PORV POWER OPERATED RELIEF VALVE PRO POTENTIAL REPCRTABLE OCCURRENCE psi POUNDS PER SQUARE INCH psia POUNDS PER SQUARE INCH ABSOLUTE psid POUNDS PER SQUARE INCH DIFFERENTIAL i psig POUNDS PER SQUARE INCH GAUGE l PT PRESSURE TRANSMITTER QA QUALITY ASSURANCE QC QUALITY CONTROL l QE&C QUALITY ENGINEERING & CONTROL QMDS QUALIFICATION MAINTENANCE DATA SHEET RCP REACTOR COOLANT PUMP RCS REACTOR COOLANT SYSTEM RCW RAW COOLING WATER REV REVISION RHR RESIDUAL HEAT REMOVAL RPI ROD POSITION INDICATOR RSW RAW SERVICE WATER { RTD RESISTIVE THERMAL DETECTOR ' RTV ROOM TREATED VULCANIZATION i i i
RX REACTOR R.G. REGULATORY GUIDE SAR SAFETY ANALYSIS REPORT SCF STANDARD CUBIC FEET SCFH STANDARD CUBIC FEET PER HOUR SCR SIGNIFICANT CONDITION REPORT SE SHIFT ENGINEER SI SURVEILLANCE INSTRUCTION SI SAFETY INJECTION SIS SAFETY INJECTION SYSTEM - SNM SPECIAL NUCLEAR MATERIAL SOI STANDARD OPERATING INSTRUCTION SP STANDARD PRESSURE SPDS SAFETY PARAMETER DISPLAY SYSTEM S PTS SEQUOYAH PROCEDURES TRACKING SYSTEM SQA SEQUOYAH ADMINISTRATIVE INSTRUCTION SR SURVEILLANCE REQUIREMENT SRO SENIOR REACTOR OPERATOR SSPS SOLID STATE PROTECTION SYSTEM STI - SPECIAL TEST INSTRUCTION TACF TEMPORARY ALTERATION CONTROL FORM TAVG AVERAGE TEMPERATURE TI TECHNICAL INSTRUCTION TSC TECHNICAL SUPPCRT CENTER T.S. TECHNICAL SPECIFICATION (S) UHI r UPPER HEAD INJECTION ~ UO UNIT OPERATOR USQ UNREVIEWED SAFETY QUESTION , USQD UNREVIEWED SAFETY QUESTION DETERMINATION V VOLT VCT VOLUME CONTROL TANK WC WATER COLUMN WGDT WASTE GAS DECAY TANK WP WORK PLAN ,
1 l l l - i i O O O SL MMARY OF O
- O EMERGENC" CORE O O COO._ING SYS"EM O
! and l O PRIMARY SYSTEM O ! O RE _lEF or SAFE"Y O VA._VE ! O o O O
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r SEQUOYAII NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATIN". REPORT i I.
SUMMARY
OF EMERGENCY CORE COOLING SYSTEM (ECCS) OUTAGES No ECCS system was declared inoperable while in an applicable mode of operation in i 1987. Both units were in mode 5 the entire year. a II. PRIMARY SYSTEM RELIEF or SAFETY VALVE ACTUATION There were no challenges to the primary system relief or safety valves in 1987. t 4 1_
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O O l O O O S.MMARY OF O l O F A C l._l Y O CHANGES
- O O O MODIFIC ATIONS O O O I O -
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Page No. 1 02/M/88 SEQUOYan NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES IN THE FACILITY - M00lFICATIONS DESCRIPTION SAFETY ANALYSIS g I ** ECD - L5247 DCA 0535 This modification replaced the votume control tank tevel controtter The proportional only controtter allows the divert valve to be operated (1-TC-62-129A) from a proportional plus reset plus derivative te a manualty. If the controtter faits, no safety hazard would be involved and proportional control only. the level in the volume cmtrol tank is still ef fectively controlled. The probability of an occurrence or consequences of an accident or metfunction were not increased, and the possibility for an accident of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
** Ecu - L5314 DCR 0661 This modification relocated the pressure switches PS-3-140s and PS-3-150s This modification did not change the equipment being used; it only changed from the west steam valve room to the suaillery building. This change was the location of tne equipment. The pressure switches were moved from a made tt, locate the switches in an area of tower temperature. Each of these high energy zone to a low energy zone not subject to a pipe break. The pressure switches serves as one of two pressure switches iAich will isolate hardware was reinstatted per the same seismic and electr'ical operation flow f rom the turbine driven aualtiary feedwater ptsg) to the associated criteria. The probability of an occurrence or the consequences of an steam generator on detecting tow pressure. accident or metfunction were not increased, and the possibility for an accident of a different type was not created. These instruments are not addressed by, and do not affect, the basis for the T.S. 'Therefore, the T.S. margin of safety was not reduced.
l ** ECD - L5353 l Oc3 0914 This modificatien disconnected handswitches 1-hS-1-158, -168, -178, -188, the switches are still instat ted tut are conptetely disconnected f rom the 1-NS-3-338, -478, -878, -100s,1-NS-72-40s and -418 which are not circuits and labeled "spare." These switches were instatted for component l documented as environmentatty qualified. These switches were used for testing only and had no function in accident mitigation. The probability saintenance and local testing of valves in the main steam f eedwater and of on occurrence or the consequences of an accident or matfunction were not containment spray systec:s. increased, and the possibility for an accident of a different type was not created. The margin of safety, as defined in the basis of any T.S., was l
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4 Page No. 2 02/22/83 SEGUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES IN THE FACILITY - MODIFICATIONS DESCRIPTION SAFETY ANALYSIS , t not reduced.
" Ec] - L5433 DCR 0433 This modification instatted a wire cage around the hatch at the entrance to This modification was to non-CSSC equipment and did not directly or the incore instrumentation penetration room from inside contginment. This indirectly affect nuclear safety. The prot. ability of an occurrence or the modification was necessary to prevent unauthorited personnet entrance which consequences of an accident or malfunction were not increased, and the may result in overemposures. The existing hatch cover was modified for possibility for an accident of a different type was not created. The operation by one person. The wire cage access door is key operated f rom margin of safety, as defined in the basis of any T.S., was not reduced.
the outside only.
** ECM - L5499 DCR 0741 This modification provided new togic and new wiring of the SQN MVAC system This modification did not change or affect the function of any (system 30) which causes the auxiliary buildire general supply f ans, safety-related equipment. The auxiliary building supply and exhaust fans auxiliary building exhaust fans, and the fuel handling area exhaust fans to are non-divisional power supplied and electrical safe separation C:'iteria stop upon initiation of an auxiliary building train A or train 8 isolation have been met. This electrical modification allows the sutject fans to signal, stop automatically upon an auxiliary building isolation signal. This decreases the potential for en offsite radiation event. The probability of' an occurrence or the consequences of an accident previously evaluated were not increased, and the possibility for an accident of a different type was not created. The operation or operational modes for the auxittary building supply and exhaust fans are not covered in the T.S. This change reduces the potential for en offsite radiation event and enhances the margin of safety as defined in the basic of the T.S.
C* ECJ - L5519 002 0735 This modification instatted a Rescusatic emergency escape device in the cab the function of the set f-rescue device is not nuclear saf ety related, nor equipped overhead crancs in the reactor buildings, the auxiliary toitding does it affect nuclear safety-related equipment. This device is for plant
4 Page No. 3 02/22/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CMANCES IN THE FACILITY - MODIFICATIONS DESCRIPTION SAFE 1Y ANALYSIS , and the turbine building. This device is a smatt package which is stored personnel safety only. The probability of an occurrence or the in the crane cab. consequences of an accident or matfunction of equipment were not increased, and the possibility for en accident of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced. " ECM - L5575 DCE 0972 This modification replaced timit switches for FC&30-87, FCO-30-107, The new equipment meets or exceeds the qualifications of the original FCO-30-22, and FCO-30-109 on MVAC (system 30) with switches that are equipment. Att of the original seismic design requirements are met. The envirorsnentatty qualified in accordance with the guidelines of NUREG 0588. probability of an occurrence or the consequences of an accident or malfuction were not increased. The possibility for en accident or malfunction of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced. " ECM - L5587 DCS 1159 This change revised the isometric drawings to reflect the new analysis This change was for docunentation only, and no ph-sical work was done. No based on the east valve room seismic spectra. plant safety fmetion or feature was changed or degraded. The probability of an occurrence or the consequences of an accident or mali mction were not increased, aruj the poselbility f or en accident of a dif ferent type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced. " ECM - L5624 DCE 1185 This modification changed drawing 47W846-2 to show valve 1-33-704 normall y This was a drawing correction, and no uso was involved, closed per 50-0CR-1185. The valve function was shown incorrectly on the drawing.
Page 20. 4 02/22/88 St.QUOYAd NUCLEAR PLANT 10 CFR 50.59 1987 WRC ANNUAL OPERATING REPORT CMANCES IN TNE FACILITY - MODIFICATIONS DESCRIPTION SAFETT ANALTS!$ 6
** Ecu - L5651 DCR 1170 This modification added to the logic of valves FCV-67-176 and FCV-6-182 an The SIS pump and room cooter are used only for accident mitigation. Adding "or" gate so the valves witt open on a SIS ping start signal as well as the this logic to the cooling water valve did not increase the probability of cooling fen motor start signet. This change ensured that cooling water to an occurrence or the consequences of an accident or malfunction. The the SIS pump ott cooter is available anytime the $15 pimup is operating. possibility for en accident of a dif ferent type was not cented. The T.S.
The SIS pump oil cooter is in parattet with the ANU cooter. states that cooling water sust be available to these cooters. This change ensures the margin of sa8ety is maintained.
" ECM - L5702 DCt 1358 This modification instatted an additional valve (63-697) downstream of The new valve is operable by hand only and does not interface with 1E valve 63-564 on the SIS (system 63). Valve 63-564 Leaked and was equipment or power supply. It has been seismicatty evaluated to show that inaccessible for making repairs. The inaccessibility of valve 63-564 sede it is property supported for its location in a category I structure and in repair costs prohibitive. TVA class 8 piping. The probat ility of an occurrence or the conse<paences of an accident or selfunction of equipment were not increased, and the possibility for en accident of a different type was not created. The margin of safety, as defined in the basis cf any T.S., was not rechaced. ** Etu - L5715 DCR 1297 This modification replaced the plastic bushings in the CROM cooling suction The brass bushings perform the same functions as the plastic bushings, and danpers 2-TCO-30-81-84. -89, and -93 with brass bushings. The plastic the operation of the danpers is not degraded. The dampers are st'll bushings wear out in a short period of time. seismically qualified with the brass bushings. The probability of an occurrence or the consequences of an accident or malfunction were not increased, and the possibility for en occident of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
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m _ ._. _ _ _ _ Cage No. 5 - 02/22/88 SEQUDYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES IN THE FACILITY - MODIFICATIONS DESCRIPTION SAFETY ANALYSIS ,
** E CW - L)974 OCR *077 ~ This modification was made to relocate the mein feed ptmp turbine vibration This modification did not degrade the logic, control, or function of the recc.rder sequencer / selector switch from the back side of panet M-3 to a feedwater control system or other featurer required to perform nuclear soere tocation on the front side of panet M-3. This attows the operator to safety functions. This did not inntidete compliance to existing seisa/c conveniently monitor the individual vibration channels for spectfic and CA require n ts. The probabitity 0" en occurrence or the c w eg encem ..
Information needed during high vibration alarm conditions without having to of an accident or metfunction were not increased, and the possib G y for go behind the penet, an accident of a type different than that previously evetuated was not created. The margin of safety, as defined in the bests of any T.S., was not redJced. O ECM - L6122 c41/ 2271 This =dification voided spring s@ ports M10-6%, N10-616, and The spring s wnorts were originetty instatted to prevent targe tcading on 47A-464-3-135 on the CCW. the nozzels downstream of the supports. CES anetysis showed that removat of the sprir.g s @ ports did not invalidate the seismic quellfication of the piping. Since there was no change in the function or operability of the piping, the proba.bility of an occurrence or the consequences of an accident or malfunction of equipment were not increased. The possibility for an accident or matfunction of a different type was not created. The mergin of safety, as defined in the basis of any T.S., was not reduced.
** ECN - L6175 ~
OCR 2478 This modification was made to reduce the setpoints for PS-32-62 and Reducing the setpoint to 80 psig did not affect the system's ability to
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PS 62-88 from 84 psig to 80 .esig. The change was needed due to the control provide 70 psig to the air header for equipment which uses air sw ptied by air compressors operating excessively. this system. Att equipment which uses air is purchased to operate on a
, miniaun of 70 psig. The probability of an occurrence or the consequences of an accident or matfunction were not increased, and the possibitity for an accident or malfunction of a dif ferent type was not created. The L
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_m - , _ _ Page No. 6 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES IN THE FACILITY - MODIFICATIONS DESCRIPTION SAFETY ANAt,YSIS , i essential controt air system is nct specificatty defined in the basis of the T.S. However, the control air affects the basis by its requirement to make valves and systems available. Since this change did not effect the system's abitity to provide this function, the margin of safety was not reduced.
** KCN - L7092 DCit 2259 This modification was made to seat sit spare mechanical sleeves in the The seating of the reactor building shletd watt penetrations below et 724 shletd building watt up to el 724.0. This was done to maintain the seating will preclude water seepage in the event of site flooding. The changes did integrity as required by FSAR, Section 6.2. The sleeves were capped and not degrade the fire rating of the shield watt, and the cover plates welded seat welded to prevent floodwater entering the amulus. on the penetrations did not degrade the seismic design of the shield building watt or the mechanical penetrations. The probability of an occurrence or the consequences of an accident or metfunction were not increased, and the possibility for an accident of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not redJced. ** ECM - L7096 00] 1791 This modification installed tesperature thermocouples in the radiochemical This was done to ensure steam cycle samples are within the proper laboratory titration room on each sanpling cooling coil outlet. This also temperature range. FSAR, Section 10.3.5, describes secondary side water instatted temperature selectors and indicators on the titration panel and chemistry but does not describe sampling techniques or instrumentation.
connected thse to thermocouples. This change enhances the sanpling techniques and will ensure compliance with the water chemistry guidelines referred to in Section 10.3.5 of the FSAR.
** 1C] - L7105 DCR 2259 This modification abandoned the nunber 16 AWG TSQ teads in penetration Changing the cable f rom one lead to another :4ithin the same penetration
s Page No. 7 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CfR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES IN THE FACILITY - MODIFICATIONS DESCRIPTION SAFETY ANALYSIS - I rssubers 19, 38, 45, and 49 The cables were reterabated to rameer 16 AWG does not affect system operability or seismic analysis. The probability of TSP leads in the same penetrations. The green leads et 'he TSQ cables had an occurrence or the consequences of .sn accident were not increased, and deformed insulation causing concern as to whether they meet to the possibility for an accident of a different type was not created. The requirements. By changing to the TSP cables, there is no problem in modifications to these electrical penetrations were not dire tty addressed meeting EQ regJirements, and all IE requirements are met, in the T.S. T.S. 3/4.8.3 (overcurrent protective devices) was not affected. The margin of safety remained unaltered.
- ECW - L7137 DCR 2293 Performed physical modifications to various pipe stoports to qualif y the The modification on various pipe supports was performed to make sure the supports for the design basis events as required by the oppt(cable design pipe stoports were qualified both environmentally and seismicalty per criteria. These mndifications were performed on the fottowing systems: applicable design criteria. The safety function of the associated CVCS, AFW, SIS, RCS, and MS. mechanical systems was not jeopardized. Since the systems are more reliable, the probability of an occurrence or the consequences of an accident or malfunction of equipment important ts safety are rad xed. Each modification was steported by an individuet calcua ntoni and the effects on miscellaneous structures were considered. The omrida of safety, as defined in the basis of any T.S., was not reduced.
- ECM - L7147 DCR 2293 Performed physical modifications to various pipe stoports to g2atify the The modification on various pipe stpports was performed to make sure the supports for the design basis events as required by applicable design pipe stoports were qualified both environmentally and seismically per criteria. These modifications were performed on the following systems: applicable design criteria. The safety function of the associated CCS, CSS, and RPR. mechanical systems was not jeopardized. Since the systems are more reliable, the probability of an occurrence or the consequences of an accident or malfunction of equipment inport ant to safety are reduced. Each arxtificalion was stexerted tsy an individual calculation, and the et fects on misceltartous structures were considered. The margin of safety, as defined in the basis of any T.S., was not reduced.
s Page No. 8 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CfR 50.59 i 1987 NRC ANNUAL OPERATING REPORT i CHANGES IN THE FACILITY - MODIFICAi!ONS DESCRIPTION SAFETY ANALYSIS g
** Ecu - L7157 DCR 2259 This modification replaced the non-qualified AFW discharge pressure gauges Replacing these gauges with seismicatty qualified gauges ensures the with qualified seismic 1 (L) pressure gauges. The pressure gauges involved pressure iomdary integrity of the section of *)ss Af W system where these in the change were 2-PI-3-1228 and 2-PI-3-1328. gauges are connected. The pressure gauges are only used for tocal pressure indication of the AFW pumps discharge. The pr9bability Of an occurrence or the consequences of an accident or malfuction of e93spment were not increased, and the possibility for en $ccident of a different type was not created. The margin of safety, as defined in the basis of any T 5., was 1
not reduced.
** ECW - L7160 DCR 2259 This modification was made to the control logic and circuit wiring of the This modification did not affect the design requirements of the shutdown auxiliary building ventitation and cooting system to eliminate the board room chilters, but enswes their continued operability should the automatic stoney start function of the shutdown board room water chilter circuit located in the Control building fall. This f metional change to package B-e when it is in the backup control mode and isolates att wiring the chitter packages did not inva'.idate any system design requirements as routed to the control building when switches x5-31C-303 and xs-31C-338 are identified in son-DC-v-13.9.3 arvJ rsAR, section 9.4.2.2.4, "shutdown Board in the AUX position. Room Air Conditioning Systems." T.S. 3.4.8 requires these chitters to be operable. This modification ensured the continued operation of these chitters, and no margin of ss.fety was redded.
** ECJ - L7223 DCR 2259 This modification deleted the temperature modulating feature from the tower Deleting the temperatur<f modulating feature f rom the tower compartment conpartment coolers. This :::::dif b et ton :.:22 re w ired for the upgrade of the . cooters wit L maintain adequate flow to the cooters without significantly cooters to safety grade, because tenperature controt valves 2-ICV-67, -54, resiuoing tiew to cthar efety-retatM ecuipment. The probability of an
-92, -100, and 108 are not envirorimentally qualified. The valves have t.ad occurrence or the r,onsequences of an accident or outfunction of equipment power, controtters, and air lines disconnected 'to keep the valves in t% were not increasW, and the possibility for an accident of a dif ferent type
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Dage No. O 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CfR 50.59 1987 WRC ANNUAL OPERATING REPORT CMA'sGES IN THE FACILITY - MODIFICATIONS DESCRIPTION SAFETY ANALYSIS i fully OPEN position. They will maintain this position with the air supply was not created. The margin of safety, as defined in the basis of any removed. T.S., was not reduced.
- EC3 - LT228 DCR This modification added or revised supports on ducting for the tower This modification gailf f ed and upgraded the dJct steports for the tower cagartmen: cooling system (system 30). conpartment cooters to meet seismic Category I rewirements. No safety-related system, component, or structure was adversely affected by this modification. The probability of an occurrence or the consequences of an accident or malfunction were not increased, and the possibility for an accident of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
- ECN - L7231 DCR 2250 The modification replaced vitet battery rooms I, II, III, and tv emhaust The new exhaust f ans are seismicatty qualified and seismicatty steported.
fnns with Class 1E qualified fans. The new fans do not create extra electrice4 toads and do not effect cable aspecity. The probability of an occurrence or the consequences of an accident or malfunction were not increased, and the possibility for an accident of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
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S.MMARY OF ; F A C I._l Y O O CHANGES O O O ' O EMPORARY O A "' E R A T I O N S t O O O O i 1
s OPEN TACFs PREVIOUSLY REPORTED ================================............ ============...= ...--==.....========== ...============= .... G-70-0633-079 0-82-0340-410 0-85-0077-039 1-82-0168-062 1-84-0057-085 2-80-0537-090 2-83-2036-062 C-83-0088-012 0-83-0347-057 0-85-0079-317 1-82-0213-062 1-84-0G65-050 2-81-2298-014 2-83-2047-062 C-80-0089-012 0-83-0349-077 O-85-0090-234 1-82-0214-062 1-84-0081-062 2-81-2341-087 2-83-5057-068 0-81-0297-014 0-83-0366-245 0-86-0005-079 1-82-0240-079 1-84-0107-005 2-81-2342-087 2-84-2004-062 0-01-0328-077 0-83-0375-030 0-86-0019-317 1-82-0242-062 1-85-0063-094 2-81-2343-087 2-84-2008-013-C-01-0429-031 0-83-0400-030 1-80-0152-079 1-82-0266-077 1-85-0064-046 2-81-2344-087 2-84-2016-062-C-81-0458-067 0-83-0411-241 1-80-0576-062 1-82-0339-006 1-85-0066-025 2-81-2564-001 2-84-2039-003' G-81-0465-027 O-84-0007-031 1-80-0625-068 1-82-0341-013 1-85-0067-025 2-81-2565-001 2-84-2046-001 C-81-0529-014 0-84-0084-059 1-81-0215-055 1-82-1001-090 1-85-0070-030 2-81-2566-001 2-85-2009-062 0-82-0127-077 O-84-0101-025 1-81-0467-062 1-83-0007-062 1-85-0684-079 2-81-2581-055 0-82-0130-077 O-84-0103-077 1-82-0062-002 1-83-0026-050 1-85-0085-317 2-81-2607-055 C-82-0229-057 0-84-0110-079 1-82-0103-234 1-83-0367-245 1-85-0088-062 2-82-2039-002 0-82-0258-067 0-85-0022-241 1-82-0107-090 1-84-0001-062 1-85-0091-030 2-82-2050-068-0-82-0275-077 0-85-0040-062 1-82-0140-090 1-84-0039-031 1-85-0092-026 2-82-2077-090 0-82-0315-410 0-85-0073-077 1-82-0154-062 1-84-0052-085 1-86-0006-068 2-83-2022-079 4 e _ _ - . . _ _ _ _ _ m _ __. .. -. Page eso, 1
. 02/22/88 SEQUOTAN NUCLEAR PLANT -
10 CFR 50.59 1987 NRC ANNUAL OPERATlWG REPORT FACILITY CNANGES - TEMPORARY ALTERATIONS DESCliFTIO:: SAFETY Suv4ARY ,
** TACF NUMBER: 0-86-0007-317 Thia change used two spare breakers in the hot shop 480V MCC to provide This alteration is not evaluated in the FSAR and only affects non-CSSC teaporary power for traporary of fice space in the service building. equipment. The probability of an occurrence or the conse<pJences of an accident or malfunction were not increased, and the possibility for an accident or metimction was not created. The margin of safety for this equipment is not defined in the basis of any T.S. ** TACF NunsER: 0-86-0009-317 This etteration added a "Y" connection in fire hose cabinet 0-26-715 to provide This alteration does not affect any CSSC equipment. The probability of an o cooling water source for temporary A/C unit, and added two threadotets to the occurrence or the consequences of an accident or malfunctim were not increased, servics building root and floor drain piping for cooling water discharge. Also, and the possibility for en accident or malfunction of a different type was not c connection was added to the potable water in the laborers' shop for a water created. The margin of safety for this equipment is not defined in the basis of cooter la a temporary of fice, any T.S. ** TACF NLMSER: 01-82-0097-37 This citeration lif ted a wire on accumulator weight indicating switches The accumulator weight indicating switches have been declared defective try 1-WIS-87-21, -22, -23, and -24 to disable the stare irput to annunciators Westinghouse. Defeating the stare input from the system witt not increase the 1 xA-55-6C/27 and 1-aA-55-6A/28. probability of an occurrence or malfunction. This TACF is schedsted to be cleared when work for DCR P-1400 is cceptete. ** 1ACF hum 8EN: 2-86-2014-031 This citerattors removed the RTV foam insulation f rom e $*lrth sleeve between the CNE calculations, SQNAP P53-035 (845 861125 235), ernure environmental 4 Mt side and the sample side of the post accident sanpting f acility. This was . qualification is not affected. The margin of safety, as defined in the basis of cone to etlow increased air flow from the sample t i de ta the hot side of the any T.S., is not reduced. This TACf is scheduled to be cleared post mit 1, post accident sanpting f acility. cycle 3.
b I O O O S.MMARY OF O O P R O C E D;i R E O i O CHANGES O O ABNORMA_ O O O P ER A ING O
/ O lNSTRLC'lONSo O O
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fage "fe. 1 02/22/88 SEcuDTAN NUCLEAR PL ANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPOST CHANGES TO PROCEDURES AS DESCR18E0 IN THE SAR DESCRIPTION SAFETY
SUMMARY
** AOI-003 MALFUNCTION OF REACTOR MAKEUP CONTROL - UNITS 1 AND 2 REV NO. 007 This revision delet-d issnediate actions and combined the three sections for Isenediate actions for dilution accidents are contained in AOI-34. The inadvertent dilution into one section. probability of an occurrence or the consequences of accident or metfmetion were not increased by this rews. ion. The possibitity for an accident of a different type was not created. This revision did not make any T.S.
equipment inoperable.
** A01-004 NUCLEAR INSTRUMENTATION MALFUNCTIONS - UNITS 1 AND 2 REV NO. 009 This revision deleted the insnediate actions of source range monitor failure The deleting of isusediate actions and reformating the instruction did not and combined it with audio comt rate failure. This revision also dr.teted increase tne probability or consequences of an accident or malfunction.
isusediate actions for intermediate range f alture and changed the symptoms The T.S. basis was not affected, and the margin of safety was not reduced. to assume single power range channet failure in the power range failure section.
** AOI.005 UNSCHEDULED REMOVAL OF AN RCP ($) SkLOW P UNIT'. T AND 2 REV No. 010 This revision revised starsvindications to the more probable and & tete's The inusediate operator actions are handled in an emergency instruction.
lausediate operator actions. The procedure was also revised to be The probability of an accident was not increased, and the possibility for consistent with Westinghouse N-7 procedure. an accident of a dif ferent type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
** AOI-006 SMALL REACTOR COOLANT SYSTEM (EAK - UNITS 1 AND 2 REV No. 01T This revision reduced the inmediate operator actions a.nd sygton alarms This change did not have any offeet on the T.S. basis. The probability cf section, and also revised the general format of the irstruction. a** occurrence or the consequences of an accident or metfunction were not increased, and the possibitity of an accident or matfunction of a different
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Page No. 2 02/22/88 SEQUOY AN NUCLE AR PL ANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CMANCES TO PROCEDURES AS DE5*RISED IN THE 5AR DESCRIPTION SAFETY SUMWAY g type was twt created. A01-008 TORNADO WATCN/ WAR 4thG - UNITS 1 AND 2 RCO no. 012 This revision updated the door list and nede it consistent with f5AR, this revision made the proccdure consistent with comunitments in the FSAR. Section 3.8.4. It was also revised to power to tornado dampers per SCR 504 This revision was also consistent with the T.S. In that ECO 3.0.3 is EEB 86136. entered when both trains of control room emergency ventitation :,re made inoperable by closing the tornado despers. This does not increase the probability of an accident or create the possibility for an accident of a different type. REV NO. 013 This revision added 24 fire doors which must be breached for tornado These fire doors are breached per T.S. 3.7.12. The probability for a warning. This is per memo g25 870721019 from DME and CAQR SQF870022. The previously evaluated accident was not increased. The possibility for en rfrision also added a step to ensure automatic-closing fire door A51A is accident of a different type was not created, and the margin of safety, as cren. defined in the basis for any T.S., was not reduced. REV NO. 014 This revision replaced the ERCW strainers automatic backwash with a manual The ERCW system will not be degraded by placing the backwash features of backwash ty utilizing 508-67.1 which describes the manual operation of the the screens aM strainers irt the manual mode. The appropriate procedaral, traveling screens. modification, and dose rate considerations have been addressed and evaluated ensuring that the system integrity is mainteined. The probability of an occurrence or the consequences of an accident or met function were not increased, and the possibility for an accident of a different tyrw was rwit createef. The margin of safety, v. defirwd 6n the ' besis of any T.S., was not reduced. O* A01-009 EAttwouAKE + UNITS 1 AND 2 REW uo. 007 This revision added a step for checking locat seismic atarm panet and a Att of these changes are procedure ethancement changes which did not af fect
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Page Co. 3 02/22/13 1.EQUOTAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERAi!NG REPORT CHANGES TO PROCEDURES AS DESCRISED IN TNE SAR DESCRIPTION SAFEif
SUMMARY
reference to A01-7 and A01-22 in case of a dam break. Also added a step to any T.S. basis. check the ERCW traveling screens.
** AGI-011 LOSS OF CONDENSER VACUUN - UNITS 1 AND 2 REV N% EOS The revision added Westinghouse reconumendation to smenually trip the turbine The main condenser is not included in the T.S. The probability of en ed:en the condenser pressure is >1.7 psia when operating below 30 percent occurrence or the consequences of an accident or metf metion of e wipment power. were not increased, and the possibility of an accident or metfunction of a different type was not created. No margin of safety was reduced. ** A01-0'2 LOSS OF CONTAINMENT INTEGRITY - UNI 15 1 AND 2 #EV NO. 006 This revision redaced the immediate operator action time and changed the The reduction of the lausediate operator action time and changing the formet format of the instruction. of the instruction did not increase the probability or consetynntes of an accident or malfmetion. The toss of containment integrity is not addressed in the FSAR. It is addressed in the T.S. for modes 1 through 4; a one hour action time is attowed. The margin of safety, as defined in the bests of any T.S., was not reduced. ** A01-013 LOSS OF ESSENTI AL RAW COOLING WATER - UNITS 1 AND 2 REV 8s0. 013 This revision redxed issnediate operator actions, cont >ined ptsp trip and The reduction of issuediate operator actions and changing the format of the gassing f at ture sections, and deleted loss of att ERCW pimps and operating instruction did not increase the probability of an occorrence or requirements for various plant site conditions. Also ad$ed Appendia R consequences of an accident or malfunction. The possibility for an valve information. accident of a dif ferent type was not created, and this revision had no affect on the T.S. basis.
t Page No. O 02/22/08 SEQUOTAM NUCLEAR PLANT 10 CFR 50.59 1987 hRC ANNUAL OPERATING REPORT CnAwcES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
** A03-016 LOSS OF NORMAL FEEDWATER - LMITS 1 AND 2 REW WO. 009 This revision reduced issuediate operator actions and added a section for the format changes and the reduction of immediate operator actions did not NFW pump speed malfunction. This also deleted a section for total loss of increase the probability or consequences of are are3 * - 7 *~ . J ws rernet feedwater since it is covered by emergency instructions. previously evaluated in the fSAR. This did not create an accident of a different type and had no offect on any T.S. basis.
- A01-017 TUR8IME AND GENERATOR TRIPS - UNITS 1 AND 2 REW #0. 013 The revision deleted part ITA (turbine trip above P-9), since this is This procedure change is consistent with TSAR handling of turbine trip covered by E-0. Also deleted discussion section and revised part 175 to below P-9; therefore, the probability of the occurrence or consegaences of meintain RM power levet instead of decreasing to approximately two percent. an accident or metfunction of equipment were not increased. This proce &re change did not affect any T.S. basis.
- A01-021.1 LOSS OF 125V DC VITAL SAITERY SOARD I - Outi 1 RED 80. 010 This revision re & ced inumediate operator actions and reconciled the The reduction of issuediate operator actions and removat of the PD chargins !
procedure with emergency instructions. The PD charging pump usage pump reference had no af fect on the probability or consegaences of an ! reference was deleted, and annmciations were corrected. accident or metfunction. The PD charging pump is a nonsafety item, and the change had no adverse affect on any safety system. I I
- i A01-021.2 LOSS OF 125V DC VliAL BATTERY SCARD II - UNIT 1 REV 80. 011 This revision reduced leanediate operator actions and reconcited the The reduction of Inunediate operator actions and removat of the PD charging procedure with the emergency instructions. The charging pump usage pump reference had no af fect on the probahitity or consequences of an reference was deleted, and annunciations were corrected. accident or motfunction. The PD charging pump is a nonsafety ites, and the change had no adverse af fect on arvy safety system.
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Pete No. 5 02/22/88 SEQUOYAN AfuCLEAR PLANT 10 CFR 50.59 1987 mRC AssefuAL OPERATING REPORT CNAeGES TO PROCEDURES AS DESCRIBED IN INE SAR DESCRIPTION 5AFEff
SUMMARY
- AO!-021.3 Loss OF 125W DC VITAL 8411ERY BOARD I!! - U18171 aEU WO. 007 This revision deleted launediate operator actions, corrected annunciations, the deletion of Isanediate operator actions and addition of information had and added a reference to fifth vital battery. to af fect on the probability or consessences of an accident er metfunction.
The tausediate operator actions are now located in the s4segaent actions section, and the margin of safety was not effected. " A01-021.4 Loss OF 125v DC vlTAL SATTERY 80ARD tv - Uu171 REO mo. 007 This revision moved lammediate actions to stbsessent actions section and The relocation of isumediate actionc had no af fact on the probability or corrected the annwiciations. consequences of an accident or malfunction. Ito unanatyred condition esas intro Asce6 and the margin of safety asas not af fected. " A08-021.5 Loss of 125V DC v!TAL SATTERT SOARD I - UNIT 2 REW WO. 905 This revision moved laumediate actions to subsegaent actions sections and the relocation of issuediate actions had no ef fect on the probability or corrected the armunciations. consegaences of an accident or malfunction. Ito unanatyred condition esas introduced, and the margin of safety esas not ef fected. " A01-021.6 Loss OF 125V DC VITAL BATTERT BOARD II UNIT 2 aEV uO. 006 This revision smoved issuediate acticns to subsessent actions section ard The relocation of isumediate actions had no af fect en the probab;tity or corrected the annwiciations, corweguences of an accident or malfunction. too unanatyred condition naas introduced, and the margin of safety esas not af fected. __.-. _-.-- _- ~.- . . ~ . . _ = _ _ _ _ . . . . - _ - _ - . .. . _ .. . - _ - 2 _. . ~ . ~ , Omge No. 6 02/22/88 SEQUDYAN NUCLEAR PLAuf 10 CFR 50.59 1967 mRC AaNUAL OPERAllhG REPORT CHAmGES TO PROCEDURE *. AS DESCR!gED IN TE SAR DESCRIPTION SAFETY
SUMMARY
AOf-021.7 LOSS Of 125V DC VITAL BATTERT SOARD Ill - UNIT 2 aEV 50, 007 This revision corrected arviunciations aruf deleted the PD charging pmp This revision did not increase the proc Wility of an accident or reference. metfunction previously evaluated in the 75AR. The PO charging gesp is a nonsafety ites, and the mergin of safety was not ef fected. Act-021.8 Loss OF 125v DC VITAL sATTERY sonRD IV - Unif 2 NEW WO. 007 This revision corrected annmciations and deleted the P0 charging pump This revision did not increase the probability of an accident er reference, malfunction previously evatusted in the FSAR. The PD charging pimp is a nonsafety ites, and the margin of safety was not of facted.
" A03-022 GREAst OF DouwstREAft DAst - UNITS 1 AND 2 aEV to. 006 This revision redaced tausediate operator actions and was a general revision the formet changes and the reduction of immediate operator actions did not ,
of the forimet. Increase the probability or consequences of an accident or motfunction previously evaluated in the f5AR. The possibility for an accident of a different type was not created, and the change did not affect any T.S. basis. atW NO. 007 This revisien added step E for menuet operation of ERCW screens and there are no specific design regairements iAlch specif y that the automatic strainers, feature for bec6 washing be in service or that manuet backwash is preferred over automatic or vice verse. ONE calculation (s44 870918 011) provided graphs of flow versus pressure drop for clogging of the strainers and indicated when bec6 washing should be implemented to cican the strainers. The calculation also establishet that the continuous backwash feature of the strainers could be placed in service without degrading the ERCW system er f tow reepsirements, samt en the tafety evatwt son, etw probdiitity of
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02/32/88 [ SEQUOYAsl muCLEAR PLANT 10 CFR 50.59 1987 eseC AmmuAl cPERAf teG REPoni CleAeGES 10 PROCEDURES AS DESCRISED IN TIIE SAR , c J
)
DESCRIPTION 5AFETY SuletARY g l occurrence or the consequences of an accident or malftmetion of equipment mere ret increased. The possibility of an accident er malfunction of a ; , ditferent type than those previously evolust.ed uns not creeted. The mergin ; of safety, as defined in the basis of any T.S., mes not redaced. J
** A01-023 REACTOR C00LAmi PtseP SEAg asunesentitlES - UNITS 1 AND 2 WEW NO. 006 This revislan deleted lammediate operator actions and deleted section 5 Seat abnormatities prior to gamp starte are' to be encluded in 508-68.2.
(seet abnormatities prior ta samp starte). These changes did not increase the prehability of an occurrence er consegaences of an accident or malfuncteen previously evetusted in the , f5AR. These changes did not create the possibility for en occident er -
! malfunction of a different type. AOI-23 does not effect any I.S. basis. " A01-026 Sifase steEmaTOR TueE LEAK - UNITS 1 Amp 2 REW up. 006 This revision reesced isusediate operator actions, revised the procesare to The reduction of lemudiate operator actions and the generet revisien to the '
be consistent with E-3, and transitioned to ES-3.2 for coot down. mot did not increase the pr.hability of an occurrence er cenoegssaces of en accident or metfuction previously evetuated in the isAR. The possibility for a dif ferent type accident asas not creeted, and the change had rae effect on any T.S. basis.
" a01-Q5.2 toss Of 120v AC VITAL ItsfeusetNT Powta 80A401-II - UNIT 1 .
MEW 80. 005 This revision streamlined operator actions and deleted an,endices A and s. seoving imamediate operator actions to seesequent operator actions section and deleting appendices A and 5 did not increase the probability of an . occurrence ce the consegaences of an accident. Immediate operator actions ete not of an urgent nature. A new Appendia A, Moed List," mes pieced in the instructici. The possibility of en accident of a dif ferent type esas E t t
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It Pege me. 8 02/22186 SEQUOTAN NUCLEAR PLANT 10 Cf R 50.59 1957 hec AmuuAt OPERATIWG RtPORT CNANGES TO PROCEDURES AS DESCRIBED IN THE $AR i D($CRIPTION SAFEff SUPE 4ARY g not creataf, and the mergin of safety es defica.4 in the tassie of any T.S. was ret redxed. AO!-025.3 Loss of 120V AC vITAt IusiRUMENT P0btt 80ARD 1-1II - UNIi 1 REV WO. 005 This revision streamlined operator actim aruf deteted appendices A ard 8. fooving imunediate operator actions to subsequent operator actions and the l deletion of appendices A and 5 did not increase the probability of an l cccurrence or the consegarnces of an occident er motf metien. Iammediate I operator actions are not of an urgent nature. A new Appendia A, "Lead j List," was ptoced in the instruction. The possibility for en accident of a j dif ferent type was not created, and the outsin of safety, as defined in the basis of any T.S., was not redxed. l , ** ACI-025.5 LO55 0F 120V AC VITAL lesfeuntui Powit 30Aa0 2-1 + uut!,2 REW WO. 006 This revielen streaudined operator actions and deleted appetefices A and B. fioving issuediate operator actions to the subsegeent operater action section eruf deleting appendices A and 8 did not increose the prebebility of an occurrence or the consequences of an accident or selfection. Isamediate operator actions are not of an urgent noture. A new Appendia A,' atead List," was placal in the instruction. The possibility for en accident of a dif ferent type was not created, and the mergin of safety, as defined in the basis of any T.S., was not reduced.
** A01-025.7 Loss OF 120V AC Insf auntui P0ute soAa0 2-111
- tju!T 2
, mEO =0. 004 This revision streandined operator actions and det<teci erroneous ess;endices The actions performed on safety egeisment were unchanged. The probability A and S. of an accident was wt increased, arus the possibility for an accident of a different type was not c*eated. The margin of safety, as defined in the 1 1
; - ,y.
vw -.,w..n~.n.- , . . . , - . - , . . . . - . . .-,-n ..n-,- - ., ,.,-n~- n ,, ,,, ,,., ,n-e. ,,r,, - -,,, , , , . . , ...,ww- , ,, , . - - - - - ., ,-n ---,e , - , , - r - , ,
Page No. 9 02/22/88 SEQUOYAN NUCLEAR PtANT 10 CFR 50.59 1987 het AteesuAL OPERATIWG REPORT CMANGES TO PROCEDURES AS DESCRIBE 0 IN THE SAR DESCRIPfloss SAFEIT $UMMARY , basis of any T.S., was not reduced.
** A01-075.8 LOS5 OF 120V AC VITAL INSTRUMENT POWER 80ARD 2-IV - tmli 2 NEO so. 006 This revision streamtirrd the operator actions and deleted anendeces A and Moving isenediate operator actions to the sikasegaent operator actions
- s. section did not increase the probability of an occurrence o.- the consegaences of an accident. Ismediate operator actions are not of an urgent nature. The new appendia A, mich contains the I.B. atares and indicators, is suf ficient to identify malfunctions to the operator. The possibility for an accident of a different type wee not created, and the mergin of safety, as defined in the basis of any T.5., was not redaced.
AOI-028 (UEL CA00lmG FAILtmE OR MIGN ACTIVITY IN REACTOR COOLANT - UNils 1 AND 2 REO so. 001 This revision reduced immediate operatoe actions and conR>ined Sections A The format chnoges and the reduction of launediate operator actions did not and e into one section. increase the probability or consequences of an accident er entfunction previously evaluated in the F5AR. The possibility for en accident of a different type was not created, and the change did not affect any T.S. basis.
** A01-029 DROPPED OR DAMAGED FUEL ASSEMBLY OR REFUELING CAVITY SEAL FAILURE - (mlis 1 Ato 2 REV esO. 003 The format was revised for human f actors, redaced isonediate operator This revision was written to handle an accident. The probability of an actions, and revised organtrational name changes. The revision added a accident was not increased and the possibility for an accident or ref erence to Scl-30.5E for verification of an aualliary building isolation, malfunction of a different type was not created. These changes do not affect any T.S. basis.
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_ .- m m-.-. 2 ..._ _ m . . - - . m -- . _ . _. . ._ . .m-. . _ . - . . . . ._. _ . . . _ --_.m_ _ l Page me. 10 C2/22/88 SEQLOYAN NUCLEAt PtANT 10 CfR 50.59 1987 mRC ANNUAL OPERATING REPORT CnAmGES TO PROCEDURES C DESCRIBED IN TNE SAR 1 i l l DESCRIPTION SAFETY
SUMMARY
, i l l l ** AOI-C30 PLANT flRE - UNITS 1 Aa0 2 BEW WO. 005 This revision etexed issuediate operate actions and clarified poss6ble The operator actions are essentially e changed. The streaatining of the alarms, procedure had to etfcct on the probability or consegmences of an accident or matfmction. The margin of safety, as defined in the basis of any T.S., teas fsot reduced. l
** AOI-C31 Atm0RnAL RELEASE t# DADf 0 ACTIVE MTER$ ALS - UNITS e .'.'.S 2 l
AEV ko. 004 This revision reduced the syevstoms section cir3 the asemedlete operates This asas tnsicatty a procedse format revision. the changes did not actions section. - A veneret revision to the automatic ections and the increase the probability of an occurrence or the consegmences of an esesequent action sections seas made. accident or metfunction. The possibility for an accident or motf action of a dif ferent type esas not created, and the change did not af fect any T.S. basis.
** A01 033 Cut 0R!aE RELEASE - UNITS 1 AMD 2 aEW NO. 002 This revision radaed the imrediate operatce actiare section and clarified This irntruction handtes an abnormat event as anstyzed in the ESAR. The the chlorine instrument setpoir.t. A general rew?sica to the fermat of the changes made did not increase the probability of an occurrence or the instruction ses mode, comgaences of an accident or malfunction. The possibility for an accident of a dif f erent type esas not created, and the changes had no af fect on any T.S.
** A01-0% EntRGEaCY ElR4T10N - souTS 1 AND 2 aEW N0. CD2 This revision reduced the uncontrot ted lecrease in rrector power as Redxing the urtontrotted increase in nuclear power as indicated by nuclear irdicsted bw texteer instrurnentetion and redxed inswdiste operator instrumentation and reducing insnediate operator actions did not increase actions T' a e section f or local boration Mich i t, not used) w.1 the the probabit 6ty or consequences of an accident. Local boration is not l
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Page No. 11 02/22/CS SEQUOYAN NUCLEAR PLANT l l 10 CFR 50.59 1987 ERC ANuuAL OPERATING REPORT CMANCES to PROCEDIRES AS DESCRIBE 0164 TME SAR l l LESCRIPTIOlt SATETY
SUMMARY
l section for boron injection tank 'njection (which is reserved for ECCs/ATWS mentioned in the FSAR and may be deleted without affecting the FSAR. This ! conditions) were deleted. Act contains steps for checking the T.5. timits, and the margin of rifety was not redred. 9
1 i 1 i i )
! O O
! O O O
SUMMARY
OF . PROCEDURE O O CHANGES O O O O EMERGENCY O INSTRUCTIONS O O O Of , f
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l l Page to. 1 02/22/86 SEQUOTAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC A440AL OrfRATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN TME SAR DESCRIPi!ON SAFETY SUMesARY g
** E-0 mEACTOR TRIP 04 SAFE 1Y INJECTION REW Wo. 002 This revision added step 17 to check ERCW operation. This step esas The EaCW screen wash system, as modified ty TACT 82-258-67, is capetde of rewired to fulfitt the requirements of the DNE L1500 for TACT 82-258-76 seeting the regstrements of the ERCW system. The TACF requires the system (825 870613 501). This TACF esas implemented to remove the "Loss of signal" to be operated le the manual mode, editch is acceptable, provided the to automaticatty start the esash pump and screens and to stop their special requirements recommended by NES are implemented. The probability r continuous operation caused by the f ailure of the tewet instrumentation. of an occurrence or the consequences of an accident or malfunction of Other changes incorporated were procedural enhancements. ogsipment esere not increased.
Tesuporary deletion of the automatic foeture for starting the acreen and unsh system has no ef fect on system performance or operator action daring toss of offsite posser. With the special requirements laptemented, toss of arneciation of dif ferential pressure across the screen for operator information is not essential. An accident of a dif ferent type esas not created by the TACF. - TACF 82-258-67 does not affect the mergin t,f safety, because the basis for j the T.S. esas not reduced. l
** E-2 STEAM GregeATOR TusE RUPTutt l
j pfv m0. 001 This revision provided enhancements to the procedJre to assist the coerator These enhancements do not increase the occurrence or the consequences of an in determining a faulted steam generator and other guidance. accident or metfunction of egaipment evaluated in the FSAR. They do not ' create an accident or metfunction of a dif ferent type than previously , evaluated. This change did not affect any I.S. basis; therefore, the i margin of safety esas not redaced. I i j i
s Pope me. 2 02/22/86 SEQUOYAN NUCLEAR PtA4T 10 Ctt 50.59 1987 N#C AmuuAL OPERAT!bG REPORf CnA4GES 10 P90GDURES A5 DEscalpED In fpE SAR DESCRIPfl04 SAFETT
SUMMARY
** ES-1.2 TRAesfER To one CONTAlWMENT $ UMP
#EW DD. 003 This revision changed the conteirveent sump oute swepower setpoint from 10 The procedure was revised to egree with rww auto swapower setpoint. The percent to 11.25 percent levet to comply with the new bistable setpoint, probability of an occurrence or the consequences of an accident were not increased, and the possibility for en accident of a type different from that prewicusly evetuated was not created. The mergin of safety, es defined in the basis of any T.S., was not reduced.
t 4
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SUMMARY
OF
- O PROCEDURE O
/ O CHANGES O i O O O
SURVEILL ANCE O I N S.T R U C T I O N S O O O O,
s Page so, 1 02/22/88 SEQUOTAN NUCLEAR PLANT 10 CfR 50.59 1987 mec Ammust OPERATIwG aEPORT CMA#GES TO PROCEDURES AS DESCRISED IN THE 5AR DESCRIPT104 SAFEff SLMMARY ,
** 58-C31 SuevtittAuct PeoGaAst
- tmstis 1 Amo 2 MEW a0. 019 This revision added the requirement, in accord.ence with apOAM, Part II, this change did not af fect ghysical plant configuration. It provided a Section 4.9, f or D#E to review att unresolved test deficiencies and more accountable method of reviewing amresolved test deficiencies. The laptemented the reqJeremente of h0480, Part I, $cction 2.16 (9'IS 861215 A s.or6tmt of 6prCilic Mas araj $lb eseh ent af fected tsy thin charspe, and 8701190). Therefore, the probabitsty of an accident or malfunction of plant equigment was not increased, nor did it create any dif ferent type of accident.
secame the content of the T.s. was es,t charpf, the omrein of safety wee ret redxed. 4
** C8-002 58ilvi LOG
- L801151 A40 2 mEV 20. 041 This revision deleted references to figure 3.1.2 eAlch no longer esists in the changes to incorrect figure reference and administration had no adverse the T.S. It also included correction to verlous data units and T.S. timits af fect on equipment or safety. The correction did not increase the and deleted 2TT51A, 5, and C relays from degraded vontage reter operability perAmsbility of an accident or outfisiction, nor did it create any of a verification, different type. The correction awje in this revision has no impact en safety; theref ore, the snargin of safety was ret redued.
mE7 to, 042 This revis;en added a e ,me* (3.21.1) to the instructions for Clarifice-lon of rctes and inforsetion about cottecting data neither clarification, ar.*ad a number n the note section of the data sheet e. Sere increased the probability of an accident or metfunction, nor created a
- nore than one instrassent can te used, added gonc4 runders on several 6 tem de f ferent type of ecodent. Ihese clarifications did ret reduce the sursin to pinpoint location, corrected identification of Contairement Preswre of safety.
Plant Operating lastrtxtions, eruj contaleted inf ormation to note 12.
** $1 003 DAILY, WEELY, Au0 NONTMLY LOG 5 - tmITS 0,1, AND 2
#EV aO. 052 This revision changed vitet battery V distritotieri penets A and 8 frone Mhirq the procedure agree w6th plant configuration in to way increased the circuit brea6er 1 and circuit breaker 2 to circuit breakers 104, M,106, probability of an accident or matissiction of ensipment, nor did it create a
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - . _ ~ _ _ _ _ _ . - _ . _ _ _ . - _ . _ _ _ _ _ . _ . . _ _ . __ _ _ _ .
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Pope me. 2 02/22/88 SEQUOTAN NUCLEAR PLAuf 10 CFR 50.59 l 1967 mRC ANWJAL OPERAYIWG REPORT l CnANGES TO PROCEDURES As DESCRIBED IN TME 5AR , 1 l DESCRIPTION SAFETT SupmARY g and 107. These breakers were retabeled by way of a worit request to conform dif ferent type of accident or metfunction. Since the tograde in the with print 45a703-5-1 (RO). The procedure cAange reflects this ptar t procedure did not adversety af fect plant safety, the mergin of safety was . configuration change. not degraded in any menner. SI-006.1 CouTAltrEuf SUILDING VENTitAf f 04 Isot Allou (100 m/T DAt) - Uutts 1 AuD 2
#EO NO. 005 This revision deleted at t tiquid-fitled and closed-loop system valves from Only the valves, hatches, doors, etc., whic.h provide direct access from the the St. containment atmosphere to the outside atmosphere are regaired to be checked. The probability of an accident was not increesed, and the possibility for an accident of a different type was not created. The margin of safety, es defined in the basis of any T.S., ues not reeJced. " $I-007 ELECTRICAL PCWER SYSTEM: DIESEL GENERATORS + tJNIT 0 REV WO. 03T This revision added port 6.3 to the instruction body, added e note to Clarification of this instruction of edun to collect < eta ensures further clarify edwn Date sheet 3 is to be performed, and addad blanks to ensure compliance with safety analysis. This clarification did not increase the both engine perameters are checked. probability for an accident or metfunction, nor create a dif ferent type of accident or metfunction. This revision did nnt atter the mergia of safety as defined; therefore, it was not reduced in any menner. #EO No. 038 This revision was prompted by T.s. Change 107. TSis changed the testing The changes to the instruction clarified the scope, implemented T.S.
frequency and gave ellowance for less frequent ambient starts, added changes, and did not offect the actual performance of the test. Therefore, signof f s for togging starting and loading times, corrected references (D89ts the probability or consequences of an accident or malfunction were not have tseen Superseded by techn6 cal standards), added a note desting with increased, and the mergin of safety, as defined, was not af fected by the emergency stops and/or relay actuations, and corrected Data Package Cover changes. sheet in accordance with $1-1.
#EO #0. 039 This revision added a signof f for verif ying that MVARs are within range The s,ctual scope and intent of the instruction was not changed. Because of
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Page so. 3 02/22/88 SEQUOTAN MUCLEAR PLANT 10 CfR 50.59 1987 NRC ANNUAL OPERAi!NG REPORT CNANGES TO PROCEDURES A5 DESCRigED IN THE SAR DESCR!ri!04 SAFETY SIMt4RY , (.75 to 2.38). This change is due to the removat of the enc' er voltage the modification, the procedure esos revised to ensure correct performance regulator min-man module. Added D/G capability curves as r* reves. ty the operator. The possibility of an accident or ogsipment matfmetion was actually decreased ty ensuring fewARs esere within the acceptable range of the reitity curve. The mergin of safety, as defined in the basis of any T.S., esos not reduced. 8EO NO, 040 This revision was made to change approniente numbers to a range for several The scope and intent of the proce&re esere not altered. The prebebility of parameters and added minisuse and emaimaan rameers to several items on ee an accident was not increased, and the possibility for an accident of e D/G risining condition checklist, dif ferent type teos not created. This revision did not re & ce any mergin of safety as defined in the basis of any T.S. DEW 40. 041 This revision 6ses made to increase the D/G continuous and 2-hour load The new limits are based on DuE calculation SON-53-002, "Dieset Generator ratings to comply with a T.S. change. This revision increased the 0/G toad Analysis." These new limits do not emceed the D/G capability curves. toeding f rom 4000kW to 4400kW ard from 2000kW, when both smits are in sedes The probability of an accident was not increesad, and the possibility for 5 or 6, to 2200ku.
~
an accident of a different type was not created. The mergin of safety, as described in T.S. 3.8.1.1 and 3.8.1.2, esos not reduced.'
~ SI-007.1 DIESEL GENERATOR AC ELECTRICAL POWER SOURCE OPERAg!LITY VERIFICAllou (DIESE8. GENERATOR /0FFSITE SOURCE) - Unli 0 REW NO. 010 This revision added a note to state when ambient starts are required, This revision clarified Jwn adlent starts esere regsired and .m.ne signoff clorified note emplaining enhen to stop the stopwatch for the 10 seconds, for recording time. This did not af fect the probability of an accident er.
and added space to record the actunt time of each start, the consequences of accidents or antissictions. This revision did not alter any T.5.; therefore, the mergin of safety esos not reduced.
** St+007.2 DIESEL GENERATOR SURVE!LLANCE FREQUENCY + Unit 0 REW to,003 This revision deleted superfluous information from the scope, added a data All of the changes to this instruction, other than 1.5, and acceptance sheet for recording troperables and added several more lines f or criteria changes, escre of an administrative nature. The T.S. change 4 + - - _ - _ _ - - _ - _ - - - __ _ - _ _ _ . - - - - ._ .,e - , - - -, - .e - -,e -
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l l Page No. 4 i 02/25/88 SEQUOTAN WuttEAR PLANT 10 C*R 50.59 198; mRC AN%At OPERAf tNG REPORT CMANGES 10 PRottDUtts AS DESCRIBE 0 IN THE SAR DESCR!PTION SAfEif $UMMART i performers' signatures. The data sheets were siaptified, and new emasple involved the testing f regaency based on the rumber of f altures per valid tables were made. The title of Attachment S was changed to "Definitions" tests (20 test and 100 test windows). The rusber of tests ard f attures is and acHressed f.S. change which changed acceptance criteria. now determined on a per D/G unit basis instesd of a per reaclear mit basis. This revision also contained provisions for declaring the D\G inoperable and bRC reporting regairemrnts. The changes did not affect the mergin of safety or increase the prchability of an accident. 31-007.3 DIE 5U GEWERATOR FUEL O!L TRAN5fER PUMP PER80RMAltCE TEST - UNIT 0
#EV WO. 000 This instruction was written to estabtish a guidet tne for measurement of the test methods remain the same as when they were performed in $1-7 The each D/G fuel oit transfer psp flow rate and vibration sumitoring. This probabitity of an ocen rence or the cornegaences of an accident or instruction was previously incorrerated in :t-7. 51-7.3 will now stand malfunction were not increased. The possibility for an accident of a stone, different type was not created, and the margin of safety, as defined ir. the basis of any T.S., was not rei1Jced.
aty ho. 001 This revisir* sdded a note stating that the fuel et t transf er psp shall Operation of the fuel oil transfer gxsup 5 minutes before taking data is an run 5 minutes before performance data is taken and corrected a trarnposed ASME requirement and does not af fect the margin of safety or increase the vetve nurter (0-LI-18-7613). probability of an occurrence or the consegaences of an accident or matfunction of equipment important to safety. rorrection of transposed valve ramiber has no aspect related to safety. Cl-003 BORIC ACID i!ali PATNS - TEMPERATURE VERIf! CATION - ifMITS 1 AND 2 Rt? WO. 009 This revision charged the title page to reflect unit 1 ard unit 2, added This revision conplies with $1-1, Appendia f. It was administrative in sto approvst of test, and corrected typographicel errors. nature and did not increase the probability of an accident or estfmc*lon and did not create an accident of a dif ferent type. There was no safety
=
margin degradation realtred ty administrative c.hanges in this instruction revision.
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Page No. 5 - 02/22/88 SEQUOYAH NUCLEAR Pt*1T . 10 CFR 50.59 ' . I' 37 NRC ANNL'AL '1PERAT! hts PrMT C E EC TO PROCEDURCS AS DESCRI% 6 IN T"E. SAR
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REV No, 021 d.is instruction has been revised to'l'dentify phass } W containment vent This revision in no way increased the probability of an accident or .> isolation handswitches by use of p'r oper equipment idenssitT-"- nLabers ~ malfunct i9, rOr did it C W 2 a differe9t type of accident. Since the SI
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andtocorrectborculujectiontankrecirculationvalve(,,ETQfication. scope, ir- and T.S. remairtfbe ar[$erarginofsafetywasnot ' reduced.
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** C!-014.2 VERlef"ATION M CONTA!NME!!i INTE%tITY - UNIT 2 . -1 REV No. 014 This (esision ses made to ihtude att vents and drQ h4en a3 L This rev6sion brought the instruction in d futt c.1spliance with LCD 3.6.1, cone feret soWic9 valv s with e the exceptim ef a.3in steam, AFW, MFW and SON T.S., and NRC's T.S. interpretatirm 3/AS.1 cyter* Decedier 12, 1986.
ECCS srtein15. There was no change in plant configurac9n M ber4rming thirJ:
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instruction;theprobabilityofanaccidentwaffct, increasp Mc;the f ,
- g possibitity of an accident or matfunction was nrC ereat,ec WJjansno ,
_,- .; , reduction in the margin of safety, as defined in 1 fg-js of any y t/ c' ff ~-
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** SI-0U EMERGUCY CCO t;00 LING SYSTEM RNR L' N _ -JCf! SOLATION - UNITS 1 AND 2 .w - - . --
REV NO.'0" *r.t. reu sion et c fitd 4 the SR, char.: 1 not(fication from SE to SRO, and The h uiston complies wite,s St-1, Appendix W and did not attef anf_.T.S. or-desir..eted W stcp signoff at what'o.4 43 r' the valves actually close. theintentoftheinstrteckton. Therefore; % Drobabi!!!y of N M dent'
- T 'or pasfunction wr* 7t increased,' and t*Q argin of safety was not reduced. '
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** SI-016 BIT NEAT TRACING - UN!!S 1 Ami. i[- ,
REV NO. 008 This revision changed step 6.1.1 ? :ontrot panelCchanged to "conttal 4 'gv _ ion did p t a(ter any T.S. and did not change the intent or-thermostat"), included the m rpose of ?tarm in step o.1.3. sitered t'OtJ 7 " g ' Ist.f't of 1 e insitysy ion. .Therefore, the margin of safety remains to include verification of burned o' t u;ight as requeste<* in step 6.1.3, and'- unchar.Ced.}yd r as no insrease in the probability of an accident or
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Page No. 6 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFM 50.59
- 1987 etRC K CAL OPERATING REPORT CHA M S TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION 6 SAFETY
SUMMARY
g changed title of instruction to accurately reflect the intent of new talit malfunction. addition SIT heat tracing and SIT strip heaters.
** St-017 CONTAINMENT SHIELD BUILDING EMERGENCY CAS TREATMENT SYSTEM FLOW - UNITS 1 AND 2 REV No. 019 This revision added adninistrative signof f to data sheet, SRO approvat of This revision conplies with SI-1, Appendix F. These adninistrative changes -
test performance, clarification of SR, and corrected numerous typographical and enhancements did not increase the probability of an accident or errors. malfunction and did not reduce the margin of safety.
** SI-019 CONTAINMENT SYSTEMS DIVIDER BARRIER, REMOVA8LE CUR 85, PERSONNEL ACCESS DOOR AND EQUIPMENT HATCHES - UNITS 1 AND 2 REW No. 010 This revision changed the organizational name f rom QA to OE&C on Data This revision conpties with SI-1, Appendix F, and was administrative in Package Cover Sheet, changed SE to SRO, and identified data sheet to match nature. This did not reduce the margin of safety and did not increase the-instruction. probability of an accident or malfunction of plant equipment.
SI 021 AUXILIARY SUILDING CAS TREATMENT SYSTEM - UNITS 1 AND 2 REV NO. 018 This revision changed unit designation to -0 , added SRO approvat prior to This revision in no way affects the intent or results of this procedure. testing, added Nuclear Reliability Data System technician signof f for There was no increase in the probability of an accident or metfLaiction due Qualified Maintenance Data System purposes, added instrunent identification to these changes, and the margin of safety w3s not re &ced. on hour meters for each. fan, and corrected various typographical errors. SI-026.1A LOSS OF OFFSITE POWER WITH SAFETY INJECTION - D/C 1A-A CONTAINMENT ISOLATION TEST - UNIT 0 . REV No. 013 This revision added ERCW purp load sequence verification and added a load This revision ensured the ERCW punps and alternate feeder are property - shed test of the alternate supply breaker to the shutdown board. tested. This decreased the probability of an accident or malfunction of equipment. The possibility for en accident of a different type was not created, and the margin of safety, as defined in the basis of any T.S., was 4
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Page No. 7 02/22/88 - SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
p not reduced. SI-026.2A LOSS OF OFFSITE POWER WITN SAFETY INJECTION - D/G'2A-A CONTAINMENT ISOLATION TEST - UNIT 0 REV NO. 014 This revision upgraded the procedure to reflect T.S. changes, additional The testing of previously untested equipment does not increase the SRs, CATS items, WP additions, PRO /LER, and corrected nunerous probability or consequences of an accident. The upgrade reflects the typographical errors throughout the instruction. current T.S., and property reflecting the SRs does not degrade any safety function nor create any new accident or malfunction.
- SI-327 RHR LOOP FLOW RATE - UNITS 1 AND 2 CEV No. 008 This revision changed notification from SE to SRO, CA to CEEC, clarified This revision did not increase the probability of an accident or the data sheet regarding acceptable flow rate, and what to add for. 2 toop malfunction and did not create any different type of occurrence. Making the operation, and corrected various typographical errors. procedure conpty with 51-1, Appendix F, did not alter the T.S. and did not reduce the margin of safety in any manner.
SI-032 COMPONENT C00LIhG WATER VALVES (POSITION VERIFICATION) - UNITS 1 AND 2 REV HO. 017 This revision corrected valve identification nunbers. Correction of valve identification raabers enhanced safety, created no new accident or malfunction, and did not increase the probability of an accident or matfunction. Correcting the valve identification nunbers did not reduce the margin of safety in any way. REV No. 020 This revision added position checks of throttled valves servicing safety PositioningtheECSthrottlevalvesatarequiredpositionor.asetnumber ecpipment or af fecting safety equipment flows. of turns f rom futt open ensures the minimum required flow rates to safety-related equipment during the most LCO. The only flow rates different from those analyzed in the FSAR are the minimum flow requirements to the CSP which have been revised f rom 6 gpa to 5.3 gpm, and flow rates to
Page No. 8 02/25/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR l l DESCRIPTION SAFETY
SUMMARY
I xmsafety-related equipment. Changing the C:iP cooling water flow will not I prevent the pm p from performing its safety function. None of the other l revise <t flow rates affect safety-related equipment or equipment used to l mitigate the effects of an accident. l l
** SI-033 ERCW VALVES SERVICING SAFETY RELATED EQUIPMENT (COMMON) - UNIT 0
, REV No. 022 This revision added references, stated prerequisites, changed notification Clarification of the procedure and notificati m changes to comply with f rom SE and SRO, CA to QESC, and designated dotbte verification on SI-1, Appendix F, guidelines in no way reduceil the margin of safety and did signoffs. not increase the probability of an accident or malfunction of plant equipment. i SI-033.1 ERCW VALVES SERVICING SAFETY RELATED EQUIPMENT (UNIT) - UNITS 1 AND 2 ! REV NO. 006 This revision corrected procedure titles, mode operability requirement, Correctly identifying a procedure and grouping valves together correctly in j added prints to references, changed notification frun SE to SRO, put A no way af fect the probability of an accident or malftnction and do not train valve on A train list and put B train valve on B train list, create any type of different occurrence. The clarification of the corrected various typographical errors. Instruction does not alter any T.S.; therefore, the margin of safety was not reduced. ! REV No. 007 This revision deleted the terrperature control vatves from the St, because The deletion of non-CSSC valves did not increase the probability of an they are not CSSC equipment, and the physical construction of the valves occurrence or the consequences of an accident. The possibility for an makes it impossible to determine their operability by visual inspection. It accident of a different type than previously evaluated was not created. also deleted one vatve which does not exist and provided a note for one. The margin of safety, as defined in the basis of any T.S., was not redaced. valve which exists on unit 2 only. REV NO. O' 8 This revision added a note to clarify'the intent of the instruction, The clarification made in the' revision ensures att valves are properly clarified what to do for a "throttleo" valve, clarified footnotes, and- verified. The scope and intent of the instruction are clarified with the l ( l !
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Page No. 9 02/2218S SEQUOYAM NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIDED IN THE SAR DESCRIPTION SAFETY EUMMARY g added a position for four valves. notes and valve positions added. These changes did not increase the probability of an eccident and did not reduce the margin of safety, because the T.S. and acceptance criteria remained unchanged.
** SI-034 CONTAINMENT SPRAY SYSTEM VALVE POSITION VERIFICATION - UNITS 1 AND 2 REV NO. 008 This revision changed notification from SE to SRO, OA and OE&C, and deleted Changes in notification and clarification of the entire instruction in no references to flow diograms. way increased the probability of an accident or malfunction and did not-create a different type of accident. Clarification and chance in notification requirements did not alter any T.S.; therefore, the margin of safety was not reduced.
** SI-036 VERIFICATION OF 100 HOURS OF SUBCRITICALITY - UNITS 1 AND 2 REV NO. 003 This revision removed instructions from the data sheets and incorporated The procedural change was made to meet administrative recp!;ements.
them into the body of the test. Also, it added a reference section and Instruction steps were removed from data sheet and % eced in the body of updated Data Package Cover Sheet in accordance with 51-1. the test. This change did not increase the probability of an accident or malfunction, nor was the margin of safety decreased.
** SI-038 SMUT 00WN MARGIN - UNITS 1 AND 2 REV No. 021 This revision corrected an error in step 5 of Data Sheet 5 wh6ch indicated Correcting an error in the data sheet to indicate a correct data source and an incorrect source of data, correcting the methodology to obtain accurate data did not increase the probabliity of an occurrence, nor create the possibility for a different type of accident or untfunction. Since correcting on error in the methodology did not alter any T.S., the margin of safety was not reducCf.
D Page No. 10 02/25/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
I
** SI-040 CENTRIFUGAL CHARGING PUMP - UNITS 1 AND 2 REV No. 036 This revision corrected inadequacies and added enhancements. It was This method of testing requires the opposite train to be operable and revised to mate part C a separate instruction. Part C has a frequency of in-service, supplying charging and seat flow, and the punp being tested to 31 days, and the pwp test f requency is quarterly. It was also revised to be on recirculation ftow. This allows more positive control of the pump test the pump on minif tow onty, instead of miniflow plus seat / charging being tested, allows a more accurate flow measurement, fulfills T.S.
flow, to attow a more accurate flow measurement. 4.5.2.F.1 (which states that on recirculation f tow, the punp will develop a discharge pressure of greater than or equal to 2400 psig), and attows testing or one train without affecting the other train. Flow will be measured as required by ASME, Section XI.
** SI-040.1 CENTRIFUGAL CHARGING PUMP CASING AND DISCHARGE PIPING VENTING PROCEDURE - UNITS 1 AND 2 -
REV NO. 000 This new instruction incorporated att the requirements of St-40, Part C, The methodology incorporated into this SI is the same as that described into 51-40.1. Acceptance criteria and action to be taken if not met were previously in SI-40, Part C. The addition of acceptance criteria and added, and a valve runber was corrected. correction of a valve nunber had rio af feet on the margin of safety.
** SI-045.4 ESSENTI AL RAW COOLING WATER PUMP M UNIT 0 REV No. 000 This instruction was written in two parts for the testine of the ERCW punp ' This instruction is in accordance with SI-1, Appendix F. The probability M-S and the discharge check valve. of an accident has not been increased, and the possibility br an accident of a different type was not created. ** SI-045.5 ESSENTIAL RAW COOLING WATER PUMP N-B - UNIT 0 REV NO. 000 This instruction added the use of test instruments, made each pump test a The use of test instruments and testing at a single fixed flow rate did not ' '
separate procedure, and changed testing at several flow rates to a single reduce the margin of safety. The probability of an occurrence or the fixed flow rate. consequences of an accident were not increased, and the possibility for an
s Page No. 11 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANCES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY SUMMART g accident of a different type was not created.
** SI-045.6 ESSENTIAL RAW COOLING WATER PUMP P UNIT 0 REV NO. 000 This instruction was written in two parts for the testing of the ERCW pump This instruction is in accordance with SI-1, Appendix F. The probability and discharge check valve. of an accident was not increased, and the possibility of an accident of a different type was not created.
** SI-tA5.8 ESSENTIAL RAW COOLING WATER PUMP R-A - UNIT 0 REV NO. 000 This instruction added the use of test instrunents, made each pump test a The use of test instruments and testing at a single fixed flow rate did not separate procechre, and changed testing at several flow rates to a single reduce the margin of safety. The probability of an occurrence or the flued flow rate. cons w es of an accident were not increased, and the possibility for en accident of a different type was not created.
** St-046.1 COMPONENT COOLING WATER PUMP 1A-A - UNIT 1 REV No. 000 This instruction full strokes the CCS purp discharge check valves and All of the requirements of SI-46 for CCS pump 1A-A were incorporated into establishes a one-point test at a set flow rate. Each pump is tested by a an individual procedure. The establishment of a one-point test at a fixed separate procedure. SI-46 has been cancelled. flow rate for verifying full stroke of the discharge check valve did not increase the probability of an accident or create the possibility for an accident or malfunction of a different type. The margin of safety was not reduced.
** St-046.2 COMPONENT COOLING WATER PUMP 1B-B - UNIT 1 REW aO. 000 This instruction tutt strokes the CCS punp discharge check valves and Att the requirements of SI-46 for CCS pu:p 18*8 were incorporated into an -
establishes a one-point test at a set flow rate. Each punp is tested by a individual procecbre. The establishment of a one point test at a fimed
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t separate procedure. SI-46 has been cancetted. flow rate for verifying futt stroke of the discharge check valve did not increase the probability of an accident or create the possibility for an accident or matfunction of a different type. The margin of safety was not reduced.
- $1-046.3 COMPONENT COOLING WATER PUMP 2A-A - Unit 2 REV NO. 000 This instruction futt strokes the CCS punp discharge check valves and Att the requirements of $1-46 for CCS ptmp 2A-A were incorporated into an establishes a one-point test at a set flow rate. Each pump is tested by a individual procedure. The establishment of a one-point test at a fixed separate procedure. SI-46 has been cancetted. flow rate for verifying futt stroke of the discharge check valve did not increase the probability of an accident or create the possibility for en accident or catfunction of a different type. The margin of safety was not recbced.
- S1-046.4 COMPONENT C001.ING WATER PUMP 28-B - UNIT 2 REV No. 000 This instruction futt strokes the CCS pupp discharge check valves and Att the requirements of SI-46 for CCS pum 28-8 were incorporated into an establishes a one-point test at a set flow rate. Each pump is tested by a individual procedare. .The establishment of a one-puint test at a fixed separate procedure. $1-46 has been cancelled. flow rate for verifying full stroke of the discharge check valve did not increase the probability of an accident or create the possibility for en accident or malfunction of a different type. The margin of safety was not reduced.
- 51-046.5 COMPONENT COOLING WATER PUMP C UNIT 0 REV NO. 000 This instruction futt strokes the CCW pump discharge check valves and At t the requirements of SI-46 for CCS pump C-S were incorporated into en establishes a one-point test at a set flow rate. Each pwp is tested by a individual procedure. The establishment of a one-point test at a fixed separate procedure. SI-46 has been cancetted. flow rate for verifying futt stroke of the discharge check valve did not
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4 increase the probability of an accident or create the possibility for an accident or malfunction of a different type. The margin of safety was not reduced. s
** SI 050 72-HOUR CHEMISTRY REQUIREMENTS - UNITS 1 AND 2 i REY 40. 026 This revicion clarified frequency requirement for Reactor Coolant These changes did not affect the intent or results of this instruction.
Dose-Equivalent I-131 in accordance with T.S., indicated conplete or Therefore, the probabit'*y of an accident or malfunction was not increased, partial T.S. compliance, included changes required by Discrepancy Report and an accident or malfunction of a different type was not created. The 86-281R, and clarified the gross activity of coolant systems. This $1 was basis of any T.S. was not affected; therefore, the margin of safety was not revised in accordance with SI-1, Appendix F. reduced in any manner. o* SI-052 MONTHLY CHEMISTRY REQUIREMENTS - UNITS 1 AND 2 REV NO. 019 This revision to the SI included the addition of an objective section to Sampling of turbine building exhaust was eliminated, and the tritium limit
~
the scope of this instruction. This objective section states the was added af ter receipt of hRC IE But tetin 80-10 and ttye Tennessee requirements and their source docunents. The applicable modes have been Departsent of Health and Environment requirements. The margin of safety added to the appropriate sections. The sanpting of the turbine building was nut degraded in any manner. exhaust has been deleted because of the obsence of a requirement for this analysts. An acr(ptance criterion of 2.0 E - 05 UC./ML (Tennessee Departwr.t of Health and Environment) hst been added f ar the tritiara analysis e,f the drinking water. SI-053 SPECIFIC IODINE ISOTOPIC ACTIVITY CONCENTRATION AND/OR D.E. I-131 DETERMINATION - UNITS 1 AND 2 REV NO 012 This revision conformed to SI-1 review guidelines and took into The changes made to this Si af fect the format and Mxpte flush times and - consideration the predominate beta eeltter tritium. Also, it added conform to SI-1 guidelines. The changec in this revision did not affect acceptance criteria for modes 1, 2, 3, 4, and 5. ptant safety and did not present any new safety aspects dif ferent f rom nn
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those previously evaluated in the FSAR.
** SI-054 REACTOR COOLANT E DETERMINATION
- UNIIS 1 AND 2 REV No. 010 This revision conformed to SI-1, Appendin F, provided clarification, and the addition of the dominant beta emitter tritium to the E calculation did took into consideration the dominant beta emitter tritium, not affect plant equipment, safety, or the FSAR. Therefore, the margin of safety was not reduced, and these changes did not increase the possibility of an accident or a malfmetion.
** SI-056 SYPRODUCT MATERI AL INVENTORY AND SEALED SOURCE LEAC TEST'- UNITS 1 AND 2 REV NO. 014 The revisicn was made to correct the T.S. reference and to remove SNM f rom This revision af fected only the T.S. reference and included SR 4.7.1.0.1 the St. which has always been performed. SNM is now in fl-101. The probability of an occurrence or the consequences of an accident or metfunction were not increased, and the possibility for an accident of a dif f erent type was not
, created. The margin of safety, as defined in the basis of any T.S., was not reduced.
** SI-058 ICE CONDENSER CHEMISTRY - LMIIS 1 AND 2 REV No. 013 This revision complied with SI-1, Appendia F, format, clarified and The changes to the instruction in this revision were administrative and condensed the instruction section, added an "additional data" sheet, and format-complying in nature and did not increase the probability of an-added the FSAR timits on buron for fitting purposes (changed from boron >= accident or matfunction. The margin of safety was not reduced.
1950 ppe <= 2100 ppm to >= 1900 ppm).
** SI-062 CONTAINMENT VACUUM RELIEF VALVES AUTO-OPEN - UNIIS 1 AND 2 REV NO. 011 This revision clarified requirements, test frequency test method. and The performance of this test consists of opening each containment vacwm
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7 simplified acceptance criteria. It addressed and specified actions to be relief valve and measuring the force required for opening. It also verifies taken when acceptance criteria are not met and added required accuracies operability of the containment vacuun relief valves which ensures that and ranges to test equipment. containment internal pressure does not become more negative than 0.1 psid. The performance of this test does not place the plant in an undocunented LCO or unanatyred condition; therefore, the margin of safety, as defined in the besis of any T.S., was not reduced. c+ $3 067 PERIODIC CALIBRATION OF RPI SYSTEM - UNIIS 1 AND 2 REV NO. 004 This revision was made to conply with SI-1, Appendix F, and to include the The St has been revised to include final hot chssnnel calibration contained final hot channel calibration. This revision will also clear CATS 86-529. in IMI-85-RPI. The remaining sections of IMI-85-RPI will be performed by
$1-67. Previously, IMI-85-RPI met att T.S. requirements. Att original requirements are still met. This revision did not increase the probability of an accident or malfunction and did not create a different type of accident. Because att T.S. requirements were met, the safety margin as defined was not re<bced. ** . SI-067.1 PERIODIC CALIBRATION OF THE ROD POSITION INDICATION CHANNELS - UNITS 1 AND 2 REY No. 002 This revision incorporated the electrical calibration, cable connection This SI has been revised to include all but the final hot calibration verification, and cold shutdown channel calibration sections formerly sections contained in IMI-85-RPI. The final hot calibration will be retained in IMI-85-RPI, and steps to Calibrate the bypass module. performed by SI-67. This procedure affects existing equipment only. This procedure and SI-67 will perform all other sections previously performed by IMI-85-RPI, which met all T.S. requirements. Therefore, the method of testing has not changed, and the margin of safety has not decreased.
~ REV NO. 003 This revision removed calibration of the bypass modules and corrected The testing and calibration of the bypass modules are performed in tolerance on rod bottom bistables. This revision also removed verification IMI-85-RPI and are not required for this instruction. .XA-55-48-28 actuates
-4 0--
.= -. .- , . .. , - - -
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of XA-55-48-28 and removed repeatability statements from step 10, because from the same relay as the rod bottom bistable lights. The lights are setpoints are not being checked, only indications. checked by this instruction and prove the associated relays are functioning property. This annunciator is verified to function during startt.p when the rod banks are att off the bo* tom. There were no T.S. setpoints or limits changed. The probability of an accident or malfuncticn was not increased, and the possibility for an accident or malfunction of a type dif ferent than previously evaluated was not created. The margin of safety, as defined in the basis of any T.S., was not reduced,
- SI-068 fUNCIl0NAL TEST OF CONTAINMENT SPRAY PUMPS AND ASSOCIATED VALVES - tallTS 1 AND 2 (FREQUENCY 550 DAYS)
REV NO. 003 This revision incorporated SR for CSP and automatic valve allgrunent f rom The testing methods did not change, and the margin of safety was not containment pressure high-high test signal. This was previously part of affected. SI-471 which has been cancetted.
- $1-071 DISSOLVED NITROCEN AuD AIR CONCENTRATION IN UPPER HEAD INJECTION WATER-FILLED ACCUMULATORS - UNITS 1 AND 2 REV :3. 009 On Data Sheet 1.0, the acceptance criteria of <80 SCF as the dissolved This revision did not increase the possibility of an accident or nitrogen and air concentration in the UMI water-fitted occumulator was malfunction of equipment. 'This revision was to format the SI and to state added. Changed wording to correct various typogregAlcal errors. that it fully satisfies T.S. requirements. Since the instruction satisfies T.S. requirements, the margin of safety was not reduced.
- SI-072 QUARTERLY CHEMISTRY REQUIREMENTS - UNITS 1 AND 2 CEV NO. 012 This revision cancet ted SI-72. T.t SR 4.11.1.3.2 has tween eliminated.
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j CO SI-078 POWER RANGE NEUTRON FLUX CHAhNEL CALIBRATION BY HEAT BALANCE COMPAR!bCN (DAILY) - UNITS 1 AND 2 REV NO. 010 This revision added a reference section, revised the Data Package Cover The corrections in this revision made the procedure more consistent With Sheet for consistency with Al-4, corrected LCO nunbers for consistency with plant Als and the T.S. It did not increase the possibility of an accident, each unit's T.S., added a prerequisite to obtain 510 permission to perform and the margin of safety was not reduced. the test, and allowed performance of the test with an inoperable channet. SI-079 POWER RANGE NEUTRON FLUX CHANNEL CALIBRATION BY INCORE - EXCORE AXI AL IMBALANCE COMPARISON (MONTHLY) - UNITS 1 AND 2 REV No. 008 This revision added steps for performance of TI-36 and corrected figure 1 The addition of t!eps and correction of figure 1 enhanced and clarified the to reflect a more realistic incore computer output. Also added steps to methodology of the procedure. Satisfying LCO 3.3.3.2 ensured that source satisfy LCO 3.3.3.2 moveable detector system cperability, data used to perform SI-79 was accurate. The probability of an accident was not increased and the possibility for an accident or motfmetion of a different type was not created. The margin of safety was not reduced. SI-080 POWER RANGE NEUTRON FLUX CHANNEL CALIBRATION AND FUNCTIONAL TEST (QUARTERLY) - UNITS 1 Aho 2 REV NO. 011 This revision added SRs that are partletty satisfied by this $1 and added This revision did not change the method of testing or sequence of events. references to other instructions that conp!etely satisfy SR 4.3.1.1.1.8.2 None of the T.S. setpoints or tolerences were changed. The probability of and SR 4.3.1.1.1.B.7. This revision also clarified the acceptance criteria an accident was not increased, and the possibility for an accident or section and added reference to TI-54/54.2. malfunction of a different type was not created. The margin of safety was not affected. C* St-082 FUNCTIONAL TESTS FOR THE RADIATION MGNITORING SYSTEM - UNITS 1 AND 0 , REV NO. 013 This revision incorporated changes nude by two separate ICFs (ICT 87-273 These ICFs did not affect the margin of safety. These changes were intent and ICF 87-135). changes and were incorporated. ICF 87-135 was incorporated so that 51-82 could be performed and would work as written. ICF 87-273 wcs ir.corporated,
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g ICF 87-135 clarified instruction step for measuring high voltage, added because the tolerance placed on RM-90-102 and -103 was too tight. This ! instruction step to clear att alarms before testing for motfunction stares, tolerance was established, because RM-90-102 and -103 are GM tute-type and corrected window rud;ers for RM-90-103 and -126, and block switch detectors. The +/- 25 volts high voltage value tolerance is adequate since - position for RM-90 126. the GM tube plateau curves are f airly constant at the calibrated high vottage setting. This change corrects errors made by ICF-87-135. These ICF 87-273 changed tolerance on the calibrated high voltage valve for changes ensure the SI can be performed the way it was written and do not radiation monitors RM-90-102 and RM-90-103 from "As Fotsid" +/- 10 volts and alter the margin of safety. The probability of an accident or malfunction "As Lef t" +/- 2 volts to "As Found" +/- 25 .wlts and "As Lef t" +/- 25 was not increased. volts. The tolerance originally specified is for scintittation-type detectors and does not apply to the GM tube-type detectors. Radiation monitors 90-102 and 103 are GM tube-type detectors. l ** 'SI-082.2 FUNCTIONAL TEST FOR THE RADIATION MONITORING SYSTEM - UNIT 2 REV No. 006 This revision added vendor "CPM" values equivalent to T.S. values. The T.S. allowable values specified in "CPM" were corrected to coincide with the vendor sensitivity plots stoptied under contract 92759. Since the "CPM" vetu % are equivalent per vendor documentation, the margin of safety was not affected.
** SI-090.12 REACTOR TRIP INSTRUMENTATION FUNCTIONAL TEST OF DIFFERENTIAL TEMPERATURE /TAVG CHANNEL I, RACK 2 (T-68-2) - UNIT 2 REV No. 003 This revision corrected deficiences in technical adequacy as evaluated The test methodology was unchanged. The revised procedure ensured that the using SI-1, Appendin F. This revision also contained IMI-99 with SI-90.12 toop performed its intended function by verifying additional inpJts to the and cancelled IMI-99. overpower dif ferential temperature and overtemperature dif ferential tenperature setpoint calculators. The probability of an occurrence or the consequences of an accident were not increased. The possibility for an accident or malfunction of a different type was not created, and the '
revision ensured that the T.S. requirements were fully satisfied.
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I SI-090.32 REACTOR TRIP INSTRUMENTATION DIFFERENTIAL TEMPERATURE /TAVG CHANNEL II, RACK 6 (T-68-25) - UNIT 2 REV NO. 003 This revision corrected deficiencies in technical adequacy as evaluated The test methodology was unchanged. The revised procedure ensured that the using SI-1, Appendin F. This revision also combined IMI-99 with SI-90.32 toop performed its intended function by verifying additional inputs to the and cancetted IMI-99. overpower dif ferential tenu-;.ature and overtemperature dif ferential - temperature setpoint e a cu*.ators. The probability of an occurrence or the consequences of ar accident were not increased. The possibility for an accident or me'. unction of a different type was not created, and the revision er G red that the T.S. requirements were futty satisfied. St-090.42 REACTOR TRIP /ESF INSTRUMEN1 ATION QUARTERLY FUNCTIONAL TESTS (RACKS 7 AND 8) - UNIT 2 REV NO. 002 This revision added applicable references, prerequisites, performance This revision did not increase the possibility of an accident, because any-modes, and corrective action when "As Found" data are not within desired T.S. that is covered remains the same. These changes are mainly tolerance. administrative in nature which ensure compliance with the T.S. requirements. SI-090.52 REACTOR TRIP INSTRUMENTATION FUNCTIONAL TEST OF DIFFERENTIAL TEMPERATURE /TAVG CHANNEL I!!, RACK 10 (T-68-44)
- UNIT 2 REV NO. 003 This revision corrected deficiencies in technical adequacy as evaluated The test methodology was unchanged. The revised procedure ensured that the using SI-1, Appendix F. This revision also contined IMI-99 with St 90.52 Loop performs its.latended function by verifying a&Jitional inputs to the and cancetted IM1-99. overpower differential temperature and overtemperature differential tenperature setpoint calculators. The probability of an occurrence or the consequences of an accident were not increased. The possibility for an accident or malfunction of a different type was not created, and the revision ensured that the T.S. requirements were futty satisfied.
~44-
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g C* SI-090.72 REACTOR TRIP INSTRUMENTATION FUNCTIONAL TEST OF DIFFERENTIAL TEMPERATURE /TAVG CHANNEL IV RACK 13 (T-68-67) - UNIT 2 REV NO. 003 This revision corrected deficiencies in technical adequacy as evaluated The test methodology was unchanged. The revised procedure ensured that the using SI-1, Appendin F. This revision also ccat)ined IMI-99 with SI-90.72 Loop performs its intended function by verifying additional inputs to the and cancetted IMI-99. overpower differential tenperature and overtemperature differential temperature setpoint calculators. The probability of an occurrence or the consequences of an accident were not increased. The possibility for an accident or malfunction of a different type was not created, and the revisions ensured that the T.S. requirements were fully satisfied.
*3 SI-090.8 REACTOR TRIP INSTRUMENTATION MONTNLY FUNCTIONAL TEST (S$PS) - UNIT 1 REV NO. 004 This revision incorporated comments f rom the SI-1, Apperdix F, added SR These revisions did not increase the prebability of an accident. The-4.3.1.1.1.C.22.A, and added signof fs in various points to document return changes did not change the intent or method of testing. They helped to to normat conditions, ensure corptience with T.S. and ensure adequate and proper equipment operation. The T.S. SRs were met, and no setpoint was changed; therefore, the margin of safety was not reduced.
** SI-090.82 REACTOR TRIP INSTRtt.ENTATION MONTMLY FUNCTIONAL TEST (SSPS) - Unit 2 REV NO. 005 Revised the instruction according to SI-1, Appendix F. This revision added the scope and intent of this instruction did not change. The addition of SR SR 4.3.1.1.C.22.A, revised surveittance frequency, added return to normat 4.3.1.1.C.22.A was a documentation change only because the procedure has signof f s, added mechanical ard technical equipment requirements, and always satisfied this SR. The method was not changed, and no T.S. was corrected various typographical errors. affected by the revision. No possibility of a new accident or malfunction was created, and the margin of safety was not decreased.
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l O* SI-093 REACTOR TRIP INSTRUMENTATION e*UNCTIONAL TESTS CCNDITIONAL 7 DAYS (PRIOR TO STARTUP) - UNITS 1 AND 2 ' REY NO. 010 This revision addressed T.S. interpretation 79, revised the reference The testing methods conform to NRC generic letters 83-28 and 85-09 and NCR section, added TSC points, and clarified the acceptance criteria. 79-4 and 79-5. This method does not increase the probability of an accident. The addition of TSC point verification increased reliability of computer information. No margin of safety Fas reduced. SI-09( FUNCTIONAL TEST OF INTERMEDIATE AND POWER RANGE NEUTRON FLUX CHANNELS AND THE P-7 INTERLOCK - UNITS 1 AND 2 2EY No. 003 This revision removed the contents of the SI, because SR 4.10.4.2 is a Removing the contents of this SI and rewriting it when special conditions conditional surveillance test that is required when the T.S. allows less exist do not reduce any margin of safety. than four reactor coolant punps running in modes 1 and 2 (LCO 3.4.1.1). This LCO wit t not be suspended unless required by special conditions or tests. If required by special conditions or tests, this surveillance test wilt have to be evaluated and rewritten to conform to the actual special test requirements. m SI-097.2 CALIBRATION OF AUXILI ARY FEEDWATER FLOW RATE FOR REMOTE SHUTDOWN AND ACCIDENT MONITORING (550 DAYS) - UNIT 2 REO NO. 001 This revisico corrected tolerances on flow toop F-3-142. The correction of these tolerances enhanced safety. It also ensured proper flow indication and proper catibration of the loop components. No T.$. criteria were af f ected by this change.
** SI-100.3 ANNUAL 125-VOLT VITAL BATTERY SYSTEM INSPECTION - UNIT 0 REY NO. 000 This new instruction was written to fulfitt SR 4.8.2.3.2.C.1, SR When the vitat battery changes are inspected, the spare vitat battery 4.8.2.3.2.C.2, and part of SR 4.8.2.4.2 which was formerly fulfilled by charger is removed from service. The probability of an occurrence or.the SI-105. consequentes of an accident or matfunction are not increased, and there is
Page No. 22 02/2S/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DEStelPIION SAfEIY LUMMARY l no redJction in the sergin of saf ety.
** SI-102 INSPECTION OF DIESEL CENERATORS - UNITS 1 AND 2 REV NO. 007 This revision cancelled the instruction. It is being replaced by SI-102M This instruction has been cancetled and replaced by two more detailed .
and SI-102 E/1.5Y. instructions in new procedures, SI-102M and St-102E/1.SY. These more detailed instructions do not increase the probability of an accident or malfuncticn and do not create any of a different type. Because the basis' of any T.S. remained unaffected, the margin of safety was not reduced.' SI-102 E/1.5Y DIESEL GENERATOR (18 MONTHS) ELECTRICAL INSPECTIONS - UNITS 1 AND 2 AEV NO. 001 This revision cancetted this instruction. The manufacturer-recommended maintenance is not an SR. Inspections are now made on an IMI. U -102 E/M DIESEL CENERATOR MONTHLT [LECTRICAL INSPECTIOh - UNIIS 1 AND 2 RE*J EO. 004 This revision added a reference to EMSL A36, "Common Mode f ailure," added The intent of this instruction remains the same. .The various referei.ce an SR nunber to the procedure scope, and changed clarity note to step information was added to meet the requirements of SI-1. These changes did 6.4.4. not increase the possibility of an accident or eelfunction of equipment. The addition of reference information did not alter the T.S. In any way; tterefore, the margin of safety was not reduced.
- SI-102 M OIESEL GENERATOR MECNANICAL INSPECTIONS
- UNITS 0, 1. AND 2 REV NO. 001 This revision added a note to first perform the steps required white the The steps in the SI will be performed ir a sequence that is most efficient engine is tagged out and allowed inspection cf the ott filter check valves. to work schedules. Att inspections will be performed as required.
Therefore, there will be no increase,in the probability of an accident or
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the creation of an accident of a different tyre, because the results of the SI witt not be affected. Also, the 1: asis of any T.S. edit not be af fected, and the margin of safety >:llt not be reduced.
- o 51-102 M/M DIESEL CENER* TOR MONTHLY MECMANICAL IhSPECTION - UNITS 0, 1, Ak0 2 REV NO. 003 This revision deleted the inspection of ir,cerrwi fuel system d.aring The fuel system internel manifold is inspected with the engine chutdown and operations at futt load. the fuel systect pressur ized by the priming pump. The deletion of the inspection at futt lead prevents opening the top deck covers at full load.
Deletion of this inspection at futt load did not increase the probability of an accident, because it is performed during shutdown. The possibility-for an accident of a different type was not created, and the margin of s.nfety, as defined in the basis of any T.S., was not redtced.
- SI-104 AuxrtfARy sugL0gNG CRARE INTERLOCKS - UNIT 0 REV NO. 011 This revision clerified performance and applicable modes. Signoffs for unit The margin of safety from the previous revision was not altered by this 1 ams unit 2 S2/SRo were added, end a Deficiency Log was ad1ed. revisirei to the instruction. ' The enhancement changes in this revision only clarified the scope and added signof fs for deficiencies and consson equipment signof fs. The margin of safety, as defined in any T.S., was not.
reduced.
- St-105 VITAL BATTERY BANK AND NORMAL CHARGER PERFORMANCE TEST - UNIT 0 DEv NO. 021 this revision ircorporated SR 4.8.2.3.2.F to increase prccedure frequency No system configuration changes were made by this revision. The due to degradstion. probability of an octurrence or the consequences of an accident were not l'ncreased. The possibility for an accident of a different type was not created, anri the margin of safety was not reduced.
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i O* SI-106 ICE CONDENSER - ICE BED - UNITS 1 A C 2 l REY ho. 011 This revision aderes to the requiremient of SI-1, Apperdix F, and enhances the revisions to the tratruction were for clarification and enhance: ace.t. the procedure. The revision removed the requirements for weighing the ice removed to j provide access for.the basket lift rig. The ice removed is cor:sidered regligible and wilt not affect the acceptance criteria for this SI. Therefore, the margin of safety was not reduced and the possibility for an acciden'. oc e tfunction was not increased.
** St-108 ICE CONDENSER 000R$ - UNITS 1 AND 2 REV No. 009 This revision complies with T.S. SR 4.6.5.4.B and SR 4.6.5.3.2.8. SR 4.6.5.3.2.8 requires an inspection of tne intermediate deck door vent l assembtles. The acceptance criteria were revised con,ervatively to attou for the accuracy of the measuring and test equipment to ensure T.S. values were not inadvertently exceeded. This change did not affect safety as previously evaluated and served to maintain the tevet o'f safety. No new accident or matfunction was created.
SI-113 TESTING AND SETTING OF SETPo!NT O' PRESSURIZER SAFE 7f VALVES - UN!1S 1 AND 2 a REV NO. 009 This revision incorporated ANS!/ASME OM-1-1981 regairements for testing of ANSI /ASME OM-1-1961 was written specifically for in-service testing of-pressurized safety valves arms deleted requirements specified by power test - safety valves and is a source document improvement as compared with the codes 25.2 and 25.3. power test codes. The probability or consequences of.an accident were lessened by implementing OM-1-1981 requirements. The possibility for an accident or malfunction of a different type was not created. Tt.e margin of safety was not reduced. l
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Dage No. 25 1 02/M/38 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBE 0 IN THE SAR DESCRIPTION SAFETY
SUMMARY
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** SI-114.1 ASME SECTION MI IN-SERVICE INSPECTION PROGRAM - UNIT 1 REV #0. 008 This revision incorporated the use of a CAQR in accordance with SP T.S. This change incorporated the use of a CAQR in accordance with NOAM, Part F, 861127D and corrected various typographical errors in the procedure tabtes. Section 2.16, wd AI-12 as additional reporting and tracking requirements.
It did not incicase the probability of an accident or metfunction of equipment and 4 ed not alter the scope, intent, or T.S. The margin of safety was not reduced C* SI-114.2 IN SERVICE IMSPECTION PROGRAM FOR TVA $[QUOYAN NUCLEAR PLANT - UNIT 2 ONLY REY h0. 009 This revision incorporated the use of a CAOR in accordance with SP T.S. This change incorporarrd the use of a CAQR in accordance with NQAM, Part F, 870119E and corrected various typographical errors in the procedure tables. Section 2.16, and Al #,2 as additional reporting and tracking requirements. It did not increase .he probability of an accident or metfunction of equipment and did not alter the scope, intent, or T.S. The margin of safety was not reduced.
** SI-117 ERCW SYSTEM OPERATING - UNITS 1 AND 2 RED NO. 003 This revision included changes of organizational designation from QA to This revision was for clarification and flow indicator inctusions. The flow cE&C on the Data Package Cover Sheet and added flow irdicators 1-FI+67-222, indicator inclusions give the performers more positive indication that the 2-FI-67-222, aruf 0-FI-67-226 to be used in conimction with the pressure ERCu pumps are delivering flow to the headers. With pressure only It could indicators. Changed notification from SE to SRO. be questionable, because the pts are on the discharge of the pumps, and valves could be isolated downstream, thus blocking flow into the auxiliary building. These revisions and inclusions did not increase the probability of an accident or malfunction, nor decrease the margin of safety.
4
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Page No. 26 02/22/88 . SEQUOYAH NUCLEAR PLANT , 10 CTR 50.59 . 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRISED IN INE SAR i i DESCRIPTICs SAFETY
SUMMARY
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' *
- SI-118.1 TUR8INE-DRIVEN AUMILI ARY FEEDWATER PUMP AND VALVE AUTOMATIC ACTUATION - UNilS 1 ANO 2 REW mo. 015 This instruction was revised to comply with SI-1, added signoffs to verify The revision did not change the scope, intent,-methodology, or result of' turbine driven AFW pump of f and in auto prior to initiating each test this test. Therefore, the probability or consequences of accidents or signet, and corrected acceptance criteria *or low-tow steam gmerator tevet malfunction were not increased. This revision did not create any r.ew test. accidents or malfunctions, and the mergin of safety was not decreased.
** SI 119 ERCW AUTO ACTUAi!ON FROM AN St SIGNAL
- UNIT 0 REV n0. 009 This revision changed unit. designation from 1 and 2 to 0, corrected These corrections did not' change the intent or technique of this test in
~
typogragbical errors tSI should have tren safety injection), changed any momer, The margin of safety was not redaced and the probability for q ret 6fication f rom SE to SRO, and included orgerilzational change f rom OA to an accident or motfunction'of equipment was not increased. This test did QE&C. not create a new type of~ accident or malfunction.
** $1-127 RCS AND PRESSURIZER TEMPERATURE AND PRESSURE LIMITS - UNITS 1 AND 2
~
REW NO. 015 This revision was made to implement corrections needed to resolve technical The evaluation of past performances of SI-127 with the'technliet': inadequecies identified by St-1, Appendin F. and to ensure literat inadequecies indicated no vlotation of the plant T.S.'- Ensuring Literal compliance with the plant T.S. comptience with the plant T.5, did not increase the probability of an occurrence or the consequences of an accident or matftsiction of equipment. The possibility of an accident or maifunction'of a different type was not - created, and the margin of safety, as defined in the basis of any T.S ,'wes . not reduced. St-128 EMERCENCY CORE-COOLING STSIEMS RESIOUAL HEAT REMOVAL PUMPS
- UNIIS 1 AND 2 .
REW No. 029 This revision cancetted this instruction. AktT.S.requirementshavebeentransferredto 51-128.1, 5t-128.2, 51 123.3, $1-128.4, and $1-128.5 f or test _ing each pump. a 4 S t
. =. .. .. . ._ .,. . . .
s Page No. 27 02/22/88 SEQUDYAM NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRISED IN THE SAR DESCRIPTION SAFETY
SUMMARY
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** SI-128.2 RESIOUAL HEAT REMOVAL PUMP 1A-A PERFORMANCE - UNIT 1 REW NO. 000 This new instruction was written to replace SI-128 and to separate the There have been no changes in the method of testing or acceptance criteria.
testing of each pump to an instruction by itself for clarity and The margin of safety, as defined in the basis of any T.S., wes not reduced. ' erdiancement. All requirements of SI-128 have been incorporated. Test instruments that meet the accuracy and rarge requirements of ASME, Section MI, have been added.
*O SI-128.3 etSILUAL HEAT REMOWAL PUMP 18-8 PERFORMANCE - UNIT 1 REV No. 000 This new instruction was written to replace SI-128 and to separate the There have been no changes'in the method of testing or acceptance criteria.
testing of each pump to an instruction by itself for clarity and The margin of safety, as defined in the basis of any T.S., was not reduced, er!.ancement. All requirements of SI-128 have been incorporated, and test instruments that meet the accuracy and range requirements of ASME, Section XI, have been added. c+ $3 128.4 RESIDUAL MEAT REMOVAL PUMP 2A-A PERFORMANCE - UNIT 2 REV NO. 000 This new it.struction was written to replace SI-128 and to separate the - There have been no changes in the method of testing or acceptance criteria. testing of each pump to an instruction by itself for clarity ard The margin of safety, as defined in the basis of any T.S., was not reduced. erdunnc ement . Att requirements of $1-128 have been incorporated. and test instruments that meet the acct. racy and range requirements of A*,ME, Section XI, have been added.
" SI-128.5 RESIDUAL HEAT REMOVAL PUMP 28 8 PERFORMANCE - UNIT 2 REV No. 000 This new instruction was written to replace SI-128 and to separate the ' There have been no changes in the method of testing or acceptance criteria.
l
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Page no. 28 02/31/83 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CNANCES TO PROCEDURES AS DESCRISED IN THE SAR DESCRIPilON SAFETY
SUMMARY
testing of each pump to an instruction by itself for clarity and The margin of safety, as defined in the basis of any T.S., was not reduced. enhancement. Att requirements of $1-128 have been incorporated, and test instruments that meet the accuracy and range requirements of AsdE, Section XI, have been added. SI-131 THERMAL POWER DETERMINATION DURING PHYSICS TESTING IN MODE 1 - UNITS 1 AND 2 REV No. 002 This revision deleted requirceent 3.2.1 (Axist Flux Difference) and added a The deletion of the requirement 3.2.1 (Amiel Flux Difference) results in reference section to the scope, the nonperformance of the requirement for the power physics test using power range instrtsnentation. This deletion did not increase the probability of an accident and did not reduce the margin of safety in any manner. St-135 EGIS CLEANUP SUBSYSTEM AUTOMATIC START - UNIT 0 REV NO. 010 This revision to the SI changed notification requirements from SE to SRO, The corrections and procedural clarifications in no way affect the intent, added a T.S. SR reference, clarified system operating instructions scope, or result of this test. They did not increase the probability of an reference, and added signoff for verification of system operating accident or malfunction and did not create any new type of accident. The instructions and return to normat per attached copy. margin of safety, as defined in the basis of any T.S., was not reduced.
- SI-136 EGTS CLEANUP SUBSYSTEM FUNCTIONAL TEST - UNIT 0 REV NO. 009 This revision changed unit designation from units 1 and 2 to wiit 0, The changes made are for clarification and conpliance with SI-1, Appectfix changed notification f rom SE to SRO, made organlaationat corrections f rom F. They did not af fect the scope or intent of this procedure f r$ any CA to OE&C, made data sheets for fan AA and 88 the same, and corrected manner. The probability for an accident or malfunction of plant equipment various typographical errors. was not increased, nor did the changes create a new type of accident. The changes did not affect the T.S. The surgin of safety was not reduced.
__ m_ _. _ . . __ ___ _ . _ _ . . =_, , _ _ _ . _ ... _. Page No. 29 C2/23/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50 59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
l SI-137.1 REACTOR COOLANT SYSTEM - UNIDENTIFIED LEAKAT.E MEASUREMENT - UNITS 1 AND 2 RED No. 014 This revision added M&fE docuentation, replaced unvalidated methodology, The intent of this procedure was tnchanged, and no new system Lineups or reorganized and restated for clarity. changes were initiated. There was no increase in the probability of an accident or malfunction of equipment. All T.S. requirements and regulatory guidelines were met; therefore, there was no degradation of the margin of safety.
- St-137.2 REACTOR COOLANT SYSTEM WATER INVENTORY - UNITS 1 AND 2 REW NO. 018 This revision added a reference section, incorporated signofis into the No accident or metfunction of a different type than prev!ously analyzed was data sheet, and rounded of f conversion factors to comply with the regJired created. The margin of safety, as defined in the basis of any T.S., was.
accuracy of the procedure. Also added the requirement to perform Si 137.2 not reduced. If the acceptance criteria of SI-137.1 are not met. This ensures compliance with SR 4.4.5.2.1.9 and SR 4.4.6.2.1.6.
$1 137.3 MEASUREMENT OF THE CONTROLLED LEAKAGE 10 THE REACTOR COOLANT KJMP SEALS - UNIIS 1 AND 2 REW NO. 004 This revision was made to require, in addition to the emplicit T.S. RegJiring verification of the minimum 10J osid pressure drop properly requirement, verification of the som specific bases for the SR. The change augments the surveillance and ensures that both the.expticit T.S.
required the pressure drop across the seat injection Lines to be verified retpirements and the basis for the SR are satisfied. Adjustment of the equat to or greater than 100 psid during performance of this test. seat back-pressure valve to reach desired pressure drop prior to checking Guidance is given to allow adjustment of the RCP seat back-pressure valve, maximum flow rate does not alter the validity of the surveillance. FCV-62-89, to assist in obtaining the equal to or greater than 100 psid Enhancement of the surveillance ensures ECCS capabitity will be consistent t pressure drop. with that assumed in the safety analysis. These changes did not increase the probability or consequences of an accident or redece any margin of safety. s I _g
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Dage No. 30 02/32/88 SE000YAH NUCLEAR PLANT i 10 CfR 50.59 l 1987 NRC ANNUAL. OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR i l l ? DESCRIPTION SAFETY
SUMMARY
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$1-153 CONTAINMENT SPRAY - SPRAY NO2ZLE TEST - UNITS 1 AND 2 REV NO. 006 This revision corrected various technical details and provided conformance This instruction ensures that the contairunent spray nozzles are functional.
with SI-1, Appendix F. There is no modification to permanent plant equipment implemented by the perfornunce of this instruction. .The procedure ensures operability of T.S. equipment in accordance Nith T.S. guidelines wwi frequency. There was no l margin of safety degradation and no increase in the probability of en accident or metfunction. c* SI-141 RESULTS FROM TEST LA80RATORY ON CHARCOAL TEST CANISTER - UNITS 1 AND 2 1 RED No. 009 This revision included T.S. reouirements for modes and f requency, added a Adding information to the procedure for reference did not increase the reference, and contained instructions with data sheets, probability or the consequmces of an accident, and it did not create a different type of occurrence. Adding information for reference had no affect on the T.S. The margin of safety, as defined in the basis of any T.S., was not reduced.
** $1-149 AUXILIARY SUILDING CAS TR'ATMENT SYSTEM VACUUM TEST - UNIT 0 REV NO. 014 This revision added a note stating that the equipment is consnan to both Adding comanon equipment note, prmission requirement, and clarification did units, added a requirement for unit 1 and unit 2 SRO permission to perforte not increase the probability of an accident, and it did not create a test, and added a sentence to clarify the formula. different type of accident. B w,,use the T.S. remains unaltered, the margin of safety was not reduced.
9
** SI-151 SIX-MONTN TEST REQUIREMENT ON ELECTRIC HYOROGEN RECOMBINER SYSTEM - UNITS 1 AND 2 REV No. 012 Thss revision changed approvat and verification from SE to SRO, deleted This revision in no way affected the intent or scope of the instruction; Page No. 31 02/22/818 SEQUOYAM NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
g stperfluous information, corrected organizational designation from CA to therefore, the probability of an accident or malfunction did not increase. QE&C. and clarified the instruction in accordance with $1-1, Appendix F. The changes did not create a new type cf accident or malfmetion. Since the clarification did not alter any T.S., the margin of safety was. unaffected. REV NO. 013 This revision clarified the procedure steps and the acceptance criteria. The clarifications made to the instruction ensured that the equipment was tested to satisfy the scope of the instruction. The probability or consequences of an accident or malfunction were not increased. The possibility for an accident or matfmetion of a dif ferent type was not createo, and the margin of safety, as defined in the basis of any T.S., was not reduced. SI-152 SwJTDOuN MARGIN SPECI AL TEST EXCEPTION - ROD DROP VERIFICATION - UNITS 1 AND 2 at* a. 002 This revision made the test more applicable to actual special test Compliance with plant design requirements and special test requirements did eaception requirements and current plant design requirements if the test is not increase the probability of an accident. This revision made the SI ever performed because of relaxation of the shutdown margin requirement. more applicable to the SR which is designed to ensure that no margin of safety is redJced. l St-155 REACTOR COOLANT FLOW VERIFICATION - UNITS 1 AND 2 REV No. 012 This revision added data sheets for recording voltages of the RCS flow This revision did not affect any systems in such a way as to increase the transmitters and reoutres the Si to be performed concurrently with TI-2 and possibility of an manalyzed accident. The margin of safety is increased St-246. by ensuring the RCS flow transmitters are in the proper sensitivity band and by requiring $1-246 to be performed concurrently. 1 i
=
m .. ..- ,_. - - Page so. 32 - s 02/22/88 SEQUOYAH NUCIEAO PtANT 10 CFR $0.59 , g, 1987 MRC-ANNUAL OPERATING REPORT _ CHANGES TO PROCEDURES As DESCRIBED IN THE A R W DESCRIPTION SATETY
SUMMARY
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** SI-15f.1 PERSONNEL f A!RLOCK OPERASILITY AND OVERAtt LEAKAGE TESTS - UNITS 1 ;.WO 2 RfV NC. 010 This revision clarified the instruction, corrected discrepancies, clarified The clarifications and corrections made tw this revision did r.ot change the the calculation procedure, and correcte 4 errors discovered by the SIReview intent or function of the procedure. The method of testing and the Task Force. Also, it has tested the ranges / accuracies of test equipment, acceptance criteria were not altered by this revision. The limit of made the data sheet more deteited, and included additional signoffs, teakage and the test f requerr./ were not changed. Therefore, the probability of an accident or metfunction was not increased, no new eccidents or malfunctions Lere introduced, and the !nergin of h fety was not reduced.
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^ ** $1-159.2 AIRLOCK RESILIENT SEAL LEAK RATE TEST - tmITS 1 AND 2 REW No. 012 This revision clarified the procedure, specifleo ranges and acct.recies for The actual testing method has not changed from the previous revision of test equipment used in performing the procedure, and included correct ,-' this procedure. Containment integrity is maintained and not affected by references used in preparing the procedure. The value used in the performance of this test. The acceptance criteria'Tvelue change ensurch acceptance criteria was revised f rom 2.37 SCf N to 2.25 SCf N. that T.S. timits are mt.%
y , _ :s a 3'K.
** SI-159.3 CONTAINMENT Mf0ROGEN ANALYZER SYSTEM LEAKAGE TEST , 2N a'
?
~ REV 'J0. 005 This revision deleted references to procedures that have been cancetted, At least one t[altl of the N W [.n ar3tyrce is ensured operable at att s - added other references, clarified instruction calculations, and added LCO times, and contairment* ..c.grity is maintained. The probability of an - requirements to the acceptance criteria, accident was nc? *. creased, and ih* pcesibility of an accident or malfunction of a different type was not created. The margin of safety as N Eb defined in the T.S. was not reduced. (
*? SI-139.4 PERSONNEL AIRLOCK OPERAgILITY
- UNIIS 1 AND 2 -
I-
. ett; No. 002 This revision detettd steps that notified the UO prior to entry into the intent remained trxhanged, arvJ the instruction is still technicatty
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35
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rege No. 02/22/08 , a s SE000YAn ,WCLf At PiANT 10 Of2 50.5' 198T NEC;ANNt:Af OPERAS,Ns RDORT ' CHANGES 'O PROCEDURES AS DESC816ED IN THE SAR DESCR PTION SAFETY
SUMMARY
g contairunent and added entra sheets to the instruction so ther one SI performed in the same snanner. There was no increase in the protability of package could cover both airlocks on ane unit. anaccidentormal(unction. ThymarginofsafetywasIsGtreduced,because the T.S. remale;9 L ahanget. ' j y ; I '/ s r a
** $!-139.5 . LEAC RAYE TEST ON CONTAINMENT PRESSLA.E INSTRumsCATIs,T - UNI 151 A<c 2 -
REV NO. 000 Thte eevision included test methods and .,%ca sheets tecessary to cumtify The p scedure is"still perryrri.3 in the same manner; however, it is now teskage f rom the contairunent pressure instrumenta-lon tested unde.- this clearer and provides for quantification of Icakage. The probability of an. procedure. This also made provisions to add "As Fount"* 7. w .% e Q the occurrence or the consequences of an accident or rialfunc$ ion were rot
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total integrated conteirinent teak rate. inc eased. The possibility for an accident o. tttmction af a diff0. ant 141 was not created. The quantification of leakage ensures compilance with the T.S., and the margin of safety was increased.
.)
** SI-160 PRIMARY CONTAINMENT LOCAL U.AK 4 ATE SUM".8.or . tsiis 1 ;dc 2 REV NO. 004 This revision added tha D,2 e; **y valve's teakase to the inventory teskage The revision: sffected no equipment or components within the plant. ; The ~
requireenents and added provirions tc, .Lep a rv4Ns total of leakage Kwa'Ve is u ert only to keep a current summary of contairement teakage associated with contairunent it.*egrat?1 teakage rates. This revision also rahse ao'r.ru conditions that could affect safety were created. ibe deicted ERCW valves's teakage ' rom.vnysntory requ!iements and char ged tirjting factors (values) for containment teskage as delineated in the T.S. acciptance criteria value for Graminment spray valves . inventory leakage +ve not charned. The 58 stilt provides f v the now vrgin of ser$ty. j requirement. ? 7
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>st 162.2 NW f UNCTIONA:.'iTSilWG P9AULIC AND Mt.CHANICit) - UNiiS 1 W 2[ ,
,. s R6'wo.005 This revision prodded hydraulic snubber seat life history and citelfied This revision did not reduce the);p gin,of,s."Jfety. 7 It' strengthened the
< snethar ical snubber functional t% ting methods. snubber prograre ord increaud' *he,;i;,4 9Irv't
- daf ety. beca:Jsf it prov' fled 4
/ strenger in-service inspecti.srfprogra d kfined in T.S. 3/4.7.9. ' This '
re*ision did not increase the possittli".y' of ar ecci4 tot, because the . 1 7 > j l-
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02/Y/88 51QUOYAn NUC1 EAR PLANI - 10 CfR 50.59 2 s 1987 N C ANNUAL OPERATING REPORT CHANGES TO PPOn EDURt3 AS DESCRIBCD IN THE SAR DESCRIPTION SAFEif
SUMMARY
changes erhanced compliarce with FSAR. CEV NO. 006 This revision was made in accordance with 58-1, Appendia f. This revision This revision did not alter the equipment's desigre or change the FSAR and also added test method considerations for testing the large mechanical T.S. requirements. The probability of an occurrence or the consequences of snubbers and hydraulic snubber seat service-life monitoring program. en accident or metfunction were not increased, and the possibility for an accident of a different type was not created.' The revision strengthened compliance to 7.S. 3/4.7.9 by enhancing ati srsAkser testing sRs.
** 51-164 TESTING SEIPOINT OF SAFETY AND RELIEF VALVES (ASME, SECTION XI, CATEGORY C VALVES)
CtV NO. 009 This revision was made to implement ANS$/ASME OM-1-1931 in accordance with this revision enhanced the safety and relief valve test program. The IVA memo L44 661212 808 instead of power test codes, revision did not af fect the method of safety valve operation and did not (harrje the sw:thod of verif yire valve gerabitity. No defined margins of safety are applicable for the valve eMres*.ed by this 58. The set pressure specifications for these v tves remain unchanged. C* 58-165 CHANNEL FUNCTIONAL TEST Of $15 ACCUMUL ATOR TARHC WATER LEV (L AND PRESSURE INSIRUMENTAll0N (MONINLY)
- UN!!$ 1 AND 2 RED NO. 008 This revisicn deleted the requirement for date-taken signature on att data The scope ond intent of this instruction have not been altered by the sheets and added rack ramber identification in step 7.11.6. deletion of the recpJirement for data-taken signatures and the addition of a rack identification. This revision did not increase the probability of an accident, did not create an accident of a difftrent type, and did not alter any T.S. The margin of safety was not redaced.
** 58-166 $UMMARY Of VALVE TESTS FOR ASME, SECTION MI - UNiiS 1, 2, AND COMMON
- REV No. 011 This revision divided the instruction into parts A, 8, C, and D for the ihls reorganization change did not alter any Section XI code requirements purpose of reorganizing the St+166 valve test program and clarif ying and did not increase the probability of an accident or the malftsection of
Fage Co. 35 02/22/88 SEQUOYAN NUCLEAR PLANT
- 10 Cfa 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFEif SUMMART g Section XI code requirements. In addition, part D contains an appendim equipment. Since this revision did not impact or alter any T.S., the margin containing data sheets for stroke testing att category "A" and "B" valves. of safety was not reduced.
** SI-166.01 FULL STROCING OF CATEGORY "A" and "B" VALVES DURING OPERATION - tmITS 1 AND 2 RED NO. 037 This revision removed data sheets and replaced them with $1-166.6, Valve This reorganization of the instruction did not atter Section XI code Checklist. Individual valve data sheets that will be attached to the Valve requirements and did not impact any T.S. TI.a probability of an accident Checklist are now in SI-166. or malfunction was not increased, and the margin of safety was not reduced.
** 58-166.01.1 FULL STROKING OF CATEGORY "A" AND "B" VALVES REQUIRED IN ALI MODES - UNITS 1, 2, AND COMMON REV bO. 000 This is a new instruction for futt-stroke testing Section XI, Category "A" This change did not atter any Section XI code requirements, and the T.S.
and "B" valves, once per quarter white in any mode. This new instruction response time for safety-related valves within the instruction remained the also reorganized entire 51-166 valve test program to clarify Section XI same. The probability of an accidmt or malfunction was not increased, and code requirements and to inprove the test procedure format. the margin of safety was not reduced.
** SI-166.02 PARTIAL STROKING OF MAIN STEAM ISOLATION VALVES DURING OPERATION - UNITS 1 AMD 2 REV No. 007 This revision deleted the individual valve data sheets from SI-166.2 and This reorganization of the instruction did not alter Section XI code placed them in $1-166. The valve checktist in SI-166.2 will specify which requirements and did not impact any T.S. The probability of an accident or data sheets must be putted from SI-166 for a performance of SI-166.2. malfunction was not increased, and the margin of safety was not reduced.
SI-166.03 fUtt STROKING OF CATEGORY "A" AND "B" VALVES DURING COLD $HUTDOWN - UNITS 1 AND 2 REV NO. 024 This revision deleted the individual watve data sheets from 51-166.3 and This reorganization of the instruction did not atter section XI code placed them in 51-166. The valve checklist in 51-166.3 wilt specify which requirements and did not inpact any T.S. The probability of an accident or data sheets must be putted from $3-166 for a performance of SI-166.3. setfunction was not increased, and the margin of saf ety was not reduced.
Page No. 36 02/22/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
g SI-166.03.1 FULL STROKING OF POWER OPERATED VALVES REQUIRED OPERABLE DURING ALL NODES - UNITS 1 AND 2 REV NO. 000 This new instruction is for fut t-stroke testing Section NI, Categories "A" This instruction did not alter any Section XI code requirements, and the and "B" valves, once per quarter whi te in cold s'natdown. This new T.S. response times for these valves remained the same. The probability of instruction also reorganized entire SI-166 valve test program to clarify an accident or malfunction of equipment did not increase. The T.S. Section XI code requirements and to irprove test procedure format. remained unchanged, and the margin of safety was not affected.
$1-166.03.2 f ULL STROKING OF RNR VALVES FCV-Tel AND FCV-74 UNITS 1 AbD 2 REV NO. 000 This is a new Si for the full-stroke testing of Section MI, Category "A" This instruction did not atter any Section XI code requirements, and the RMR valves FCV-74-1 and FCV-74-2, during starttp, shutdown, and cold T.S. response times for these vetves remained the same. The probability of shutdown. This was necessary because of a reorganization of the entire an accident or malfunction of equipnent did not increase. The T.S.
51-166 valve test program to clarify Section NI code requirements, and to remained unchanged, and the margin of sa'ety was not af fected. inprove test procedure format. SI-166.06 TESTING OF CATEGORY A & 8 VALVES AFTER MAINTENANCE OR UPose RELEASE FROM HOLD ORDER - UNITS 1 AND 2 REV NO. 022 This revision removed . lata sheet and replaced it with 51-166.6 valve This reorganization of the instruction did not alter Section XI code checklist. Individual valve data sheets are now in SI-166 and will be requirements and did not impact any T.S. The probability of an accident or attached to the valve checklist. malfunction was not increased, and the margin of safety was not redxed. CD SI-166.08 IkCREASED FREQUENCY TESTING OF CATEGORY "A" AND "B" VALVES - UNITS 1 AND 2 REV NO. 006 This revision removed the data sheet and replaced it with 58-166.6 valve This reorganization of the instruction did not alter Section NI code ched t ist . Individust valve data sheets are nuw in 58-166 and witt be requirements ord did not inpact any T.S. The probattlity of an accident or attached to the valve checklist. malfunction was not increased, and the margin of saf ety was not redxed. Page No. 37 02s22/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANCES TO PROCEDURES As DESCRIBE 0 IN THE SAR DESCRIPTION SAFETY SUPNARY , C* SI- TM.12 SIS /RHR/ UNI CNECE VALVE OPENING TEST - UNITS 1 AND 2 REV No. 013 This revision was made to require the flow rates used in the T.S. The test method was not changed. The revision required additional flow to meet rambers listed in the T.S. and to meet NRC requirements in the ASME, Section MI, gasp and valve safety evatuation report. The probability of an occurrence or the consequences of an accident or matf m etion were not increased, and the possibility for en accident of a different type was not created. The acrgin of safety, as defined in the basis of any Y.S., was not reduced.
- SI-1M.21 FULL STROKING OF THE Capet0N ERCW AND CCS CATEGORY "A" AND *B" VALVES DURING OPERATION - UNIT G REV No. 012 This revision deleted the individual valve data sheets f rom SI-1M.21 and This reorganization of the instruction did not atter Section XI code placed them in SI-1M. The valve checklist in SI-1M.21 will specify which requirements and did not isp t any T.S. The probability of an accident or data sheets must be putted f rom SI-1M for a performance of SI-1M.21. matimetion was not increased, and the margin of safety was not reduced.
- SI-1M.22 SAFETY INJECTION CHECK VALVE TEST DUR ANG COLD SHUTDOWN - UNITS 1 AND 2 REV NO. 009 This revision added ref erences and precae*lons, agidated Data Package Cover The restriction of adding no more than 10 settons of desineralized water to Sheets, rewrote the requirement section, and specified that no more than 10 the SIS did not require the safety injection pumps to run on recirculation.
gatlors of demineratired water be added to the SIS. The reactivity was not increased enough to require the pumps to be run. These changes made the instruction more conservativt. The probability of an accident was not increased, and the possibility of an accident or metfunction of a different type was not created. i
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- SI-166.23 ERCW CNECK VALVE TEST DURING COLD $NUTDOWN UNITS 1 AND 2 REV NO. 004 This revision added references, reworked the requirement section, Making the changes listed in the change description did not increase the incorporated the data sheets into the instructions, updated the Data probability of an accident or malfmetion and did not reduce the margin of Package Cover Sheet, added steps to remove and replace pipe caps, added safety, as defined in the basis of any T.S.
statement about 51-158.1 being performed if the valves fait, added that a work requnt be written if they f ait, and added unit, mode, and date to top of data sheets.
- 53 166.24 ERCW CNECK VALVE Test DURING OPERATION - UNITS 1 AND 2 REV NO. 004 This revisico combined the instructions and data sheets, added a statement Adding the precaution stating that if the telt is In modes 1-4, the removal about initiating a work request to remove and rep 8 ace the pipe caps, of the pipe caps requires compliance with LCO 3.6.1.1 to maintain revised the Data Package Cover $heet, and added references and containment integrity, and adding the precaution requiring the pipe caps to prerequisites. It a W ed a precaution which states that if the toit is in be returned to their "As found position no later than one hour af ter they modes 1-4, the removal of the pipe caps regJires comptience with LCO were initially taken off, increased the margin of safety.
3.6.1.1 to maintain containment integrity. This revision was made to correct deficiencies in technical adequacy.
- 58-166.26 COMPONENT COOLING WATER CdECK VALVE TEST DURING OPERATION - UNii$ 1, 2, AND COMMON REV NO. 005 This revision clarified the instruction by combining the instruction Bringing this instruction into compliance with 58-1, Appendia F, by ,
section and the data sheets, making the test description clearer, todating combining the instructions and data sheets, clarifying the test the refere r.es, and adding signoffs for both SR0s and UOs. This brought description, todating the references, and adding SROs and UOs signof fs, did the instruction into comptience with SI-1, Appendin F. not increase the possibility for an accident or malfunction not previously evaluated in the SAR. These changes did not involve any T.S. The margin of safety was not reduced. Dage No. 39 02/26/88 SEQUOTAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANhUAL OPERATING REPORT CHANGES TO PROCEDUeES AS DESCR!gED IN THE SAR DESCRIPTION SAFETY
SUMMARY
4 SI-166.27 PRIMARY WATER CHECK VALVE TEST DURING COLD SNUTDOWN - UNITS 1 AND 2 RED NO. 005 This revision changed the reference section, contined the data sheets and The possibility for on accident or metfunction of a different type other instructions, corrected gransnatical errors, and added a statement about the than any previously evaluated in the SAR was not created by revising the T.S. applicable modes of this St. These changes brought the SI into references, requirement section, combining the data sheets and , conptiance with the SI-1 , Appendia f. 51-158 may also be performed to instructions, and correcting grassmatical errors. If 51-15J1.1 is performed futfitt the requirements of this SI. in lieu of this test, it is to be noted on the Data Package Cover Sheet of this test. No T.S. was changed or af fected by this instruction. The margin of safety was not reduced. 5t-166.30 VCT CV VALVE TEST DURING OPERATION (62-504) - t> NITS 1 AND 2 PEV NO. 002 This revision changed the format of the instruction to a format consistent valve 62-502 is normally closed. The valve is not operated in any wey. It with other 5!s and added normatty closed valve 62-502 to the intrist system is enty verified in its proper position. This step is being added as a Linet , verifications. precautionary measure to ensure minimet water loss during testing. Changing the format of the procedure brings this instruction in line with other SI formats. Because there is no change in valve alignment and valve 62-502 is verified closed, the possibility of an accident or metitnction of a different type has not been increased. Because valve 62-502 is maintained closed, the margin of safety, as defined by T.S., was not reduced.
** 51-166.31 ff EDWATER CHECK VALVE TEST DURING CotD SMUTDOWN - t)MITS 1 AND 2 REV NO. 002 This revision W ded steps to record steam generator levet before the test The test method has not changed. This revision has made the procedure more and after waiting 30 minutes. It also edsed acceptance criteria of tess conservative in verifying that the check valve closes. The probability of than a 5 oercent drop in 30 minutes. an accident or metfunction was not increased, and the possibility for an
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SUMMARY
i defined in the basis of any i ~ . was not reduced.
** 51-166.35 UNI CHECK VALVE OPENING TEST DURING REFUELING OUTAGE - (MITS 1 AND 2 REV Wo. 003 This revision changed the format in acevrdance with 51-1 and included This test is performed after the w r head injection spool pieces are actions that are to be taken if valves fait the test. It also edoed removed and the valves are exercised after being removed from the system.
signoffs for ett prere g isites. The valves are tested when they are not required to be operable. Secause no charges were made in the performance of the test, the probability of an accident or malfunction was not increased, and the margin of safety was not reduced.
** SI-166.36 DIESEL 57aRTl#G 41R VALVE TEST - UNITS 1, 2, AND C0pequN REV #0. 006 This revisicn was made to attow testing of only two valves per D/G start. The probability of an occurrence or the consequences of an accident or The other two starting motor sets are isolated to ensure the 0/G starts metfunction of equipment were not increased. The procedure did not cause
^
with the twa air start volves being tested. any new series of events not previously evaluated. The mergin of safety, as defined in the basis of any T.S., was not reduced.
** 51-166.38 INSPECT 10W OF DIESEL GENERATOR ERCW DISCMARGE CNECK VALVES - UNITS 1 AND 2 REV NO. 003 This revision deleted system tincte prior to inspection, deleted System lineup prior to valve inspection was accomplished by rewiring that verification of flow af ter valve inspection, and added acceptance criteria. a clearance be established in accordance with Al-3. Full flow through each check valve is verified quarterly by 51-166.45. These changes did not create any new accident scenarios.
** S I - I t,6.40 P9E55URIZER PCRV AND 8 LOCK VALVE OPERA 81LITY TEST *>NIIS 1 AND 2 REV W9. 001 This revision remove $ data sheets and specific test instructio s and placed This change did not atter any Section NI code rcquirceents. Reorganization
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SUMMARY
g them in a single instruction, SI-1M. This clarified Section El code of this instruction did not create a tra accident or selfmetion. because - requirements and improved test procedure format (part of St-1M series section XI code requirements have not been affected. The PORV T.S. was not rewrite). This also renoved the 96-hour review requirement on the Data ispected by this char.ge, and the mergin of safety was not reduced. Package Cover sheet. This requirement applies only to Section NI pump tests.
- S t -1M.41 REACTOR NEAD WENT VALVE STROKE TEST DURING A REFUELING OUTAGE - UNITS 1 AND 2 REV NO. 000 This is a new testruction to stroke test the reactor head went system block The reactor head went. system vetves wilt be esercised in made 5 with RCS and throttle valves to satisfy the ASME, Section NI, valve test pressure suf ficiently high to ef fect a btW. This witt not increese requirements. Valves will be timed remotely and tested acousticatty to the probability or consowes of an accident since laetation capability verify that remote indicators accurately reflect valve operation for each is maintained during testing. (Block valves can be closed tAlte throttle reactor operator. valves are stroked and vice verse.) The margin of safety wilt not be affected, because the system is designed to vent noncondensibles from the teper head region to promote natural circulation for accidents that might occur in modes 1, 2, or 3. Exercising the valves will not creete an menetyred conditiers, since the system is capable of being isolated in the ..
event the valves fait.
- $1-1M.45 FULL STP0 TING OF THE DIESIL GENERATOR ERCW CHECK VALVES - UNITS 1, 2, AND C0 pee 0N REW No. 000 This is a new instruction to futty stroke the D/G ERCW check valves. The normal and alternate cooling water paths will be checked in the designed alignment en ensure that there is no blockage from the check valves binding. Because the designed alignment is used, there is no increase in the probability of an accident. The designed aligrument is used and checked to verify that it can perform its fmetion. The possibility of a' dif ferent type of accioent is not created. It is also being tested to .
ensure that the mergin of safety, as defined by T.S., was not reduced. a
.- - ~ . . ~ . - - . , . . ~ - . . . . . _. .- - . - - - .. _ _ - . - . - -- , . _ . - . .
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SUMMARY
g
** 51-166.46 NORnAL CHARGlWG LINE CHECK VALVE IEST DURlbG COLD SMUTDOWN (C1) - UNils 1 Am 2 REV ho. 000 This instruction verifies closing of the norset charging line check valve this instruction implemented the comunitment made to the NRC concerning the 62-543 in the CVCS. This will be acconptished by applying pressure f rom a ASME, Section MI, pump and valve program.
test rig to close the check valve.
** SI-107 flRE HEADER VALVE LINEUP INSPECTION - UNifS 0, 1, AND 2 REV NO. 019 This revision deleted att non-i.s. valves and dropped tocked requirement The probability of an occurrence or the consespences of an accident or for valves which are now doutAe verified as being seated. matfunction were not increased. The possibility for en accident or metfunction of a different type was not created. The margin of safety is enhanced by the seating of att valves.
** St-169.1A PERIODIC CALIBRAfl0N OF DIESEL GENERATOR INSTRUMENTS IN CONTROL ROOM A s AUMILIARY CONTROL ROOM - UNiiS 1 AND 2 REW NO 000 This instruction was written to establish the f requency of every 18 months The probability of an accident was not increased, and the possibility for for the calibration of the D/G instruments, an accident of a different type was not created. The margin of safety was not reduced, because the compliance instruments in $1-169.1A do not have
. T.S. setpoints or tolerances in 11-54
** $1-169.18 PERIODIC CALIBRAi!ON Of DIESEL CENERATOR INSTRUMENTS IN CONTROL ROOM As AUMILIARY CONTROL ROOM
- UNIIS 1 Am 2 REV NO. 000 This instruction established the frequency of every 18 months for the The probability of an accident was not increased, and the possibility for calibration of the D/G instrtments. an accident of a different type was not created. The margin of safety was not reduced, because the compliance instruments in $1 169.18 do not have T'.S. setpoints or tolerances. They are calibrated to meet the tolerances in TI-54.
6 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ __ _ __ _ _ _ _ _ -- - _ - ~ . _
.. - _ . . . . _ _ __ . _ _ _ _ _ . m ._ _. _.
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SUMMARY
g SI 169.2A PERIODIC CALIBRATION OF O!ESEL GENERATOR INSTRUMENTS IN THE CONTROL ROOM AND AUXILI ART CONTROL ROOM - UNITS 1 AND 2 REO NO. 000 This instruction established a frequency to calibrate the 0/G indicating This procedure established a frequency to calibrate the indicating instrianents in the control room and auxiliary control room. Instruments and to verify that they are calibrated. The probability of an accident is not increased. No new possibilities for an accident or malfunction were created, because the procedure ensures that att instruments are calibrated correctly and that a functional test is performed af ter the calibration to verify the instrtments are returned to service. The margin of safety was not reduced, because the compliance indicating instruments in the procedure do not have T.S. setpoints or tolerances but are calibrated to meet the tolerance in TI-54. REV NO. 001 This revision added wire designations, added acceptance criteria to the The wire designations added to this instsvetion ensured disconnected wires data sheet, and changed the sequence of data sheets. were property identified for reconnection. The addition of the acceptance criteria to the data sheet and sequence change of the data sheets enhanced the instruction. The probability of an saccident of a dif ferent type was not created. These changes in no way reduced the margin of safety, as defined in the basis of any T.S. SI-169.29 PERIODIC CALIBRATION OF DIESEL GENERATOR INSTEUMENTS IN THE CONTROL ROOM AND AUXILIARY CONTROL ROOM - UNITS 1 AND 2 REY NO. 000 This instruction established a f requency to calibrate the dieset generator The probability of an accident was not increased, because this instructi u indicating instrtsnents in the control room and the munitiary control room. established a f requency to calibrate the indicating instruments and to verify the instruments are calibrated correctly. No margin of safety is r ed. These instruments do not have T.S. for setpoints or tolerances.
Cage ko. 44 02/26/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPtRATING REPORT CMANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
reduced. These instruments do not have T.S. for setpoints or tolerances.
- SI-174 FIRE SYSTEM $ PRAY AND/OR SPRINKLER SYSTEM TESTABLE VALVE CYCLING - UNITS 1 AND 2 RE7 =0. 006 This revision a:Med a statement to give exemption for performance if The clarification made to this instruction and the addition of FCV 26-243 SI-166-1 is in frequency, clariflad the acceptance criteria, and added did not change the intent or the ef fects of the perforsunce of this test.
FCV-26-243 dich had been omitted. Therefore, there was no increase in the probability of an accident or metfunction of equipment, anri the margin of safety was not reduced.
- SI-175 LOW-PRESSURE CO2 SYSTEM LEVEL AND PRESSURE VERIFICATION - UNIT 0 REV I:0. 004 Changed organizational designation f rom FQE to CEEC and unit designation on The changes indicated did rut affect the performance or intent of the title page from units 1 and 2 to unit 0 in accordance with Appendin F of instruction. The changes rade were for administrative erAancemeret only.
53 1. Therefore, the probability or consequences of an accident or malftriction were not increased, and the margin of safety was not redaced.
- SI-177.3 SPRAY AND/OR SPRINKLER SYSTEMS FUNCTIONAL - UNIi: a. 1, AND 2 REV No. 005 This revision added the requirement for both unit SRO's approval and made This revision reduced the probability of an accident or malfmetion, and no corrections and clarifications to the instruction, new accident or malfmetion was created. Tie margin of safety, as defined in the basis of any T.S., was not reduced.
- SI-178 MOVEABLE DETECTOR DETERMINATION OF JUADRANT POWER TILT RATIO - UNITS 1 AND 2 REV NO. 004 This revision was made to ensure compliance with LCO 3.3.3.2, to Complying with the T.S., implementing Westinghouse recomendations, incorporate Westinghouse recomendations to atlow use of the incore attowing use of incore conputer code, and generet clarification ensure co.gn;ter code, to add a reference section, and to provirte additional monitoring of Guadrant Power Tilt Ratio and do not reduce any T.S. margin clarity. of safety or increase the probability of an accident.
e
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** SI-180 FIRE PUMP START TEST - UNITS 1 AN9 2 REV NO. 008 This revision changed the time required to perform the test from 2 hours to The margin of safety for this instruction was actually increased. This 1 hour, added step to place fire pumps not being tested in "STOP" prior to ensured that LCO 3.7.11.1 is entered when the fire pumps control switches beginning of test, and provided SRO signof f blan6.s for when the LCO is are placed in "STOP" and that the action of the LCO is comptied with. The entered and exited. Reference CAOR SQQ 870399 SIT. This change also probability of an accident ce malfunction was not increased. The margin of' included correction of various typographical errors. safety was not reduced. ** SI-181.5 n!CN-PRESSURE FIRE PROTECTION STRAINER CLEANING / INSPECTION (18 MONTHS OR REFUELING OUTAGE) - UNIT 2 REW NO. 002 This revision added 7.5. information to the scope and added a signof f for The addition of acceptance criteria to the 6*-ope of this instruction did the SE prior to beginning the test. not affect the probability of an accident, the oossibility for an accident of a dif ferent type, or the margin of safety. ** SI 182.1 EMERGENCY GAS TREATMENT STSTEM A & B ELAPSED TIME METERS CALIBRATION VERIFICATION - UNITS 1 AND 2 REV NO. 001 This revision added verification try a second person, corrected nuntering This instruction verifies calibration of the elapsed time meters. The test and format, and added information to clarify the instruction. will'not af fect operation of the EGTS fan or filter trains. The regairement to verify calibration of the seter is not addressed in the FSAR. The changes made to laprove the procedare did not af fect operation as described in the FSAR and did not af fect the acceptance criteria. The margin of safety was not reduced.
REV NO. 002 This revision changed 6 percent to 1 percent on page 5, step 5.2.2.6. This SI does not satisfy a T.S. but catitrates a compliance instriment used to fulfitt SR 4.6.1.8.A and SR 4.6.1.8.C. The margin of safety as defined in the basis of any T.S. was not reduced by correcting the percent nudwr.
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SUMMARY
** SI-182.2 AUXILI ARY BUILDING CAS TREATMENT SYSTEM A AND 5 ELAPSED TIME METERS CALIBRATION VERIFICATION - UNITS 1 AND 2 REV No. 000 This instruction was written to verify calibration of the ABGTS elapsed The meter does not affect the operation of 4 e fans and filter trains. The time meters. The ABGTS filters are required to have samples of the requirement to verify the meter is not addressed in the FSAR; verification charcoat taken after 720 hours. The meter on the filter is to be verified of the meter will not af fect operation as described in the FSAR. The on an 18-month cycle as a covtience instrument. Since the minisua testing of the meter is performed by monitoring its function during the division on the meter is 1/10 of 1 hour, a tolerance of +/- 1 percent for 10 hour run and verifying it against a calibrated time source. There are the 10-hour required run is used to verify proper operation. no connections or conditions that might degrade the equipment; no new accident condition can occur. The use of +/- 1 percent tolerance on the meter is consistent with the capability of the equipment and ensures an extremely corrervative nLaber to meet the NRC SR.
H SI-183 LOWER CONTAINMENT GASEOUS AND PARTICULATE RADIOACTIVITY MONITORING DURING PERIODS OF RADIATION MONITOR IMOPERABILITY - UNITS 1 AND 2 REV No. 006 This revision included title changes because of organizational changes and These are only title and format changes to the instruction in this revision clarificati m of the instruction by format changes. because of SI-T, Appendix F. These changes in no way increased the possibility of an accident or malfunction and did u>t redxe the margin of safety, because the changes did not effect any T.S. or acceptance criteria.
** SI-185 FIRE NOSE CONNECTION CONTROL VALVE OPERABILITY TEST - LMITS 0,1, AND 2 REV NO. 006 This revision corrected organizational designations, added requirement for The changes did not af fect the intent or result of the instruction. These SRO approvat prior to testing, corrected mit designation en title p.ege, changes brought the procedJre into compliance with $1 1, Agpendia F. The and corrected typographical errors in the instruction. The revision was margin of Safety was not reduced, and the probabitity of an accident or made in accordance with SI-1, Appendin F. malfunction was not. increased.
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** $1-117 CONTAINMENT INSPECTION - UNIls 1 AND 2 REV No. 007 This revision was made to verify the closure and the securing of the polar The doors have been verified previously in 501-88, and the new drains have crane watt doors and to add information on the new drains in the No. 3 and been analyzed per WP12369. These revisions ensure there is no decrease in No. 4 acctmutator rooms. the margin of safety. The probability of an occurrence or the consegeences of an accident or metfunctions were not increased.
** $1-188.2 EMERGENCY GAS TREATMENT SYSTEM CONTAlhMENT ANNULUS PRESSURE CONTROL REV NO. 000 This is a new instruction which provides a more comprehensive checkout of The probability of an occurrence or the consegJences of an accident or the contairunent amulus pressure controt functions of the ECTS. malfunction of egalpment Esportant to safety previously evaluated Irt the SAR were not increased. No new possibility of an accident was Created.
The margin of safety, as defined in the basis of any T.S., was not reded.
** SI 189 PERIODIC CAllSRATION OF CONDENSATE SYSTEM COMPLIANCE INSTRUMENIS - (JNIIS 0 AND 1 REW No. 008 This revision changed instructions f or F-2-256 and F-2-257 because of a The new instruments tag. oved reliability and accuracy. The T.S. bases do change in the instrament type and revised the vacutse pump rotometer not apply to the condenser vacuum exhaust instruments. The margin of instructions, safety, as defined in the basis of any T.S., was not redaced.
** SI-190 flRE HOSE STATIONS INVENIORY - UNITS 1 AND 2 Rett No. 010 This resisjon added mode applicability, added Data Sheet 5 for temporary This revision added Data Sheet 5 and clarified the instructions for -
hose instaltatlens, and clarified instructions. p iormance. No new methods of inspection have been created, and the acceptance criteria has not been changed. This revision also clarified the mode applicability and instructions pertaining to the inspection of tempc*ary fire hoses. The T.S. for this instruction has not changed. The
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SUMMARY
probability of an occurrence or the consegaences of an accident or estfiriction were not increased. The margin of safety was not rechJced.
** SI-193.2 CONTAINNENT BUILDING AND AuxlLI ARY SUILDING VENTILATION SYSTEMS - UNIT 2 REV No. 000 This instruction was written to provide for the calibration of unit 2, No T.S. timits were affected, and no abnormat plant operating conditions system 30, instruments which previously were scheduled for calibration by were created by this instruction. When equignment is made inoperable, .
53-193, redsviant 100 percent capacity e<pipment is avaltable for service. The margin of safety, as defined in the basis of any T.S., was not redaced.
** 58-195 PERIODIC CAtjBRAfl0N OF FLUID COMPONENTS, INC. FLOW SWITCNES (5YsTEMS 30, 31, 65) (SEMI-ANNUAL) - tJulTS 0,1, AND 2 REV NO. 003 The calibration sheets for the EGIS flow switches were revised to verify These changes erhanced the procedure and ensured the a @ licable contact action and to change setpoints on Fs-65-31-A/S, -s/A and instrumentation operated as designed. The setpoint changes for fS-65-55-A/s, s/A. fs-65-31-A/s, -s/A and is-65-55-A/s, -s/A are in accordance with the latest TVA drawing?. The pretability of an accident was not increased,'and the gxnsibility for en accident of a dif ferent type was rw>t created. The margin of safety, as defined in the basis of any T.S., was not reduced, ** si 198.2 CALIsRAi!ON OF COMPLIANCE & TECHNICAL $PECIFICAi!ON INSTRUMENis (10 peowins) - UNIT 2 REV No. 000 This instruction was written to calibrate the unit 2 instruments previously There were no changes to plant setpoints or T.S. timits. The probability calibrated mder SI-198. It also clarified work instruction and deleted of an occurrence or the consequences of an accident or motfunction of instrssments which are no longer identified as compliance instruments. egaissnent were not increased. The possibility for an accident or ,
metfunction of a different type than any previously evaluated was not
- created.
__ ._ __._ _ _ _ _. _m. _ . _.. . . _. .m_ _ _ , m. . _ _ _.. _ . _ . ._m m. ._. . Face No. 49 02/22/88 SEQUOYAN NUCLEAR PLANT 10 Cf a 50.59 1987 NRC ANNUAL OPERATING REPORT CMANCES TG PROCEDURES AS DESCRISED IN TNE SAR DESCRIPTION SAFETY
SUMMARY
g i l
** S1-196.3 CALIBRATION OF SMIELD, AUMILIARf, AND SERVICE gUILDING GASEOUS Ef fluent IS0 KINETIC SAssPLING SYSTEM EEV NO. 000 this SI was created to ensure proper calibratius of shield. auxitlery, and The probability of an occurrence or the consequences of an accident were service building gaseous ef f tuent isokinetic sancting system. not increased. No new possibility of an accident was created. The margin of safety, as defined in the basis of any T.S., was not reda:ed.
L
** SI-204.2 FUNCTIONAL TEST iOR RADIATION MONITORING SYSTEM (MONTNLY) - UNIT 2 REV 800. 006 This revision clarified steps for measuring high voltage and proper .This revision clarifies instruction steps and arrsures that data is recorded annunciation, added note to instruction attowing loops to be tested as intended. It is needed to ensure thet the procedure can he uorted as ~
li4.Miy, added high voltage tolerance valves, and corrected written. Placing a tolerance on the high voltage value of the detector gransnatical errors. will help to ensure that the calibration of the radiation monitor channel. ! does not drift. This revision did not decrease the margin of safety and did , not increase the probability for an accident.' It did not create the l possibility for an accident or malfunction dif ferent from that previously l evaluated. l l SI-206.2 RADIATION MONITORIIeG SYSTEM SAMPLE FLOW EALISRATIONS AND FUNCT10NAL TESTS - UNIT 2 (12 UEEKS)
- REV NO. 011 This revision cancetted the instruction. To improve the organization and performance of testing of the radiation.
monitoring system sample flow instrumentation, an integrated revision of SI-206, 51-206.2, SI-302, and SI-302.2 was developed along with the l addition of two new tests: SI-206.3 and SI-206.4 The testing of gaseous radiation monitors was moved to 58-302 and 51-302.2. The testing of l pretsvre gauges contained in gaseous radiation monitors was moved to SI-206.3 and SI-206.4. Two new tests were written to calibrate rotometers. Non-T.S. CSSC tiquid and particulate CAM radiation monitors were moved to a l I periodic e,intenance program. . These organizational changes lef t only the _ _ _ _ _ _ _ . __ . . _ . . _ _ _ _ _ - . -_ _ . _ .- .- . . ~ . _ _ - _ . - - _ _ . _ - _ - . . - - .. ,
.m _ .m_ mm _ __ _ __ _.m_ mmm . __..._m __ _ =, _ . _ _ . _ _ - . , . ._. 8'ege h. SU 02/22/88 51OUOYAM NUCLEAR PtANI 10 CiR 50.59 1987 NRC ANNUAL OMRATING REPORT CHAN(,ES TO PROCEDUPES AS DESCRI9fD IN THE SAR DESCRIPTION SAFETY
SUMMARY
g tiquid radiation monitors for which there are T.S. SRs to be addressed ty. 51-206 and 51-206.2. Because there is only one tiquid radiation monitor in unit 2 that fatts under this category, the testing of this monitor was added to 51-206. These changes attowed cancetlation of $3-206.2.
** SI 206.3 RADI ATIOl MON!iORING SAMPLE FLOW INDICATOR AC VACUUM GAUGE CALIBRATION - LJNITS O AND 1 REV NO. 000 Yhis new instruction was written to resolve CATS 86T00 by calibrating This test was performed by connecting a Nes standard to the radiation radiation monitor flow rotoreters and vacusse gauges in place. monitors intet test tees. The test complies with the LCoe associated with each monitor and ensures the proper removat and the return to service of egJipment tested. This test ensures that gauges used to meet T.S.
requirements are property certified to a spxified accuracy, thus increasing the margin of safety. SI-206.4 RADIATION MONITORING SAMPLE FLOW INDICATOR AND VACUUM CAUGE CALIS<ATION - LJNIT 2 (550 DAYS) REW NO. 000 This new instruction was witten to resolve CATS 86T00 by calibrating This test was performed by connecting a eJ85 standard to the radiation radiation monitor flow rotometers and vacuum gauges in place, monitors intet test tees. The test complies with the LCOs associated with each monitor and ensures the proper removat and the return to service of equipment tested. This test ensured that gauges used to meet T.S. recpirements are property certified to a specified accuracy, thus increasing the margin of safety.
** 51-209.2 81 aIODIC CAllgeAil0N of VOLT MEIEks IN A550CI ATLD E LECTRICAL SYSTE MS 120V ac,125V t.: 480V, 6.MV (18 MONIN5) - UNIT 2 #EY NO. 002 This revision made the acceptance criteria consistent with the DP50 field I@ pobability of an accident was not increared, because the change test annust. verlev.s that the instruments are calibrated within the required timits in theIc*> # ifetd test assual. Sirce the isntrusents do not perform any
Page Oa. 51 02/22/88 SEQUOYAM NUCLEAR PLAMI 10 CfR 50.59 1987 NRC ANNUAL OPERATING REPORT CMAfL;ES TO PROCEDURES A$ DESCRIBED IN THE $AR DESCRIPflON OAfETY
SUMMARY
eqJipment protection function, the possibility for an accident or malfemction of a dif fermt type was not created. 1%e margin of safety, as defined in the basi? ef any T.S., was not redred.
- 51-212 ECCS 1MRO11LE VALVE MECHANICAL STOP POSITION - UNITS 1 AND 2 REV No. n17 This 58 incorporated organizational acronym changes f rom QA to OELC and Gese cresnges did not af hct the intent or performance of this instruction conplies with SI-1, Appendia F. and did not reduce the eersin of saf ety or ircrease the probebility of an accident. The intent or scope of the instruction was not altered.
- $1-213 NON-INDICATING ROD POSITION DETERMINATION - UNiis 1 ANC 2 REV NO. 001 This revision incorporated requiresents of SI-1, Appendin F, ensured Ensuring coopliance with T.S. and attoNing calculation of more than one comptience with T.S. functices by afnsuring acceptance criteria, referenced nonindicating rod in no way increased the probability ef an accioent w the appropriate LCO, added a catrutation to ensure rods are within revssired matfunction. Er.suring comptlance with T.S. to make s are at t rendrments timits, and attowed determination of more than one rod position, are enforced do not reduce the margin of safety.
- 51-218.1 pea!0DIC CAttsaATION 05 REP UNDERfREQUENCY RELAYS - UNIT 1 REV NO. 001 This revision added St-230.1 in the reference, added a statement in the This revision erwures that the Rs are futfitted. The probability of an scope that 51-230.1 is needed to wnptete the SR, and added information to accident was not increased, and the possibility for an accident or clarif y and to er*ance the proce<%re. malfunction of a dif ferer:t type was not created. The margin of safety, as defined in the basis 66 the 1.S., was not reduced.
" 58-218.2 PERIODIC CALIBRAI!ON OF RCP L;NDERf REQUENCY REL AYS - UNIT 2 ety NO. 031 This revioon ad$cd si-230.2 in the reference, swided a statred in the this revision en w es that abe 5as are fulfilled, the pedudaitity of an scope that SI-230.2 is rMrd to convicte the SR, and wikd inf oroution to accident wo2 not increased, Aru1 the possibility for on accident or
.. . - - . .- . - . - - . . . . . . _- - _~~ -, .. .- . . . . . - -
Page No. 52 02/26/88 SEQUDYAN NUCLEAR PL*VT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PR(X1DURES AS DESCRIBED IN THE SAR DESCRIPTION $AFETY
SUMMARY
I clarify and to er*ance the procedure. metfunction of a different type was not created. The margin or safety, as defined in the T.S., was not reduesd.
** $1-220.1 AUTOMATIC LOAD SEQUENCE TIMER fuhCTIONS TEST - UNIT 1 REV NO. 004 This revision brought the proce &re into compliance with SI-1. Aprendia T, The generat methodology of the test was not changed. The probability of an added a statement concerning the MTE required specifications, aMed SRO occurrence or the consegJences of an accident or matfunction were not approval, and added UO notification as applicable for common equipment. increased. The possibitity for an accident or matf metion of a type different than that previously evatusted was not created. The margin of safety, as defined in the basis of any T.S., was not re&ced. ** 51 220.2 AUTom4 TIC LOAD SEQUENCE TIMER f UNCTIONAL TEST - UNIT 2 RE'r No. 004 This revision corrected deficiencies identified by SI-1, Appendia F. This Analysis of C'# increased time delay demonstrated no increase in revision also included applicable modes, MTE specifications, operations prot, ability of an accident or metfunction. The changes in this revision notification and approvat, and more concise direction regarding MTE did not change test intent or methodology. Other changes served to ensure conrections/ disconnections and contingency f or unset "As found" data. It ccmptience with T.S. requironents. The mergin of safety was not re&ced.
also included a chant? to CSP tiac delay from 30 seconds ta 180 seconds (ECW L6715).
** SI-228.2 PERIODIC TUNCTIONAL TE$T Of RCP UNDERVOLTAGE RELAYS - UNIT 2 REV No. 000 This instruction was written to replace 51-228 for unit 2. SI-228.2 Aas SI-228.2 accomplished the same function as SI-228. The added steps in steps which are not in 51-228 and which will verif y the uniervottage relays 51-228.2 improved the functional test. No new accident possibilities were actuate arproximately at their setpoints. created. SI-228.2 verified that in the required mode, the required three ,
of the four undervoltage chenets will be in service at att times daring , the test.
- n. - _. _
- __ _ m _ _ _. . __ . _ _ . _ _ _ .. . _ . _ m _ _ _ _ _ . _ _ _ _ _ _ .m _ _-- _
Page me. 53 Ou23/88 SEQUOYAN NUCLEIR PLANT 10 CFR 50.59 1987 mRC AmuuAL OPERATING REPORT CMAmMS TO PROCEDURES AS CESCRIBE0 IN THE SAR DESCRIPTION SAFETY StDetARY j
*o SI-230.1 PERIODIC FUNCTIONAL TFST OF RCP UNDERf REQUENCY RELAYS - UNIf 1 REW h0. 001 This revision added signof f s for removing the undervottage relay connection The probability of an occurrence or the consequences of an accident were blocks, deleted the referenced relay setting sheet raaters, and referenced not increased, because the change ermances the procedure by h =*nting the LER 1-M-015. removat of egaissment. At refueling, LER 1-86-015 prevents the removat of' information required by the LER in the original procedure. The margin of saf ety was not reduced, because the revision verifles the relays are tested according to T.S. requirements.
** 15+230.2 PERIODIC FUNCTIONAL TEST Of REP U4 DER FREQUENCY RELATS - UNIT 2 REW mo. 001 This revision added signof fs for removing the undervoltage relay connection The probability of an accident was not incressed, because the changes t>tock, deleted the referenced relay setting sheets, and referenced enhance the procedares by documenting the removal of equipamnt and by LER-86-015. referencing LER-1-86-015 editch will prevent the removat of information required by the LER in the original procedare. Deleting the relay setting sheets eritt not af fect this procedure, because setpoints are taken from T.S. There are no new possibilities of creating an accident or metfunction of a different type, because the revision did not change the method of testing or the precautions required dJring testing. The margin of safety was not reduced, because the revision verifies that the relays are tested according to the T.S.
** 51-233.1 VISUAL IE5MCit045 OF PEmETRATION FIRE gARRIERS + MECnANICAL SYSTEM 302 (PENETRAT10as) - UntTS 1 Amo 2 REW #0. M2 This revision changed the scope to include references to other 51s required These changes did not alter the intent or testing of this instruction.
to comtete SR 4.7.12.a. and included the requirement to visualty irspect they did not increase the possibility of an accident and did not reduce the alt mechanical piping and conduit penetrations in the fire tone bourvjary margin of safety, because no T.S. esas af fected by the changes. f l
.w - - . . . - . _ - . -_ . _ _ ~ . .- . --._- . ~-- - . . - - ~ . - - . .= . -
l I l Dage No. 54 02/32/88 SEcuoYAW NUCLCAR PLAuf , 10 CFR 50.59 1987 teC AmuuAL OPERATING REPORT l CNAmCES TO PROCEDURES AS DESCRIBED IN TNE SAR ' t DESCRIPfl04 SAFEif SUMMART ; surf aces instead of a specific ramber of penetrations. 53-233.4 vi$UAL IW5PECil0W OF INERRAL FIR $ BARRitRS l a00 #0. 004 This revision was made to implement the necessary sketched drawings into Att the fire barrier penetrations meet the regaired fire rating, and the 51-233.4 43 as a replacement and addition to esistins ir.teraction raabers. con & sits impacted are seismicatty gastified. Att fire berrier penetrations l are in accordance with 10 Cia 50.49, Aspendia R. The fire berrier-I penetrations and cable penetration berriers were restored to their originet status following cable replacement and/or receutlng. The probability of an accident was not increased, and the possibility of an accidert of a cifferent type mes not created. The mergin of safety remains unaltered.
** $l-234.3 TECNulCAL SPECIFICAil0E flRE DETECTORS - UNII5 0, 1, Amo 2 l sty no. 011 This revision was made to comply with the motional firc Protection The instruction scope has teen increased to incorporate tating of fire Association standards and to incorporate vendor cheds. It was etso stgeression flow controt valves currently performed in $8-177 series to l revised in accordance with $1-1, Appendia f, and incorpwated RATS M-275. eliminate redwusency and improve ef ficiency. The besic test reg 4irements '
remain unchanged, and ett I.5. regJirerents are futfitled. The mergin of safety, as defined in the tesis of any T.5., was not redaced. , ** 53-234.4 f tCnetCAL SPECIFICAllom flRE DEftCTORS - UW115 0,1, AND 2 , etV N0. 014 This revision was made to comply with the National fire Protection The instruction scope has been increased to incorporate testing of fire j Association standards and to incorporate vendor checks. It was also st4pression flow control vetves currently performed in SI-1TT series to revised in accordance with SI I, Agpendia 7, and incorporated CATS M-275. eliminate redundancy and to improve efficiency. The besic test ' requirements remain enchanged, and ett T.S. regairements are futfitted. The mergin of safety, as defined in the basis of any T.S., was not reduced. _ _ . _ _ _ _ _ - ._ _ _ _ _ _ . _ _ _ . . _ . . _ _ _ _ _ . - _ . _ , , , . - _ . _ = . _ - . . .-. . . . __n. . . _ . . -_
Page me. 55 02/32/88 SEQUOYA40 WUCLEAR PLAuf to CFR 50.59 1987 NRC AshuAL OPERATING REPORT l CnA#GES TO PROCEDURES As DESCRISED IN TME SAR DESCRIPTION SAFETY SUMMARf 3 I l ' ** SI-334.5 TECMWICAL SPECIf! CATI 0e FIRE DETECTORS REACTOR SUIEDING - UNITS 0,1, AND 2 , I RED NO. 011 This revision was made to comply with the National Fire Protection The instruction scope has been increased to incorporate testing of fire l Associatinn standards and to incorporate vendor recommended rhecks. It was swpression flow control valves currently periorsurd in SI-1TT series to also revised in accordance with $1-1, Appendia f, and incorporated eliminate redniency and *o isprove ef ficiency. The basic test rewirements of CATS M-275. rewirements remain mchanged, and att Tas. requirements are fulfitted. The mergin of safety, as defined in the bests of any T.S., was not reduced.'
** SI-234.7 TECMulCAL $PECIFICATION FIRE DETECTORS - tmITS 1 AND 2
, REW mo. 007 This revssion was made to comply with the National Fire Protection ibe instruction scope has been increased to incorporate testing of fire Association standards and to incorporate vendor checks. It was also suppression flow controt valves currently performed in SI-177 series to revised in accccdonce with SI-1, Appendia F, and ineceporated CATS M-275. eliminate redundancy and to improve ef ficiency. The basic test rewirements remain mchanged, and att i.S. rewireements are futfitted. l The margin rt safety, as defined fra the basis of any T.S., was not redaced. O* SI-237.1 POWER NOUSE CO2 FIRE PROTECitou SYSTEM TEST - tmITS 0,1, AmD 2 REO WO. 009 This revision added perf rwe modes and fe&TE ranges and incorporated The basic testing method remains the same but is more detailed and complete reconumended vendor cardon checks. It also incorporated rewirements of to ensure compliance with the T.S. No possibility for an accident or CATS M-497 and PRO-1-87-174. met function of a dif ferent type than any evaluated previously in the 5AR was created. The mergin of safety was not reduced. I C* SI-83F.2 DIESEL GEstRAT0e SultDING CO2 FIRE PROTECTION SYSTEM TE$T - Unlis 1 AeD 2 eEV =0. 007 This revision added performance moder and METE ranges and incorporated This revision tests equipment as designed and does et alter configuration. vendor cardon checks. It also incorporated requirements of i* 15 M-497. No margin of safety was reduced. t i l 1 -- - _. . - - . . - . - . - - - - . - - _ - - - -- - - - - . - ,. - .... - - :
Page No. 56 02/26/88 6 SEQUOYAN NUCLEAR PLfM 10 CFR 50.59 1987 WRC ANNUAL OPERATING REPORT CHANCES TO PROCEDURES AS DESCRISED IN THE SAR DESCRIPTION 5AFETY
SUMMARY
I SI-238.2 DIESEL GENERATOR SAITERY CAPACITY Test - UNIT 0 REV #0. 00s This revision was made to increase the service test current levet from 5 The probability of the occurrence of a toss of offsite power or any amps for 29 minutes to 47 amps for 30 minutes. The remainder of the accident that would require the use of the dieset generators for the safe revision addressed clarification of procedural steps and increased shutdown of the facility was not increased by the adostional discharging information in scope, prerequisites, and test equipment. time added to the service test. The consequences of the complete toss of one dieset generator train, for any reason, are anatyred in F5At 8.3.1.2.1. SI-238.3 AtmuAL DIESEL GENERAf0R SAf fERY SYSTEM INSPECTION
- UNIT 0 REV NO. 000 This instruction written to futfitt SR 4.8.1.1.3.t. 1, SR 4.3.1.1.3.C.2, this procedure is an inspection that does not take the equipment out of and part of SR 4.8.1.2. inese regsf rements were formerly fulfilled ty service ard does not disassemble anything. The probability of the SI-238.2. occurrence of an accident was cot increased, and the possibility of an accident or malfunction of a different type was not created. No margin of safety was reduced.
SI-240 fuMCil0NAL Test of CONTROL ROOM AIR INTAKE CMLORINE DETECTION SYSTEM (WEEELT) - UNIT 4 mEV mo. C12 The revision clarified instruction steps, added detalt to the f.5. ine test methods remainal the same emcept for actuatlan of the CRI. reference, armi changec authorization to commence testing to unit 1 and mit Actuation of the CRI places the plant in a more conservative condition. 2 SR0s. The prchability of an occurrence or the consegaences of an accident were not increased, and the possibility for an accident of a dif ferent type was not created. .This test ensures the operability of channets required by the T.S. J
. . - ~ ~ . _ _ . _ _ _ . . . , .. , ,._ . . . - + .- . _ - . . . . . - -- . .- --
Page No. 57 02/22/88 SEQUOYAN WUCLEAR PLAuf 10 CFR 50.59 1987 WRC AmmuAL OPERATING REPORT CNANGES TO PROCEDURES A5 DESCRIBED IN THE SAR 6 DESCRIPTION SAFETT
SUMMARY
** 51-242 fumCTIONAL TEST of INE WAsiE GA5 DISPOSAL SYSTEM OMTGEN AND NYDROGEN ANALYZERS itCV #0. 005 This revision cancetted 51-242. The functions in it-242 have been incorporated in SI-243. no testing methods have been changed.
** 51 243 CMA#mEL CALIBRATION OF THE Was?E GAS DISPOSAL SYSTEM OMYGEN Amo NYDROGEN ANALYZER eunRTERLY - UNIT 0 SEV aO. DOS This revision incorgerated the functional testing previously performed try The procedure changes were made to include testing performed in another 51 ,
58-242 and resolved discrepancies identified by 51-1, Appendia F. without changing the generat methods used. The probability of an occurrence or the consequences of an accident were not imreased,'and the possibility for en accident of a dif ferent type esas not created. The mergin of safety was not decreased, because this revision obtains the same results as 53-242 R4 and 51-243 RT.
** 51-245 fumCTIONAL TCST OF SEISMIC MONITORING SYSTEM - UNIT 0 REO #0. 004 This revision added performance modes, listed test egsipment, and The functionst testing of the response spectrue recorder (0-mR-52-86) is incorporated generet formet considerations free present guidelines. This not required by the T.S. Att the other changes were for clarity and revision also removed the response spectrue recorder (0-RR-52-86) from the documentation. The test methods remained the same. The probability ef an test, occurrence or the consegaences of an eccident or omstf amction were not increased. The possibility for an accident er metfunction of a different type was not created, and the margin of safety, as defined in the basis of any I.S., was ret redxed.
*O S t
- 2B SURVEILLANCE PROGaAM pom REACIOR letADI ATION SPECIMEW - UNIIS 1 AuO 2 l REO #0. 004 This revis6on added the requirement to neet 10 Cf R 50.61, *f racture including the requirements of to CfR 50.61 was in addition to the regaired Toughness Regairements for Protection Against Pressurized Thermat Shock T.S. and enhanced the procedure. The margin of safety was not reduced.
. _ . - ._ _- ... - _ . _ _ . __ - ~ _ _ _ . __. . .. ~ . . . . . - .-
Page me. 58 i 02/22/88 SEGUOTAM NUCLEAR PLANT 10 CfR 50.59 1987 WRC Aeuual OPERATING REPORT CNANGES TO PROCEDURES As DESCRIBED IN THE SAR DESCRIPi!OW SAFETY SupW4ARY g Events," to 58-255. This revision also corrected titles to other references.
" 51 256 PERI 00lc CALIDeAil0N Of OVERCURRENT AND GROUND F AULT RELAYS 04 RCPs AND BACKUP DEVICES 04 6.9kV UNii 901RDS (REFUElluG CYCLE) - tmits 1 Aa0 2 REW #0. 008 This revision seperated the signof f s for A phase and C-rease overcurrent Att breakers will be signed of f individaelly rather than severet at one relays on RCS breaker, normal feeder breaker, and alternate feeder breater. time. RCP circuit breaker maisers ulti be included in the identification This revision aise identified breaker number in step 6.2.2 of att data of circuit breakers in step 6.2.2. Givies more positive lesntafication and packages and esved data sheets f rom the end of the package to behind the dote sheet errangement attous adessete recording of data. The changes section for each brea6er, stated did riot af fect or reduce the smargin of safety as defined in any T.S.
REW NO. 009 This instruction was revised to correct RCP breaker readier, to change the SR ramber remains in the scope of this instruction. The probabitity of system readers, and to remove 1.5. SR nummier f rom the acceptance criteria. an accident uns not increased. and no new possibilities of an accident amere created. The mergin of safety esos not redaced.
** SI-257 PERIODIC FUNCTIONAL M RCP PROTECTIVE DEVICES (18 Moui45) - UNITS 1 AND 2 REW #0. 010 This revisten combined SI-tST.1 and 58 257, because the 7.5. addresses the probability of an accident mes not increased, and the possibility for these procedures in 58-257.1. an accident of a different type mes not creeted. The mergin of safety, as defined in the basis of any T.S., uns not redaced. ** SI-255 TEsilwG Of MOLDED CASE AND LOWER WOLTAGE CONTAlhMENT PENEIRATIDW CIRCUIT SREAKERS - Unlis O AND 1 REW #0. ESg This revisten added the detta (D) sign to the breaker consuon to both emit 1 This revision did not create any mattinction of any type, because this sis and added vendor curve list. It also added a statement that was revision (Sdated only the procedere method without af fecting any inadvertently entitled that e.ttows the breaker test sequence to be at the safety-related equipment. This change did not affect 1.5. requirements.
discretion of the cognizant engineer and deleted regsirement for d@licate ilte margin of safety remained unchanged, configuration con *rol docueentetlon.
Oege be. 59 02/22/88 SEQUOYAN NUCLEAR PLANT 10 C#a 50.59 1987 WRC AtuuAL OPERATING REP 0tf CMANCES TO PROCEDURES AS DESCRIBED IN THE sat DESCRIPT20W $ATETY summary ;
** SI 258.2 TE5f thG OF MOLDED CASE AND LOWER VOLTAGE C0miAlWMENT PENETRATION CIRCUIT DREAKERS - UNITS O AND 2
#EV NO. 611 This revision incorporated instantaneous testing of breakers and corrected This revision upgrades breaker integrity through testing and ensures instructions to be in accordance with the SI-1, Appendia f. It superseded breaker reliability, because T.S. requirements are enforced. so ICF-86-1279, CATS 86182 and 86183, NATS 8623, and NCO 860177006 and was safety-related fmction'or feature is redxed by this revisian, because the corrective action for De-87-0634. integrity of the breaker is maintained during the test. The test is in conformity with att T.S.; therefore, no safety margin was reesced, and there was no increase in the 9robability of an accident er malfaction of plant e wipment.
SI-259.1 TESTING OF ACTUAi!ON OF AUMILIARY FEEDWATER BY TRIP OF MAIN FEED PURPS - UNIT 1
#EV 20. 002 This revision cancelled SI-259.1 R2. Sa 4.3.2.1.1.c.6.F of 58-259.1 92 is Testing methodology and acceptance criteria of $1-118 a15 and 5I-118.1 a15 satisfied ty 5t+118 R15 and 58-118.1 R15. were not affected and match those required *or SI-259.1 22. ;
SI-259.2 TEST OF ACTUATION OF AUNIEIARY TEEDWATER SY it!P OF TME MAIN FEED PUMPS - UNIT 2 RE7 N0. 002 This revision cancetted 31-259.2. Sa 4.3.2.1.1.C.67 of 53 259.2 a2 is Testing methodology and acceptance criteria of 53-118 a15 and 51-118.1 a15 ! satisfied ty 53-118 p15 and $3-118.1 R15. were not affected and match those required for 58-259.2 a2.
]
53 260 535/ SIT /#pe It K Citow FLOW SALA 4CE, PUMP PERFORMANCE, AND CNECK VALVE Test - UutTS 1 ANO 2 REV to. 013 This procedsre lists the instructions in the $3-260 series. The revision the probability of an accident or metfunctive was not increened by this added twe (2) new procedures so the list: 5I-260.2.1 and 58-260.3.1 revision. The margin of safety was not redv ed, because this is an eduinistrattwe procedure intended as a cover for other $3s in the $1-260 series. i I 1 e Page eso. 60 *
- s
~- 1 p -- i 02/26/88 SEQUDYAN NUCLEAR PLANT 10 Cf a 50.59 1987 mRC AmmuAL OPERAllNG REPORT CHANGES TO PtoCIOURES As DtsctlatD IN INE SAR DisrRIPTION SA'tif stemeAtf ,_.n, s t -2t.3 MONITORING COMP 0 MENT CYCLIC OR TRANSIENT LIMIT - UNITS 1 AND 2 REV m0. 008 This revision added new guidelines for tracking cyclic timits and added the Ensuring the cocrect trackie4 and monitoring of cyctic timitations and transient one-half safe shutdown earthquake as required in tne'fSAR. complying with the FSAR did not increase the probabliity of an accident or-create the passibility for an accident of a different type. The margin of safety, as defined in the basis of any T.S., was not reduced.
** $1-2t4 EGTS A44ULUS WACUUpeRAW DOWN TEST - UNITS 1 AND 2 styae0. 007 This revision changed attowable leakage at -5.0 inches wete:- column The amutus inteekage was changed to the latest Isaa value of 500 CFM at pressure erw' changed the method by which the system is realigned. This -0.5 inch '& soeu off-site dose calcula.sions have shown that inteenage of revision aise m ade other small changes to comply with the SI-1, Apsmfia t. 500 Cf n at -0.5 inch WC is acceptat,te. sepowed the 300 CfM at -5.0 inch WC inteakage specificstion, because the inteakage criteria only apply to -0.5 inch WC. As tons as the 500 CfM at -0.5 inch WC criteria are met, the of f site dose timits witt be met regardless of tea 6 ages at -5.0 inch WC.
11-265.2 SAFEff INJECTION MYDe05fATIC PRESSURE TEsi - tAsti$ 1 AND 2 ptO eso. 003 This revision cancetted the entire instruction. It did not ecepty with This $1 takes the place of $1-265.2 and futfitts att requirements of A5ME, Section N!,1977 edition throug% summer 1978 requirements, and 58-265.2. The probability of an occurrence or the consegaences of an instruction fumber should be changed to correspond with thg.ptom tweer. accident or estfmetien were not increased, ans one of a dif ferent type was 51-265.2 is being changed to $1,205.63.1
~
nut created. 5I-265.63.1 wilt fulfitt the requirements of ASME, Section II, for the pi ing p inspected as regJired by SR 4.0.5. The margin of safety was not affected. A. d - _ -- . - . - . - - - _ .. -. -. . - . . . -.."d$~ ~. -
Pcg* No. 61 , 02/22/88 - - SEQL4 d.,i aUCLEAR PLANT I 10 CTR 50.59 1987 NRC AN9NIAL OPERAi!NG REPORT CdAr^is TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY FA MARY l
'L ** SI-266.1.1 60-MONTH INSPECTION OF I. T. E. 7.5HK-300 f900Y BREAKERS - UNIT 1 AND COMMON '
EEV NO. 000 This is a new instructir for stparat',pg $1-266 into individual Sis, one This cc.arga ensures that break;r retlability is continu;:d through _ for each type of breaker (6.9kv._ * :. Yet:4r$3S-typeandmoldedcase). inspectim of"each containment penetration breeker listed in this St. This instruction also conpt b, with SI-1, Appendix F. This $1 is.for Breakers are recoved from se-M ee for performance of this instruction in a vendor maintenarte to 6.9kV br'eakers. conpliance with any L W . There was no increase in the prrhebility of an accident er' mtfur et:on, and the crer. tion of c dif fe. Tnt type of accident did not oir'I. The margin of safety, as defined, was not redJced.
. . a.
SI-io6.La 13 MOMTH CIRCUIT BREAKER thSPEC1!ON (WESTINGHOUSE TYPE DS 480VL- UNIT 1 AND COMMON g Rais' ha. 000 This instruction 1 5 ts alt verrlar reconmended incpections. Thai in pecti ms Implement 5 tion of this instruction enstires'[ Sat the margin of safety wi!! are performed on an iB-month f requency which exceeds the mininsa 60-month, be maintained. / SR. , N
** SI-266.1.3 60-MONTH INSPECTIC* OF MOLDED' CASE CIRCUii SREAKERS - UNIT 1 AND COMKUN ,
'REV NO. 000 This instruction hat M created to inspect 480V and tower voltage molded This instruction serves to increase the inn g [ 3f safete telated case circuit breakers. St-266 is being separated into six Sts to inspect
~
,. equipment by inspecting for ;egradations. The probability of an occurrence
;- c*i,*ferent types of breakers for each unit. This instruction inspects p it was not increased, because the SI performed in -indes 5 or 6 or uider an LCO
~U _ ,2'o,tded case trerkers, adds a breaker megg6rf ng test, and incorpos-:stes in other modes. Any breaker needing to be spared out for safety reasons.
~ versfor reconenendations.
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7
, will be spared out in the ins'ruction. The prcbability of en occurrence or 7 .y 7 thy consequences of an accident or malfunction were not created. Att
, precauti 7 to protect equigu nt and personnet have been listed 'r..tha instruction. .The $1 ensures th2 w gin of safety was maintained as defined -
_, , by T.S. 3.8.3.1 and T.S. 3.8.3.3. . -
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, SE0u0MH iuuCLEAR PLANT ,,
10 CFR 50.50
-}I 1981 ERC ANNUA 1 OrERAMNG REP 0fJ CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
** SI-266.2.1 60-MONTH INSPECTION OF I. T. E. 7.5HK-500 6900V BREAKERS - UNIT 2 AND COMMON REV NO. 000 This is a new instruction for separating $1-266 into individaal sis, one This change ensures that breaker reliability was continued through f or each type of breaker (6.9kV, tow voltage DS-type and molded case). Inspection of each containment penetration breaker listed in this St.
This instruction also complies with SI-1, Appendix F. This SI is for 8reakers are removed from service for performance of this instruction in verdor maintenance to 6.9kV breakers, coupliance with any LCO. There was no increase in the probability of an accident or malfunction, and the possibility for an accident different from those previously evaluated was not created. The margin of safety, as defined, was not reduced. SI-266.2.2 18-MONTH CIRCUIT BREAKER INSPECTION (WESTINGHOUSE TTPE DS 480V) - UNIT 2 AND COM ON REV WO. 000 This instruction was issued for the separation of sis (one for each type These inspections are performed on an 18-month frequency which exceeds the breaker) and to list att vendor reconenended inspections. minimum 60-month SR. The probability of an occurrence or the consequences of an accident were not increased. The possibility for an accident of a type different from that previously evaluated was not created, and inplementation of this instruction ensures the margin of safety was maintained.
- -SI-266.2.3 60-MONTH INSPECTION OF MOLDED CASE CIRCUI? BREAKERS - UNIT 2 AND COMMON REV NO. 000 This instruction has been created to inspect 480 volt and lower voltage The instruction serves to increase the integrity of safety-related molded case circuit breakers. SI-266 is being separated into six sis to equipment by inspecting for degradations. The probability of an occurrence inspect oifferent twes of breakers for each unit. This instruction is not increased, because the SI is performed in modes 5 or 6 or under an inspects unit 2 molded case breaners, adds a breaker meggering test, and LCO in other modes. Any breaker needing to be spared out for safety incorporates vendor reconsnendations. reasons will be spared out in the instruction. The possibility for an accident different from those previously evaluated was not created. All precautions to protect equipnent and personnet have been listed.in the
Page No. 63 02/26/83 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY.
SUMMARY
,i instruction. The SI ensures the margin of safety was maintained as defined by T.S. 3.8.3.1 and T.S. 3.8.3.3.
SI-267.3.2 IN-SERVICE PRESSURE TESTING OF AUXILIART FEEDWATER SYSTEM MOTOR DRIVEN PUMPS - UNITS 1 AND 2 REV NO. 002 This revision clarified the procedure and deleted the ASME class 2 piping The procedure is used to perform an in-service pressure test on a portion from the test, because it is not required by ASME code, 1977 edition of the AFW. The deletion of class 2 piping from inspection is allowed by through sumer 1978. the applicable ASME code. Conducting the test merely reflects normal. operation and does not create or increase the possibility of an accident or metfunction. The procedure satisfies ASME, Section XI, and a portion of T.S. 4.0.5. The deletion of class 2 piping does not affect normal system operation. The T.S. margin of safety was not reduced. SI-267.3.4 FUNCTIONAL PRESSURE TEST OF THE ERCW SUPPLY TO THE AUXILIARY FEEDWATER SYSTEM - UNITS 1 AND 2 REV NO. 002 This revision incorporated SI-1, Appendix F, and incorporated instructions This procedure performs a functional pressure test on the ERCW supply to into data sheet. the AFW system. During the test, AFW can be used and the probability of an . accident or malfunction will not be increased. The margin of safety, as defined in the basis of any T.S., was not reduced.
$1-268 VERIFICATION OF P-4 INTERLOCK INPUT TO SSPS - UNITS 1 AND 2 REV No. 006 This revision deleted the reference to the T.S. and included a reference to The same equipment is tested in the same manner as before this revision.
NRC NES 79-4 and NRC NES 79-5 which requires P-4 contact verification af ter The probability of an accident was not increased, and the possibility for actuation / operation of the reactor trip breaker, an accident of a different type was not created. This instruction is not used to satisfy any T.S. SR.
Page No. 64
.02/33/85 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR j DESCRIPTION SAFETY
SUMMARY
** $1-268.3 PERIODIC VERIFICATION OF P-4 INTERLOCK FUNCTION FROM RtiACTOR TRIP BREAKERS - UNITS 1 AND 2 REV NO. 000 This instruction was written to verify P-4 interlock as result of reactor Testing continuity through breaker auxitiary contacts does not increase the trip breaker actuation. probability of an accident or metfunction. The possibility of an accident or malfunction of a different type was not created. The margin of safety was not reduced. *o SI-270 INSPECTION OF MOLDED CASE AND LOWER VOLTAGE CIRCUIT BREAKER SACKUP FUSES REV NO. 006 This revision cancetted the entire instruction. This instruction has been SI-270.1 ensures that all fuses per unit wilt be inspected property since replaced by St-270.1. T.S. requirements will be enforced. Because the instruction complies with.
T.S., the margin of safety was not reduced, and the cancettation will not increase the probability of an accident or create en accident or matfunction.
** SI-270.2 FUSES FOR CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTION - UNITS 1 AND 2 . CEV NO. 005 This revision complies with T.S. requirements by including att fuses by This revision ensures that att fuses witt be inspected' property, because EQIS identification and reference sampling method. T.S. requirements are enforced. The inspections are visual, and no maintenance is performed by this instruction. Replacements are made as required. The inspection of the. fuses does not increase the probability of an accident or malfmction and does not create one of a dif ferent type.
The instruction is in conptiance with the T.S.; therefore, the margin of shfety i, not reh r ed.
Page No. 65 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
y CEV No. 006 This revision ensured Literal compliance with the T.S. The instruction The visual inspection has no impact on safety. The "wiggle" test may provides for a visual inspection of fuses and a "wiggle" test for result in de-energizing safety-related equipment and entering a LC0; tightness. however, it will not cause en equipment malfmetion. Cautions have been added to the instruction to ensure redundant train operability prior to performing the inspection. The potential loss of one train of safety-related equipmect has been previously evaluated, and no new situation was created. The margin of safety, as defined in the basis of the T.S., was not reduced, c* SI-275.1 TESTING OF NON CLASS 1E LOAD CIRCUIT BREAKERS FED FROM CLASS 1E BUSSES - UNITS 0 AND 1 REV NO. 006 This revision added the delta (D) sign to breakers conunon to both unit 1 This revision did not create any malfunction of any type, because this Sts and added vendor curve List. It also added a statement that was revision updated only the procedure method without affecting any inadvertently omitted that attows the breaker test sequence to be at the safety-related equipment. This change did not affect T.S. requirements; discretion of the cognizant engineer and deleted the requirement for therefore, the margin of safety remained unchanged. duplicate configuration control documentation. C $1-275.2 TESTING OF WON CLASS 1E LOAD CIRCUIT BREAKERS FED fROM CLASS 1E BUSSES - UNITS 0 AND 2 REV No. 011 This revision complies with T.S. requirements and incorporates att DNE This revision upgraded breaker integrity through testing and ensured breaker lists. breaker retlebility, because T.S. requirements were enforced. No . ' safety-retrced function or feature has been degraded by this change, because the integrity of the breaker is maintained during the event. Because the test is in conptience with att T.S. requireet.nts, there was no reduction to the margin of safety.
Page No. 66 02/26/88 SEQUOYAH NUCLEAR PLANT 10 CTR 50.59 1987 NRC ANN'JAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
g
- O SI-2F6 AUXILIARY FEEDWATER AUTOMATIC CONTROL VALVES OPERtSILITY - UNITS 1 AND 2 REV NO. 015 This revision corrected the Data Package Cover Sheet in accordance with This revision to the procedure added signoffs to verify the proper SI-1, and added signof f s to verify the motor-driven AFW punp as not running conditions before and during the perforsence of this test and deleted prior to initiating the test. The revision broke up multi-action steps, redundant signoffs. The margin of safety was not affected by this
(' leted Data Sheet 4, and clarified which steps to perform dependent upon revision, because the changes were for clarity. steam generator pressure.
- St-295 DIESEL FUEL RECE!PT REV No. 005 This revision added a provision to hold the fuel in an alternate container Thi was a procedure change and did not increase the prttability of an pending results of the analysis. SQA-188, Attachment 1, coversheet was occurrence or the consec;uences of an accident or stalfunction. The added to docunent OES endorsement for PMP T.S. 04.06.07.14.03. possibility for an accident er malfunction of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
ce St.296 PRESSURE TEST OF DIESEL FUEL OIL SYSTEM - UNITS 1 AND 2 REV NO. 001 This revision added applicable modes 5 and 6 and referenced SR 4.8.1.2. These changes ensured the instruction met all applicable T.S. requirements. The revision also made the instruction applicable to units 1 and 2. The probability of an accident was not increased, and the possibility for an accident of a different type was not created.
$1-297 PRESSURIZER HEATER CAPACITY - UNITS 1 AND 2 REV NO. C03 This revision changed the organizational name f rom OA to CEEC, added a This revision did not increase the probability of an accident or ,
place for a signature of the individual determining whether or not malfunction of safety equipment and did not increase the possibility of a acceptance criteria is satisfied, renuntered steps of the data sheet to different type of' occurrence. The scope and intent were unchanged, and the match the body of the instruction, deleted superfluous signoffs from date T'.S. was unchanged. The margin of safety remains unaffected by this _91
Pege No. 67 02/26/88 SrCUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
j sheet, and added brackets to the equation for E to inaicate what in the revision. equation goes together.
** SI-302.2 VACUUPI SWITCH AND CONTROLLER PERFORMANCE CHECK FOR RADIATION MONITORING GAS SAMPLE FLOWS (MONTHLY) - UNIT 2 REV NO. 003 This revision was made to respecify the acceptance criteria to include The addition of channet calibration requiremmts and filter fall alarm analysis of "As Found" and "As Left" data for switch action in automatic testing is consistent with FSAR, Section 11.4.4. The acceptance criteria controtters and toss of flow alarms. Format changes were made so that for controtter switches added are based on trending of previous testing and detailed instructions with documentation of performance could be presented estat;tished such that the requirements for sampling described in 10 CFR 30 to the performer in a manner that ensures consistent and ef fective removat and FSAR, Section 11.4.2.2.4, are provided for consistency. The changes do from service, surveittance test and data analysis, adjustment when not implement changes to the configuration of a permanent nature. The necessary, and return of af fected equipnent to service. Also incorporated changes do not affect the way the equipment operates, such that any new in this instruction are the channet calibration requirements for the accidenS or matfmetions could af fect the design objectives of these -
monitors addressed and filter fall alors testing. monitors. Changes to the controller testing have a conservative effect on the surgin of safety by ef fectively increasing the paticula^e fitter concencrations for a given sample concentration. .
- .51-303 SPARE 480V VITAL BATTERY CHAACER PERFORMANCE TEST - UNIT 0 REV No. 002 This revision incorporated the provisions of the SI review program and This instruction is performed on the spare vital battery chargers only when adde.d detailed instructions on the use of the Alber Discharge Load System. they are not connected to a vitat battery board. Therefore, this proceduro cannot reduce the desi;med safety margin of the plant.
- SI-303.2 NYOROGEN MITIGATION SYSTf'I4 OPERASILITY - UNIT 2 9
REV No. 007 This revision ensured c'nptience with At-12. HCI-M2, EMSL-A36, and SI-1, This revision incorporated steps to ensure T.S. compliance and to clarify Appendix F. procedure. There was no modification to the existing system or shfety-related equipnent; ond by conptying with T.S. requirements, the
Cage No. 68 02/11/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDrJRES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
g margin of safety was not reduced.
- SI -307.1 DEGRADED VOLTAGE RELAY RESPONSE TIME TEST AND TIMER CALIBRATION
- UNIT 1
~
REV No. 002 This revision added requirements to lift additional leads from relays under This revision did not change the general test methodology or sequence. The test. probability of an occurrence or the consequences of an accident or malfunction were not increased. The change did not affect the "As Left* condition of equipnent, and the possibility for en accident of a dif ferent type was not created. The change ensured that the gathered data was indicative of the required time delay measurement. The margin of safety, as defined in the basis of any T.S., was not reduced. SI-307.2 DEGRADED VOLTAGE RELAY RESPONSE TIME TEST AND TIMER CALIBRATION - UNIT 2 REV No. 001 This revision added performance modes, added range and accuracy of M&TE, The changes made to the instruction by this revision were administrative in and added the common mode criteria requirements. g nature. The testing method and the intent of this inst'ruction were not altered in any way. Because the testing remains the same as in the previous revision, att T.S. requirements are the same, and the margin of safety was not reduced.
- S1-401 STEAM GENERATOR BLO@OWN CONTINUOUS RELEASE - UNITS 1 AND 2 REV No. 014 This revision was made to add the location of flow recorders and the The revisions were mostly for clarification to ensure T.S. compliance with requirements for using each one. A caution was added that if the outside no changes in methodology or acceptance criteria that would increase the tenperature is less than or equal to 32 degrees Fahrenheit, 0-LS-27-225 probability of an occurrence or the conseg;ences of an accident or j will be declared inoperable. Also, if the outside tenperature is less than malfunction of equ'ipment d acribed. The' possibility of a new type accident or cqual to 32 degrees Fahrenheit, and there is a low levet in the dif fuser Hbs not created. No changes were made to the procedure which would pond, both 0-LS-27-225 and 0-FR-27-175 will be declared inoperable, and the conpromise the T.S. conptianct or cause the margin of safety to be reduced.
Page No. 69 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1967 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
g release will be discontinued. This revision also clarified the instruction and added a reference to LCO 3.11.1.1.
** SI-403 MONTHLY RADI0 CHEMICAL ANALYSIS LIQUID EFFLUENTS
- UNIT 0 REV NO. 009 This revision reflects the deletion of P-32 T.S. requirement dJe to a Only chemistry lab activity is affected by the deletion of P-32 evaluation.
January 14, 1986, revision to the T.S. The deletion of P-32 was evaluated in the T.S. revision. Organizational name changes have no consequence on plant safety.
** SI-407.1 RADICACTIVE CASEOUS WASTE EFFLUENT-PARTICULATE AND IODINE RELEASE RATES FROM SHIELD AND AUXILIARY 80lLDING VENIS (MONTHLY) - UNITS 0, 1, AND 2 REV NO. 005 Tnis revision cancetted SI-407.1. All'the requirements of SI-407.1 are r.ow satisfied in SI-407.2.
- c. SI.407.2 RADI0 ACTIVE CASEOUS WASTE EFFLUENT PARTICULATE AND IODINE RELEASE RATES FROM SNIELD AND AUXILI ARY BUILDING VENTS' (WEEKLY / CONDITIONAL) - UNITS 0,1, AND 2 REY NO. 007 This revision corrected T.S. references and added a provision for SE/SRO The probability of an occurrence or the consequences of an accident or authorization for work on radiation monitors and second analyst matfunction of equipment leportant to safety were not increased by the verification (in accordance with AI-4 and Al-37). changes made to the procedure. The probability was decreased due to the more stringent controls on SE/SRO authorization and independent verification for operators on equipment. The margin of safety was not reduced in any manner because of the more adequate provisions for SE/SRO authorizations and verification of operations on radiation monitors.
** $1-410.1 CONTAINMENT (LOWER COMPARTMENT) VEFT TO AUXILI ARY BUILDING EXNA'JST - UNITS 1 AND 2 REV NO. 009 This revision incorporated revisions to T.S. (change number 34 and 42). This revision only affected the number of samples obtained within a 24-hour period. This does not affect the operation of equipment or the type of work performed.' The probability of an occurrence or the consequences of an
_94_
Pege No. 70 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
g accident or malfunction were not increased. The possibility for an accident or matfunction of a different type was not created, and the margin of safety, as defined in the basis of any T.S., was not reduced.
** St-410.2 CONTAINMENT (UPPER, LOWER) PURGE - UNITS 1 AND 2 REV NO. 009 This revisicn included new sample method nunexrs, changed tritium Sanpling Listing the reference and supporting instructions, reorganizing data sheets requirements, required senpting and analysis in modes 5 and 6, deleted a and steps of instruction, and other changes for clarification and reference to SR 4.3.3.10 per Compliance Tracking Report 86398, and added a enhancement purposes did not increase the probability of an accident and new title page. did not create a different type of occurrence. The clerical and clarification changes did not affect the T.S. The margin of safety, as defined, was not reduced.
$1-413 HYDROGEN AND OXYGEN CONCENTRATIONS IN THE WASTE CAS DECAY TANIC - UNIT 0 REV NO. 007 This revision added steps to Section 3.0, step 3.1, to ensure adequate This revision was made to format for adequate flush times and to correct flush time of gas line and corrected Data Sheet 1.0 procedure step nunbers Data Sheet 1.0 procedure step nund>ers. It also stated that the Si to sutch procedure steps in instructions. satisfies T.S. requirements. This did not increase the probability of an accident or malfunction, and the margin of safety was not reduced.
** $1-415 CASEOUS EFFLUENT REQUIREMENTS (CROSS ALPHA, NOBLE GAS, AND TRITIUM) - UNITS 0,1, AND 2
'REV No. 018 This revision replaced T.S. reporting limits with 1G CFR 50 reporting This procedure deals only with chemistry laboratory activities and does not timits which are more restrictive. affect equipment relating to operating the plant safety. These changes only help to ensure equipment is operable when needed, and the T.S. reporting limits changed to 10 CFR 50 requirements did not decrease the margin of safety or increase or create the possibility of an accident not previously evaluated.
Page No. 71 02/22/88 SEQUOYAN NUCLEAR PLANT , 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRISED IN THE SAR DESCRIPTION SAFETY
SUMMARY
C* SI-416 WASTE GAS DECAY TANK GASEOUS ACTIVITY - UNIT 0 REV NO. 009 This revision was to clarify and to ensure that compliance instrunentation This revision was a reocedure change to ensure representative sampling is is used to verify WGDT pressure and that a representative sanple is being done and conpli.nce instrunentation is being used. Because the obtained (50-DR-86-229R). change ensures adequare flush time, the margin of safety was not reduced, and there was no inct 2ase in the probability of an accident or malfunction.
** SI-417 RADIATION MONITOR SETP0le:T EVALUATION NOBLE GASES - GASEOUS EFFLUENTS - UNITS 0,1, AND 2 REV NO. 005 This revision made correction to title changes within the chemistry grotp The changes made were organizational changet and have no consequences in and revised the instruction in accordance with SI-1, Appendix F. regard to an accident or equipment malfunction. The margin of safety, as Additional revisions removed references to initial setpoint adjustment, defined in the basis of any T.S., was not redJced.
included setpoint limits, and provided separate treatment of RM-90-119 and RM-90-99. ,
** SI-418 GASEOU$ RADWASTE TREATMENT - OPERAB!t.lTY VERIFICATION - UNITS 1 ANO 2 REV NO. 005 This revision cancelled the entire instruction. The T.S. requirements (SR This revision did not affec? the plant equipment in any way, because it 4.11.2.4.2) of units 1 and 2 for demonstrating operability / verification of deals with only the operability requirements of the gaseous radweste gaseous radwaste treatment systems have been eliminated. This revision was treatment system which have been eliminated in the T.S. This change did required to resolve CATS item 86-524 not decrease the margin of safety and did not increase the probability of an accident or malfunction of equipment.
c* SI-431 TUR8tNE BUILDING SUMP OISCNARGE R4 9tMCTIVITY DETERMINATION - UNIT 0 REV h0. 008 This revision corrected the T.S. eeterence and added the method to [hisrevisiondidnotincreasetheprobabilityofanaccidentanddidnot determine turbine building sump flom the MPC timit was towered to a more create the possibility of an accident or malfunction of a different type.
Page to. 72 07/22/88 SEQUOYAM NUCLEAR PLANT - 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION EAFETY
SUMMARY
g conservative value. Lowering the MPC limit from 1.0 to .75 is more conservative, and the margin of safety was not reduced.
- SI-422.2 QUARTERLY 10 CFR 50 APPENDIX X DOSE CALCULATIONS LIQUID EFFLUENTS - UNIT 0 REV NO. 002 This revision clarified the SI and made the format consistent with SI-1, This revision affected only the monthly liquid effluent report format and Appendix F. It otso deleted P-32 results because of a T.S. revision, and did not increase the probability of an accident. The acceptance criteria closed Discrepancy Report 86-205R, CATS item 86-732, CA Audit was'not altered by the changes. The margin of safety was not reduced.
QSS-A-0023-D08, and EATS item 86-698. 'th REV NO. 003 This revision corrected calculations on pages 9-12 by adding a The revision did not increase the possibility for an accident or multiplication factor of 1000 to correct the units. malfunction. The revision corrected the equation by the addition of a dilution multiplication factor to provide correct data units. The change , did not reduce the margin of safety, as defined in the T.S., because the T.S. remained unaltered. 9 f
- SI-431 COCt!NGTOWEjBLOWDOWNFLOWRATEDETERMINATION-UNITS 1AND2 REV NO. 005 This revisim was made to delete steps for operating 0-RCV-77-43. This valve is now operated in accordance with a Category A SOI. The probability of an accident was not affected, and the possibility cf an accident or malfunction of a different type was not created. Directing the performer to the correct instruction and deleting the wrong instructions increased the margin of safety.
- SI-470.4 SHIELD BUILDING IODINE SAMPLER FLOW ESTIMATION - UNITS 1 OR 2 REV NO. 004 This revision reinstated $1-470.4, which was incorrectly deleted by T'his revision implemented $1-470.4, which was incorrectly detered by revision 3. It also included minor organizational changes and revision 3. There was no increase in the probability of an accident, and
Page No. 73 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANCES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
clarifications. the margin of safety was not reduced, because this SI more accurately determines the flow through the iodine sampler.
- SI-476 CLEANING AND OPERATIONAL CHECK OF LIQUID RADIATION MONITOR FLOW SWITCHES (CONDITIONAL) - UNITS 0, 1, AND 2
[EV NO. 008 This revision cancetted SI-476. The GEM sensor flow switch had been replaced by a universat-type flow switch, and this instruction was no longer applicable.
** SI-483 PROCEDURES FOR REMOVING A REACTOR PROTECTION CHANNEL FROM SERVICE - UNITS 1 AND 2 ' REV NO. 003 This revistori updated T.S. time limits to correspond to T.S. changes and This revision did not change the method of removing a protection channel was revised in accordance with $1-1, Appendix F. from service or returning it to service. The probability of an accident or malfunction was not increased. The possibility for an accident or malfunction of a different type was not created, and the margin of safety was not reduced. ** $1-487 SENTRY POST ACCIDENT SAMPLING SYSTEM OPERA 88LITY VERIFICATION AND CALIBRAfl0N - UNITS 1 AND 2 REV NO. 002 This revision added the procedure for calibration of the post accident This revision enhanced the post accident sampling system capability to sanpling system gas chromatography for.contairment air analysis for perform containment air hydrogen analysis. It ensures the accuracy of hydrogen determination in the instruction. hydrogen determination in the containment air, thus improving the reliability and minimizing any accident already evaluated in the FSAR.
This revision did not alter any T.S.; thus, the margin of safety was not, reduced. 9
** St-485 RCS RTD SENSOR VERIFICATION OF CALIBRATION - UNITS 1 AND 2 I REV No. 000 This new instructiori schedules and performs TI-60. This instruction performs TI-60 and reviews the results. The margin of i
Page No. 74
, 02/23/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 N9C ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBE 0 IN THE SAR DESCRIPTION SAFETY
SUMMARY
, I safety, as defined in the basis of any T.S., was not reduced.
** SI-532.5 OFFICE OF ENGINEERING, REPROGRAPHICS, AND TRAINING BUILDING FIRE DETECTORS REV NO. 000 This revision deleted testing of one-shot heat detectors from the SI and The testing instruction and method have not changed in the procedure. ;
included detector XS-13-1191C as shown on drawing. Also, detectors These detectors have no bearing on nuclear safety. This proce&re does not XS-13-87RA and -89RA are no longer installed, because the tocation of change out equipment or alter circuitry. Because this SI is a non-T.S. SI, detectors over printing machinery caused spurious alarms, the margin of safety was not reduced and there was no increase in the probability of an accident or malfunction occurring.
** SI-532.6 CRVI SMOKE DETEC'.OR TEST - UNIT 0 REV NO. 000 This instruction was written to perform the annual functional test for This instruction luplemented FSAR, Section 9.4.1.4, d ich requires that smoke detectors MS-31A-004A and XS-31A-0038 which initiate a CRVI. thermostats and smoke detectors be tested periodically. This annual functional test is for non-T.S. smoke detectors.
** SI-545 CONDENSER PERFORMANCE TEST REV NO. 003 This revision cancetted SI-545. This procedure was not safety related; therefore, the margin of safety was not reduced.
** S1-557 TEEDWATER HEATERS PERFORMANCE TEST - UNITS 1 AND 2 REV NO. 003 This revision cancet ted 51-557. This procedure was not safety related; therefore, the margin of safety was not reduced.
8 h
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SUMMARY
O* SI-566 ERCW FLOW VERIFICATION TEST - UNITS 1 AND 2 REV NO. 016 This revision was made for the following reasons: (1) Curves depicting mininun flow versus temperature requirements are used (1) Added mininsa flow versus temperature curves to be used to evaluate to evaluate operability of any safety-related ERCW component that is operability of any ERCU component that receives insuf ficient flow. receiving insufficient flow. This insufficient flow rate may correspond to an ERCW inlet tenperature that is less than 83 degrees Fahrenheit as (2) Revised flow acceptance criteria to reflect more detailed instrinnent required by T.S. 3/4.7.5. However, the component will remain oprable as inaccuracies. Long as the reduced temperature requirement is greater than the actual intet tenperature. Insufficient "As-Found" flow rates are evaluated, and (3) Revised to throttle auxiliary control air compressor with the upstream en attempt is made to reestablish the flow rate that corresponds to 83 isolation valve instead of the downstream throttle valve. This was done to degrees Fahrenheit. If the flow rate that corresponds to 83 degrees decrease pressure of the ERCW side of the conpressor. Fahrenheit cannot be obtained, the operability of that component is adninistratively Limited to the temperature that corresponds to the reduced (4) Revised to perform flow verification with the ERCW pump discharge "As-Left" flow rate. This will be accomplished by revising the SI-3 valves throttled to provide margin for ERCW ptmp degradation. ultimate heat sink tenperature acceptance criteria for that component, and SI-566 will require verification that the required SI-3 revision is the latest revision. (2) Flow acceptance criteria were revised to reflect instrument inaccuracies. (3) The ERCW flow to the auxiliary control air compressor was throttled with the upstream isolation valve instead of the downstream throttle valve. This action helped to ensure that the ERCW water pressure remained below the design pressure of the auxiliary controt air compressors. Any valve cavitation that occurred during testing was documented and dispositioned in this procedure. .The acceptable flow rate had a maxinun limit to minimize the ef fects of pressure and cavitation.
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SUMMARY
g (4) The performance of SI-566 established a baseline for ERCW pump degradation by throttling the ERCW pupp discharge valves. 'This baseline is in the form of a flow rate differentist pressure, somewhere between 0 and 5 psid, depending on capability to meet the required ERCW flow rates. After the performance of SI-566, the procedure was revised to reflect this baseline differential pressure. White under balancing conditions, throttling the discharge valves to a differentist pressure of 5 psid resulted in an approximate 6-percent reduction of the total ERCW flow. To ensure that plant safety was not adversely affected by this pre-baseline throttling, the ERCW train was not tested if an ERCW component on the opposite train was not operable. Also, heat loads that could not be handled by the train under testing were transferred to the opposite train. These revisions did not increase the probability of an accident or malfunction, and the possibility for an accident of a d~fferent type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced. l , I
** SI-432.0 AUXILIARY BUILDING COMBINED SYSTEMS EXTERNAL LEAKAGE
, RE7 NO. 004 This revision made minor changes to organization names, added T.S. Changing the nomenclature did not have any detrimental effect on the margin - l 6.8.5ati) (adninistrative requirements for teak reduction program), deleted of safety as defined in any T.S. Leakage trending can only enhance the a one-time only requirement to report the finding to the NRC, and added the plant's performance ability. The NRC report was a one-time only NRC requirement to have a trending program f or systems and valve leakage on requirement, and l'ts deletion had no effect. The addition of T.S. Lines that cover rad water. 6'8.Sa(i) ensures that this requirement will not be accidently lost.
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SUMMARY
l
- SI-632.2 Aux 1LIARY BUILDING SAFETY INJECTION SYSTEM EXTERNAL LEAKAGE - UNITS 1 AND 2 REV NO. 009 This revision deleted the annual report to NRC requirement, added T.S. Addition of procedural performance steps, component description, and the 6.8.5.a to the reference section, adied a detailed component description, conptience with T.S. 6.8.5.a increased the margin of safety.
and adied procedural perf ormance steps in compliance with SI 1, Argmfim F. SI-032.5 AUXILI ARY BUILDING REACTOR COOLANT SAMPLE SYSTEM EXTERNAL LEAKAGE - UNiiS 1 AND 2 REV NO. 004 This revision added information to indicate that the informa* ion gathered this revision did not introdJce any new plant configuration, operation, or would enter the leak reduction trending program and added drawing methodology in the test performance. This revision only inspects 47W610-43-6 to the reference section. components in piping Lines and does not alter any linetg>s from those in the previous revision. These changes did not alter T.S. The margin of safety was not reduced. The probability of an accident or malfunction was not increased.
*O SI-654 FIRE HEADER VALVE SEALS INSPECTION - UNITS 0, 1, AND 2 REV No. 011 This revision deleted att 1.5. valves which were incorporated into SI-167 Incorporating att T.S. valves in $1-654 into SI-167 and incorporating att and incorporated atI non-T.S. valves from 51-167 into 55-654 valves non-T.S. valves in SI-167 into SI-654 had no effect on the margin of 0-26-725 and 0-26-328A were removed f rom the valve checklist. safety. Valves 0-26-725 and 0-26-328A were removed under ECN $198 and did not affect the margin of safety. The probability of an occurrence or the consequences of an accident or malfunction were not increased. The possibility for an accident or metfunction of a different type was not created.
REY No. 012 This revision was made to change the required position of fire header valve The probability of an accident or malfunction of equipment previously 0-26-643 (oit dispensing rcom header isotation valve) to the CLOSED evaluated in the SAR was not created. The postioitity of an accident or
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SUMMARY
l position. The open spray nozzles will spray down the oil dispensing room malfunction of a different type was not created, and the margin of safety if the valve is in the required OPEN position. was not reduced by this change. SI-471 CONTROL ROD DRIVE MOTOR GENERATOR OVERCURRENT AND UNDERVGLTAGE RELAY CALIBRATION TE$TS - UNITS 1 AND 2 REV NO. 004 This revision cancetted the instruction. This SI was cancelled, because the control rod drive relays are not CSSC or T.S. The functional test of the relays has been transferred to PM 1829-085, unit 1, and PM 1830-085, unit 2. There are no T.S. requirements, so the PM program will be sufficient to maintain operability. There was no increase in the probability of an accident or malfunction, and the margin of safety was not educed.
- $1-681 CONTROL ROD DRIVE MOTOR CENERATOR RELAY FUNCTIONAL TEST mEV ko. 003 This revision cancetted the instruction. This SI was cancelled, because the control rod drive relays are not CSSC or T.S. requirements. The functional test of the relays has been transferred to PM 1829-085 and PM 1830-085. There are no T.S. requirements, so the PM program will be sufficient to maintain operability. There was no increase in the probability of an accident or malfunction, and the margin of safety was not reduced.
- SI-688.2 FUNCTIONAL TEST FOR ACCIDENT RADIATION MONITORING SYSTEM, MONTHLY - UNIT 2 REV No. 003 This revision added reference $1s which show where the high voltage The additional sources to obtain the high voltage calibration values were calibration values for radiation monitors are performed and added a added for clarification. The method and frequency of performing the statement that voltage values are mairitained in the instrunent shop on functional test were not altered by the revision due to RM-90-280 being cards. This revision also changed the setpoints on RM-90-273, -274, and inoperable because of a detector and radiation analyzer mismatch. An FCR
-280 to be in agreement with the instrunent tabs. A statement was added to will be submitted to clear this discrepancy. RM-90-280 is the area monitor
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SUMMARY
inform the UO that alarms on 2-M-30 would be actuated during calibration. for the post accident sampling faclLity and is non-CSSC. ibis revision did not delete any functional test requirements. The probability of an occurrence or the consequences of an accident were not increased. The possibility for a different type accident or malfunction of equipment not previously analyzed by the SAR was not created, because RM-90-273, -274, and -280 are non-T.S. monitors. The margin of safety was not affected. SI-689 AUXILIARY CONTROL AIR OPERA 81LITY TESTS - UNIT 0 REV NO. 005 This revision changed the acceptance criteria of the compressor operability The minista required pressure range is 70 psig. This is in line with test tests. The range was changed f rom a range of 75 to 102 psig to a rang. of equipment accuracles and remains conservative. There was no margin of 73 to 102 psig. Also added SRO signof f s from each unit rather than UO safety defined for this system in the T.S. signoffs from each unit.
** SI-693 ERCW CHLORIMATION - UKITS 0, 1, AND 2 REV NO. 002 This revision incorporated the punchlist dated November 10, 1986, deleted a This revision did not affect plant safety. The reecval of redundant reference which is redandant, clarified passage regarding purpose, stated references, correcting nomenclature, and clarifying the purpose of the that SI is non-T.S., and identified conunon equipment. It corrected drawing instruction did not affect the intent / performance e.f the St. The revision deficiencies identified in the SON 1986 walkdowns. The drawings are being also identified equipment and required obtaining reraission from the unit 1 changed to match the in-field tags through FCR 4961. This SI requires and unit 2 SR0s to run the test. The changes dir.not increase the permission from the units 1 and 2 SR0s to run the test. probability of an accident or malfunction and d'd not create a different type of accident. Because the SI is non-T.S., the margin of safety remains unchanged.
*o SI-693 RCW AND RSU CHLORINATION - UNITS 1 AND 2 REV NO. 002 This revision incorporated the punchtist, added pieces of equipment Clarification of the procedure, correction of typographical errors, and
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SUMMARY
3 previously omitted, clarified and enchanced the procedure, and specified addition of equipment which is normally operated did not increase the that the procedure is non-T.S. probability of an accident. Because the procedure is specified as non-T.S., the margin of safety was not affected.
*0 SI-702 ("esci!ONAL TEST OF REACTOR COOLANT RfD BYPASS FLOW SWITCHES (CONDITIONALLY) - UNITS 1 AND 2 REV No. 003 This revisien cancelled the entire instruction. The calibrations that were previously performed in $1-702 are now perforsned in IMI-68, Appendix B and Appendix C.
** SI-714 EXTRACTIOes STEAM PIPE WALL DEGRADATION MONITORING PROGRAM - UNITS 1 AND 2 REV No. 000 This instruction was initiated to address potential wall thinning as a Insulation was temporarily removed for ultrasonic testing of pipe watt result of erosion corrosion in suspect areas of extraction steam pipina. thickress. Pipe which had degradated to less than attowable watt thickness was replaced. The extraction steam system is not addressed in the T.S. No margin of safety was reduced, i
** SI-720 n!!!SPATION OF AUMILIARY FEEDWATER TERRY TUR8INE CONTROLS REFUELING OUTAGE - UNIT 2 REV No. 000 This revision provided a more detailed description of the location of This revision corrected typographical errors and was administrative in 4 MS-46-57 and changed the range on voltage. Location of SM-46-56 is L-326A, nature. The addition of the location of the penet did not affect safety, not 2-3268. and the thanges ensure that the instruction will be run correctly. Because this change did not affect the T.S., the raargin of safety was not redJced.
o* SI-732 QMDS CROSS REFERENCE - UNIis 0, 1 AND 2
- REV NO. 000 This instruction was written to provide a cross-reference of OMDS values
~
The providing of O M S cross-reference has no effect on the probability or which fulfitt the CMOS requirement, the frequency the instruction is pbssibility of an accident. The margin of safety was not affected by the performed, and the EQ frequency requirement. development of a new instruction which is used as a reference.
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m._-_______.-- __--_ _--- - _ _ w% f-
. _ . = _ . _
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SUMMARY
g
** St-722.4 QMDS VALVE STROKING (9 MONTH FREQUENCY) - UNITS 1 AND 2 CEV No. COO This instruction was written to satisfy EQ stroke requirements on RCS The stroking of these valves was previously done in another St. This SI valves. has a dif ferent frequency, but the strokinp prwedurer is the same as the previous St. The f requency change did not reixe the margin of safety.
SI-726 INTERNAL INSPECTION OF MFW/AFW/RNR CHECK VALVES DURING REFULLING OUTAGES - tMtis 1 AND 2 - aEv No. 000 This SI was written to inspect the internals of selected MFW, ATW, and anR The additional valve inspection requirements resulted in increased system check vetves abring refueling outages. reliability. This added assurance that these valves will function and perform as designed in the system they are a part of, This instruction did not reduce the safety margin in any way. 2 0 4
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i 9 f l O O O SJMMARY OF O O PROCE).RE O
- O CHANGES- O
- O S PECIA ._
O O E S :- O l O N S R L C l O N S o O O
Page No. 1 02/22/?E i SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 i 1987 NRC ANNUAL OPERATING REPORT ! CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR 1 i l DESCRIPTICN SAFETY
SUMMARY
g
** S11 005 DEGRADED VOLTAGE TEST FOR MFIV'S BRAKE SOLENOIDS REV NO. 000 This special test was written for degraded voltage testing of the MFIV's This test will prove or disprove the operability of the brakes during an brake solenoids. accident or undervoltage situation. The test will be performed in a mode where feedwater isolation is not required for any TSAR analyzed accident.
All the systee couponents af fected by this procedure will be certified operable before re-entry into an applicable mode. This test will not increase the probability of an occurrence or the consequences of an - accident or malfunction. It will not create the possibility of an accident, and the margin of safety will not be reduced.
** STI-007 WESTINGkOUSE DEMONSTRATION OF ICE CONDENSER SERVICING TOOLS - UNIT 1 REV NO. 001 This revision cancelled the instruction. This procedure for demonstration of ice condenser servicing tools was obsolete.
e
** STI-015 OUALIFICATION TESTING W WEDGE SOLT ANCHORS REV NO. 000 This special test was written to perform qualification testing of wedge The probability of an accident will not be increased, and the pcssibility bolt anchors in the LLRW storage buildings. of an accident or malfunction of a different type will not be created. The margin of safety for the testing of wedge bolts is not defined in the basis of any T.S. ** STI-017 DC HIGH VOLTAGE TEST FOR SELECTED UNIT 2 1E CA8tES IN VERTICAL CROP CONFIGURATION RE7 EO. 000 This de high voltage test will be performed on selected 1E cables to This test will be performed on one safety train at a time, while ensuring alleviate concerns regarding cable damage. the redJndant train is operable to styport mode 5 operation. The involved.
systems and equipment will be isolated and protected. After testing, the
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SUMMARY
p plant design configuration will be restored and documented. The plant operating parameters and system setpoints will not be attered. Functional tests and required sis witt be performed at the conclusion of cable testing to ensure T.S. compliance. REV NO. 001 This revision excluded conax connector wires from the scope of the test and This test calls for testing of cable insulation at high dc voltage. It is, added visual inspection and cleaning of the conductor insulation which is therefore, required to isolate the conax connectors from the cable accessible. Also corrected typographical error, conductors at the Raychem sleeves. The conex connectors will be reconnected to the cables at the conclusion of the test. This STI will be performed in accordance with STI-17 RO and other applicable procedJres to ensure no other system or component is affected and the margin of safety is not reduced.
** STI-018 DC EMERGENCY LIGHTS INRUSN CURRENT - UNITS 1 AND 2 REV NO. 001 This revision was made to incorporate ICF 87-482 and ICF 87-474. ICF By ensuring that electrical connection bolts are not over torqued, the 87-482 changed torquing value range to agree with bott size installed in margin of safety will be increased. Testing with a smat t number of tights the field. ICF 87-474 added note to steps 6.2.1, 6.3.1, 6.4.1, and 6.5.1 nonoperational will provide DNE a basis on which calculations of Inrush to indicate acceptability of lights being nonoperational. This attowed corrent can be determined. No margin of safety, as defined in the basis of running of the test if a small number of Lights were not working. any T.S., will be redxed.
STI-019 DC NICM VOLTAGE TEST FOR SELECTED 1E CABLES WITN POTENTIAL FOR CABLE JAMMING - UNITS 1 AND 2 ;. REV No. 000 This instruction was written to perform a de high voltage test on selected This test will be performed on one safety train at a time white ensuring 1E cables to atteviate concerns regarding cable damage. the redandant train* is operable to sups. ort mode 5 operation. In addition, a,t t the involved systems and components will be isolated and protected. The test will not personently af fect the pterit configuration. . Plant design configuration will be restored, and the plant operating parameters or
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SUMMARY
system setpoints will not be altered. The pr h itity of an occurrence or the consequences of an accident or malfunction are not increased. The possibility of an accident of a different type will not be created, and the margin of safety will not be reduced.
" STI-021 DC MIGN VOLTAGE TEST FOR SELECTED 1E CABLES WITH POTENTI AL FOR CABLE PULLBY DAMAGE CONDUIT MC 17348 - UNITS 1 AND 2 REV h0. 000 This de high voltage test is performed on selecte1 1E cables to atteviate The performance of STI-21 Ro does not increase the probability or concerns regarding possible damage due to cable puttby in con &it. consequences of an accident previously evaluated in the FSAR and does not increase the possibility or consequences of a malfunction of equipment important to safety, because the test is performed on safety train B for specific components, and train A is operable to support att equipment that is necessary to function during mode 5 operation. STI-27 RO ensures that att test cables and conductors disconnected, tested, and restored do not af fect equipment or components whose failure or actuation may increase the probability or consequences of an accident or metfuncti,on of equipment inportant to safety. Plant design and construction ensure adequate isolation between the test cables and other cables. The margin of safety, as defined in the basis of the T.S., is not reduced. The plant operating parameters or system setpoints are not affected or altered.
** STt-023 DC MIGN VOLTAGE TEST 70a SELECTED 1E CABLES WITH POTENTIAL FOR CABLE PULLBY DAMAGE CONDUIT MC1748A - UNITS 1 AND 2 REV No. 000 Th6s spectat test is performed on selected 1E cables to atteviate concerns This test will be performed on safety train A conponents. Train B will be regarding possible damage due to cable puttby in conduit. operable to stoport att equipment that is necessary to imetion during mude 5 operation. It will ensure that the test cables and conductors that are disconnected, tested, and restored (as well as other cables and conductors disconnected and restored) do not af fect equipment or conponents
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SUMMARY
l whose fatture or actuation may increase the probability or consequences of an accident or malfunction of equipment important to safety. Plant design and construction ensure adequate isolation between the test cables and other cables. This test will not affect any equipment necessary for mode 5 operation. The margin of safety, as defined in the basis of the T.S., is rot reduced. C* 4 Sit-024 DC NIGN VOLTAGE TEST FOR SELECTED 1E CASTES WITN POTENTI AL FOR CABLE PULLBT DAMAGE CONOUIT MC1750A - UNITS 1 AND 2 REV No. 000 This STI was written to perform a de high voltage test on selected 1E This test will be performed on one safety train at a time, White aneuring cables to atteviate concerns regarding damage due to cable puttby in the redundant train is operable to stoport mode 5 operation. All the condult. involved systems and components will be isolated and protected. The plant design configuration wiLL be restored and documented. The plant operating parameters and system setpoints will not be effected or altered. The probability of an occurrence or the consequences of an accident or matfunction are not increased. The margin of safety is not reduced. REV No. 001 This revision changed the test method fro testing groups of cable in This change better su p rts the validity of the test results, and the conduit MC1750A to testing each individaat conductor in conduit MC1750A. margin of safety is increased. There is no USQ involved. STI-025 DC NIGN VOLTAGE TEST FOR SELECTED 1E CABLE PULLBY DAMAGE CONDUIT MC 1754 A - UNITS 1 AND 2 REV NO. 000 This de high voltage test witt be performed on selected 1E cables to The performance of STI-25 a0 will not increase the probability or at teviate concerns regarding possible damage due to cable pullby in consequences of an accident previously evaluated in the FSAR. It will not conduit. increase the probability or consequences of a malfunction of equipment important to safety, because the test wiLL be performed on safety train A ' for spcific conpanents, and train B will be operable to stoport att ' equipment that is necessary to function during rule 5 operation. STI-25 'R0
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- _ . . . - . - - . - _. . . - - - ~ - - ~, .. .
Page me. 5 02/26/08 SEQUOTAH NUCLEAR PLANT 10 CfR 50.5C 1987 NRC ANNUAL OPERATINC, REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
ensures that att test cables and conductors that are disconnected, tested, and restored do not af fect equipment or components dose f ailure or actuation may increase the probability or consecpaences of an accident or metfunction of equipment important to safety. Plant design and construction ensure adequate isolation between the test cables and other cables. The margin of safety, as defined in the basis of the T.S., is not reduced. Plant operating parameters or system setpoints will not be affected or attered.
** - ST8-027 DC NIGH VOLTAGE TEST FOR SELECTED 1E CASLES WITN POTENTIAL FOR CABLE PULL 8Y DAMAGE CONDUlf MC 1751A - UNIT 1 AND 2 REV No. 000 This de high voltage test will be performed on selected 1E cables to The performance of STI-27 RO will not increase the probability or atteviate concerns regarding possible damage due to cable pullby in consequences of an accident previously evaluated in the FSAR.' It will not -
consbit. increase the probability or consequences of a metfunction of ecpalpment importar.t to safety, because the test wilt be performed on safety train A for specific components, and train 8 will be operable to steport att equipment that is necessary to function during mode 5 operation. STI-27 RO ensures that att test cables and conchetors that are disconnected, tested, and restored will not af fect equipment or components whose failure or actuation may increase the probability or consequences of an accident or malfunction of equipment leportant to safety. Plant design and construction ensure adequate isolation between the test cables and other cables. The margin of safety, as defined in the basis of the T.S., is not reduced. The plant operating parameters or system setpoints will not be affected or altered.
Page 50 6 02/26/88 SEQUDYAN NUCLEAR PLANT ' 10 CfR 50.59, 1987 NRC ANNUAL OPtaAf '.hG REPORT ~ CHAhCES TO PROCEDURES AS CESCRIBtD IN THE SAR 7 DESCRIPTION SAFETY
SUMMARY
l 1..
- Sit-028 DC NIGN VOLTAGE TEST FOR SELECTED 1E CABLES WhiN POTENTI AL FOR CABLE PULL 5Y DAMtGE - UNITS 1 AND 2 REV mO. 000 The test witt be performed on selected 1E cables to atteviate concerns The test will be performed on safety train A for specific components listed regarding possit>te d.aruge due to cable pullby in conduit MC16054 " -
in attachment 2 of STI-28 RO. Train a witt be operable to support att " equipment that is ne4essary to function to support mode 5 operation. The
- . test will be performed 'n accordance with STI-28 RO and other applicable procedures to ensure that the test cables and conductors that are disconnected, tested, and restored (as welt as other cables and conductors disconnected and restore <!) witt.not affect eqJipment or co p ts whose f ailure or actuation may increase the probability or consegaences of an accident or metfunction of equipment leportant to safety. The plant design and construction ensure adequate isolation between the test cables and other cables. The margin of safety, as defined in the basis of the T.S.,
will not be reduced.
- STI-029 OC NIGN VOLTArA TEST FOR SELECTED 1E CABLES WITN POTENTIAL FOR CABLE PuttBY DAMAGE CONDuti MC 1606A - UNITS 1 AND 2 REV No. 000 This de hign witaCe test will be performed on selected 1E cables to The performance of STI-29 RO wilt not increase the probability os atteviate concerns regarding possible damage dee to cable puttby in consequences of an accident previously evaluated in the FSAR. It will not conduit.. increase the possibility or consequences of a metfunction of equipment isportant to safety, because the tec,t will be performed on safety train A
]
for specific components, and train S will be operable to stpport att equipment that is necessary'to function during mode $. operation. STI 29 ensures that at t test cables and conductors disconnected, tested, ar.: restored wilt tot af fect equipment or components whose f ailure or actuation may increase the probability or consequences of an accident or malfunction
- of equipment leportant to safety. Plant design and constructiork ensure adequate isolation between the test cablas and other cables. The margin of ev p.
;f _
;' f x
V m w
~112- -
Pege No. 7 02/26/88 SEQUOYAN NUCLEAR PLANT to CFR 50.57 1987 hRC ANNUAi OPIERAT!hG REFGli De=GES TO PROCDtSES f4 DESC;tb!D IN THE SAR r DES?'*il0N SAFETY
SUMMARY
}
safety, as desined in the basis of the T.S., w!!i not be reduced. The plant operating parameters or system setpoints will not be affected or altered. i . s s
** STI-032 OC SIGN VOLTAGE TEST FOR set.ECTED 1E CABLES WITH POTtNTIAL FOR CARLE PALBY CAMAti C; u!T MC173C - tm!TS 1 AND 2 CEV No. 00;- This test witt be performed on selected 1E cables t? etteviate concerr.a This test will La performed m -Jiety train S. Train A vitt be operable to reg 2sding possible damag.' due to cable put tby in conduit. support att equef_ent that is're esa f tC 'uncti4during rode 5 '
cperation. This instruction enaares that the test'cabletc and conductors
' disconnected, tested, and restored *sitt not ef fect giperm or components -
A se failure or actuation m i increase the *wobability er consequences of > an accident or malfunction of ctpipnerm-tapori _,t to safety. Ptsnt desier , end construction ensure adeq@te' isolation between the
- att @bles and other cables. ,.' ((
' , j.
m s - - sr
** ST M 33 PC Nt6M VOLTAGE TEST Foil SELECTED 1E CABLES WITH #0 TENT!a! F04 CABLE PU'LBY CAMAGE CONDuti MCh938 - 1.*lTS 1 AND 2 -
REV NO. 000 This test will be per+ormed on selected 1E cables tt. alteviate c.xerns
, This tct will be perforrwd on safet$ train B. Train A will be operable to regardim possible dr.se 6Je to cable puttby 'n conduit.; ,
support di equipment that is necessary to function during ende 5 . operation. This instruction ensures that the test cables and cornfuctors disconnected, g!ested, and restored will not af fect equipment or components d ose laiture or actuation may increase the probability or consequences of an acc8 dent o. malfmtion of equipment important to safety. Plant design-and - * .truction ensure adequate isolation between the test cables and other cables.
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Page No. 8 " ' 02/26/88 ' STJOY41 NUCiiAs PL AMI -r
*0 CFR 50.59 -
1987 NRC ANNUAL OPFRAi!NG REPORT CNANGES TO PRorEDURES As DESCRISED lb THE SAR [ s DESCRIPi!ON SAFETY
SUMMARY
l
- CTI-034 DC atiCE WOLTAM GST FOR SELECTEC 1E CASLES WITN P01 CATI AL FOR CABLE PULLBY DAMAGE CONDUIT MC14975 - tmITS 1 AND 2 REV Wo. 000 This test witi h p*Mormed on selected 1E cables to atteviate concerns This test will be performed on safety train S. Train A will be operable to -
regarding possible ck:sw 6* 'o cable pullby in conduit. support att ecpipment that is necessary to function during mode 5 operation. This instruction ensured that the test cables and conductors disconnected, tested, and restored will not af fect ecpipment or components ~ whose falture or actuation may increase the probability or consequences of an accident or metfunction of equipment igortant to safety. Plant design and construction ensure adecpate isolation between the test cables and other cables.
- STI-037 CA8tE TRACING TEST ON POWER AND CONTROL CABLES FOR SELECTED 1E EQUIPMENT ERCW PUMP N-B - UNIT 1 REV HO. 000 This STI was written to perform cable tracing to verify that power and $11-37 RO will be performed within the safety evaluation provided in FSAR, contret cable routing to the ERCW ptmp N-S is consistent with applicable Section 9.2.2.3.2, and within the T.S. basis described in 3/4.7.4. cabte plant drawings. routing verification will introduce a low-voltage, tou _auperage trace signet to the power and control cables of ERCW pap N-8. These cables will not be exposed to voltages and currents in excess of their design.
S11-038 CA8tE TRACING TEST ON POWER AND CONTROL CABLES FOR SELECTED 1E EQUIPMENT ERCW PUMP R-A - UNIT 2 REV No. 000 This $1I was written to perform cable tracing to verify that power and 1TI-38 RO witt be performed within the safety evaluation provided in FSAR, control cable routing to the ERCW pump R-A is consistent with applicable Section 9.2.2.3.2, and within the T.S. basis described in 3/4.7.4. Cable . plant drawings. routing verification will introcbce a tDw-vottage, tow-aaperage trace signal to the power and controt cables of ERCW pump R-A. These cables will not be esposed to voltages and currents in excess of their design.
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Page No. 9 02/22/88 SEQUOYAN NUCLEAR PLANT to CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CMANCES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETT
SUMMARY
i STI-040 CABLE TRACING TEST ON POWER AND CONTROL CABLES FOR SELECTED 1E EQUIPMENT 2-FCV-67-138 REV h0. 000 This STt was written to perform cable tracing to verify that power and The test ullt be performed within the safety evaluation provided in FSAR, controt cable routing to contairment vent cooter valve 2-FCV-67-138 is Section 6.2.4.1, and T.S. basis 3/4.6.3. Valve 2-FCV-67-138 will be consistent with applicaote plant drawings. teenporarity taken out of service for the test daring cold shutdown. Section 6.2.4.1 of the FSAR states that contairment isolation is not required during cold shutdown. The cables will not be exposed to voltages ord currents in excess of their design.
- STI-042 DC NICM VOLTAGE TEST FOR SELECTED UNIT 2 1E CA8tES (SILICONE RUB 8ER CA8tES) - UNIT 2 - TRAIN A REV NO. 000 This instruction witi perform a dc high-vottage test on selected unit 21E This test will not increase the probability or consequences of an accident cal;tes to atteviate concerns regarding cable damage. previously evaluated in the FSAR. The test will be performed on safety train A with safety train 8 operable to support att equipment that is necessary to function during mode 5 operation. The test ulti be performed in accordance with STI-42 R0 iAich ensures that the test cables and conductors disconnected, tested, and restored (as wett'as other cables and conductors disconnected and restored) do not af feet equipment or components whose failure or actuation may increase the probability or consequences of an accident or metfunction of equipment important to safety. The plant design and construction ensure adequate isolation between the test cables and other cables. The margin of safety, as defined in the basis of the T.S., is not reduced.
- STI-043 DC NICH VOLTAGE TEST FOR SELECTED UNIT 2 SE CA8LES (Sit! CONE RUBSER CA8tES) - UNIT 2 - TRAIN B ~
LEV No. 000 This instruction will perform a de high voltage test on selected unit 2 1E This test does will not increase the probability or consegaences of an cables to atteviste concerns regarding cable damage. accident previously evaluated in the FSAR. The test will be performed on
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_ _ m_ . . - _ Page No. 10 02/26/88 SEQUOYAH NUCLEAR PLANT to CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DEscalPTION SAFETY
SUMMARY
I safety train S with safety train A operable to support all equipment that is necessary to function during mode 5 operation. The test witt be performed in accordance with STI-43 RO which ensures that the test cables and conductors disconnected, tested, and restored (as wett as other cables and coniiactors disconnected and restored) do not affect equipment or components whose f ailure or actuation may increase the probability or consequences of an accident or malfunction or equirement important to safety. The plant design and construction ensure adequate isolation between the test cables and other cables. The margin of safety, as defined in the basis of the T.S., is not reduced. STI-052 DC NIGH VOLTAGE TEST FOR CLASS 1E 10 CfR 50.49 $!LICONE RUBBER INSULATED CABLES REV No. 000 This test was written to test class 1E 10 CFR 50.49 silicone rahber Cable testing wilt be performed on cables in both safety trains fy insulated cables to atteviate concerns regarding possible cable damage. specific components while the plant is in mode 5. The specific components - affected by the test are not required to be functional during mode 5 operation. The test cables and conductors disconnected, tested, and restored (as wett as other cables and conductors discomer.ted and restored) will not ef fect equipment or components whose f atture or ,ectuation may increase the probabitity or consequences of an accident or malftsiction of equipment important to safety. The plant design and construction ensure adequa'e isolation between the test cables and other cables. The margin of safety, as defined in the basis of the T.S., will not be reduced.
** Sit-053 DC N!GN VOLTAGE TEST FOR CLASS 1E 10 Cf R 50.49 SILICONE RUB 8ER INSUL ATED CABLES REV NO. 000 This test was written to test class 1E 10 CFR 50.49 silicone ruther Cable testing will be performed on cables in both safety trains for insulated cables to atteviate concerns regarding possible cable d.unage. specific components white the plant is in mode 5. The specific components
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Page No. 11 0F/26/88 SEQUOTAM IR, CLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CMANGES TO PROCEDURES AS DESCRISED IN THE SAR DESf,RIPTION SAFETY
SUMMARY
~
l af fected by the test are not required to be fmctional daring mode 5 operations. The test cables and conductors disconnected, tested, and restored (as well as other cables and conductors disconnected and restored) wilt not affect equipment or conponents whose fatture or actuation may increase the probability or consequences of an accident or metfunction of equipment important to safety. The paant design and construction ensure adequate isolation between the test cables and other cables. The margin of safety, as defined in the basis of the T.S., will not redaced. STI-054 CA8LE TRACING ON SELECTED CONTROL CABLES REV NO. 000 This test will be performed within the safety evaluation provided in FSAR, Cable routing verification introduces a low-vottage, tou-anperage trace section 9.5.1, and T.S. basis 3/4.3.3.8. Att the requirements of PHYSI-13, signal to the relay contacts of control cables of fire detMtion pones 127, AppendfA C, are to be met. 128, 130, and 133. These cables wilt not be stbjected to voltages and currents in excess of their design. Af ter te acing is cceptete, the fire detection zone relay contact cables will be restored and provm operable per (metional testing. The probability of an occurrence or consegaences of an accident wilt not be increased. The possibility for an accident or metfunction of equipment of a different type than previously evaluated will not be created. The margin of safety, as defined in the basis of any T.S., witI not be reduced. c+ syg.061 ERCW/AUMILI ARY CONTROL AIR COMPRESSOR TEST - UNITS 1 AND 2 REV NO. 000 This STI perfom testing on various ERCW equipment to verify the heat load At no time during the test will the ERCW flow be attowed to decrease below removing capability and record the maximurn flow avaltable. It also the minimum attowable timit docunented in SI-566 (ERCW flow balance). Att establishes a new throttle valve and its position for both auxiliary auxiliary control air compressor testing will be performed after the control air congressors based on a min / man flow. Relocatico of the compressor is placed in en inoperable status in compliance with applicable b
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Page No. 12 02/22/88 SEQUDYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPilON SAFETT
SUMMARY
g throttle valve will prevent over p esturization of the corpressor which has T.S. No new accidmt or metfunction will be created try performing this a lower design pressure rating than the ERCW system. test white ir. modes 5 or 6. There will be no reduction in the margin of. safety.
** S11-062 NOT THERMAL EXPANSION VERIFICATION REV NO. 000 This instructiort verifies adequate clearance for piping thermal espansion Visual examination for thermal expansion is described in FSAR, Chapter 14, as fottows: Section W-1.7 and 23 A & 5. Only two data points will be taken Insteed of at each 100 degrees Fahrenheit heatup. This will not affect safety.
A. Visualty assines and measures empansion clearance of piping identified Mirror insulation will be removed f rom four RNR hangers, but the sLbject M r SM1-2-317-42 daring plant heatup. pipe is isolated above 200 degrees Fahrerheit, and the heat loss to the containment is minimal. Strain gauges will be attached to four RMit pipe
- 5. bisually examines piping and hangers for potential restraints O hangers using capacitive discharge welding process. This process is thernet expansion. provided for in the NQAM and does not degrade the strength or serviceability of the component. Less than 70 pounds of taurnable plastic C. Measures the strain on four hangers in the RMR system, requiring will be added to the transient fire load by the strain Sauge cables in removal of thermal insulation and attaching strain gauges on the hangers. compliance with PNYSI-13. The probability of an accident previously evaluated is not increased, and the possibility for an accident or The systems involved are RMR, SI, RCS, CC, CS, CVC, AFW, TW, and MS piping malfmction dif ferent from that previously evaluated will not be created.
and pipe hangers. The margin of safety, es defined in the basis of any T.S., will not be reduced.
** S18-066 RESPONSE OF iME EGTS CONTROLLERS AND ExMAUST DAMPER TO A $1MULATED ACCIDENT CONOli!ON - UNITS 1 AND 2 REV wo. 000 This test is divided into two parts. The first part consists of irputting Because this test will be performed in modes 5 or 6 when the EGTS system is a step change of the mittianp control signal to the I/P danper positioner not required to be operable, there will be no ef fect on the safety of the ard measur:ng the start of opening and the completion of opening times for plant. The system will not be operated outside its limits. This ensures the EGTS emhaust danper. The second part of this test consists of that the probability or consequences of an accident or matfmetion of
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n . - . . _ _ . _ . _ ~.- . .. . Page No. 13 " 02/22/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 WRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
g inputting a simulated accident signal into the danper controtter and equipment important to safety will not increase. This also ensures the recording the controller output along with measuring the start of opening possib!!ity for an accident of a type different from that previously and the completion of opening times for the enhaust danper, evaluated will not increase.
** Sit-065 CONTAINMENT SPRAY PUMP PERFORMANCE - UNIT 2 REV NO. 000 This instruction was written to test and document the CSP performance data. This test will not involve a change in the facility or plant operating characteristics. The test wilt be conibcted without a change to T.S.
3.6.2.1.
** STI-066 POST MODIFICATION TEST OF SACKDRAFT DAMPEES REV NO. 000 This instruction provides a functional test for the safety-related This instruction verifies cooling and ventitation to ESF a@ipsont and backdraf t despers replaced by WP 9256 and WP 9341. ensures operability which reduces the probability or Consequences of an accident. These backdraft dampers and associated air handling equipment have a redundant (100 percent capacity) unit with contr'ots to start on low flow by the other unit or high teeperature in the associated area (space cooters only). Therefore, the starting or stopping o? equipment will not af fect its safety function. The cettection of data for calculating air flow will not affect system operability.
t
** STI-072 D/G 1A-A RESTART TEST - UNIT 1 REV No. 000 This instruction was written to verify items of the functional analysis This test was implemented without a change to the T.S. The test did not report for system 82. involve new procedures or instructions, or revisions to instructions or procedures, that are different from the procedures as dr$cribed in the FSAR or plant T.S. No margin of safety has been redJced.
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Page No. 14 02R2/88 SEQUOYAN NUCLEAR PLANT to v.ta 50.59 1987 NRC ANNUAL OPERAi!NG REPORT CMANGES TO PROCEDURES AS DESCRIBO IN THE SAR DESCRIPTION 5AFETY
SUMMARY
518-074 D/G 2A-A RESTART Test - tmtf 2 REV No. 000 This instraection was written to verify items of the fmetionet armlysis This test was implemented without a charrje to the T.S. The test did ret report for systems 82 and 70. lnvolve new procedses or instructions, or revisions to instructions or pr ocedar es, that ar e de f f es ent f ew the frocedures as descrited in the ISAN or plant T.S. The performance of this test will not rashce the margin of safety. STI-081 M2 ANALY2ER VALVES 2A AND 23 FAIL SAFE POstTION TEST - UNIT 2
#EO NO. 000 Thle instruction was written to verify that the hydrogm analyzer this instruction will not irwolve procedares eAlch are dif ferent fram the containment isolation vetves 2-fCV-43-201A, -202A, -207B, and -208s f ait procedures as described in the isAR. This test does not involve T.S.
open on the loss of control air and f ait closed on the toss of electrical regairements for mode 5 operation. power.
** $11-083 CONTROL 90!LDING EMERGENCY PRES $URIZATION/VENillATION TEST - UNITS 1 AND 2 REV No. 000 This instruction was written to obtain date white temporarity attering the the data obtained will attow ONE to determine eAlch flow path and aligrument ret configuration of the control building ventitation system during a changes are necessary to resolve control rocas amergency ventitation controt room isolation signet, inteskage and pressurization problems. The probability of an accident will not be increased, and the possibility for an accident of a different type will not be created. The margin of safety, as defined in the basis of any T.S., will not tw redxed.
4 *O 518-105 ERCu CONTAINMLNT is0LAf t04 CFECK VALVE TEST Rtv No. 000 This instruction witi instatt and test replacements f or the tRCW The plant witi be in mode 5 during testing. None of'the equipment affected
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_ . - , -. - . _ . . .. . - _~ . .. _. Page No. 15 02/22/88 SEQUOTAN NUCLEAR PLANT 10 CFR 50.59 1987 mRC amam*L OPERATING REPORT CnANGES TO P90CEDURES AS DESCRISED IN THE SAR DESCRIPTION SAFETY Susse4RY g y conteirament isolation volves 67-562A, -562s, -5620, and 5620. Atwood by this test is needed to perform o safety function, and it is not required foorriti scf t-seat check volves witI be installed and tested per $1-158.1. . operable in mode 5. The probability or connespaances of a previously-The current Anchor Derting swing check vetves have repeatedly felled locet onetyred accident or espJigunent snetfunction will not be increesed, and no . teek rete teating. onenetyred occident ulti be created. The mergin of safety, as defined in the T.S., will not be reduced. ] 4 4 s u 4 i 4 9 1 d 4 4
=
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Page No. 1 02/26/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT SPECIAL TESTS PERFORMED IN 1987 DESCRIPTION SAFETY ANALY$15 I
** STI-10 CCS INLEAKAGE SPECIAL TEST REV 000 This test was performed to tocate and docment any inteakage of radioactive This test did not increase the rate of equipment failure. No alignment water into the CCS. used was abnormet to the system design. The probability of an occurrence or the consequences of an accident or matfmetion were not increased. The possibility for an accident of a dif ferent type than previously evaluated was not created. The margin of safety, as described in the basis of any T.S., was not redJced.
** STI-11 PLANT CDMPUTER ROOM VENTILATION TEST RED OCG This test was performed to resolve SPOS availability problems. This test collected the data regelred to make modifications to the plant computer room ventitation system. This increased SPOS avaltability. The probability of ar occurrence or the consequences of an accident or matfunction were not increased. The possibility for an accident or malfunction of a different type than any previously evetuated was not created. The mergin of safety, as defined in the basis of any T.S., was not reduced.
** STI-12 MAIN STEAM ISCLATION VALVE SPRINGS PROOF TEST REV 000 This test performed a compression test on the MS!V springs to ensure The "Vatve Stress Review' and "Fracture Mechanics Analysis on Springs
- continued reliability of the MSIV springs for at least 960 additional ensure continued reliability of the MSIV springs for at least 960 cycles, additional cycles. This test did not ispelr the fmetion of the MSIV or create a possibility for an accident or metfunction of a different type than previously evaluated. - The test was performed dt. ring cold shutdown
- mode and did not degrade any margin of safety.
c* STI 14 NONDESTRUCT!vt TESTING OF IN-PLACE CONCRETE PER ASTM STANDARDS C803 AND C805 - UNITS 0,1, and 2 REW 000 This test was performed to determine the penetration resistance of hardened The test methods did not degrade the integrity of the structures. The concrete and rebared nurt;er of hardened concrete at various locations procedure ensured no embedded conduit, component, or piping was jeopardized throughout the plant, by this test. ASTM-approved nondestructive tests were performed by certified technicians. No areas were tested where the 90-day compressive
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Page No. 2 02/26/88 SEQUOYAM NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERAllNG REPORT SPECIAL TESTS PERFORMED IN 1987 DESCRIPi!ON SAFETY ANALYSIS I strength is tess than 2000 psi. The probabitity of an occurrence or the consequences of an accident or metfunction were not increased. The possibility for an accident or malf metion of a different type than previously evaluated was not created, The T.S. does not address testing of concrete structures. The margin of safety was unaffected by this test.
- STI-17 DC NIGN VOLTAGE TEST FOR SELECTED UNIT 21E CABLES IN VERilCAL DROP CUNFICURA'!ON REV 000 This spectat test was performed to demonstrate the adequacy of the cordait This test was performed on one safety train at a time. The redtsident train and cable instattation at SON and to verify the performance capabilities of was ensured to be operable to support mode 5 operation. The plant design the conduit and cable system. configuration was restored and documented. Plant operating parameters and system setpoints were not altered. F metional tests were performed at the conclusion of cable testing to ensure T.S. compliance. The probability of an occurrence or the consequences of an accident or malfmetion of equipment were not increased. The possibility for an accident or metfunction of a different type than previously evaluated was not created.
The margin of safety, as defined in the basis of any T.S.i was not reduced. C STI.18 DC EMERGENCY LIGNIS INRUSM CURRENI - UN!is 1 and 2 REV 000 This test was performed to measure and record the inrush current created by This test only affected circuits related to dc W rgency tighting, and the the de emergency lighting on the vital batteries during loss of of f site ac lighting system was not placed in abnorsaat alignments. Only one board was, or ati sc. tested at a time, and atI testing was performed with both mits in modes 5 or 6. The probability of an accurrence or the consequences of an accident or metimetion of equipment were not increased. The possibility for an accident or metf metion of a different type than previously evaluated was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
- STI.19 DC NIGN VOLTAGE TEST FOR SELECTED 1E CABLES WITM PoiENTIAL FOR CABLE JAMMING - UNils 1 and 2 REV 000 This special test performed a dc high voltage test on selected IE cables to The test was performed on one safety train at a time. It ensured that the at Leviate concerns regarding damage due to cable jamming in conduit. redmdant train was operable to swpwt sede 5 operation. ALL the involved systems and conponents were isolated and protected. The test did not
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Page No. 3 02/21/66 St axn A*: Maia. ruNr l 10 CFR 50.59 l 1987 NRC ANNUAL OPERATING REPORT SPECIAL TESTS PERFORMED IN 1987 1 DESCRIPil0N SAFETY ANALYSl3 i systems and components were isolated and protected. The test did not affect the plant configuration permanently. The plant design configuration was restored and downented. The plant operating parameters or system l setpoints were not attered. The probability of an occurrence or the consequences of an accident or malfunction were not increased. The possibility for en accident or malfunction of a different type than l previously evaluated was not created. The margin of safety, as defined in the basis of any T.S., was not reduced. STI-20 CONTAINMENT ISOLATION VALVES WILI. REMAIN CLOSED AFTER RESET OF THE CONTAINMENT ISOLATION SIGNAL - UNIT 2 REV C00 This test was performed to verify contairment isolaticri vn tves listed in This test is described in Section 6.2.4 of the FSAR. The test did not accordance with T.S. table 3.6-2, plus valves 2FSy-30-1% sd -135, minus involve a change in the facility or plant operating characteristics f rom the containment ventitation isolation valves, remained closed af ter reset that described in the FSAR. The test did not involve new procedares or of a contalrument isolation signal (phase A or 8). instructions that are dif ferent f rom the procedJres described in the ISAR or plant T.S. The test was performed without a change to plant T.S. C+ Sil-21 , DC NIGN VOLTAGE TEST FOR SELECTED 1E CABLES WITN POTENTIAL FOR CABLE PdLL8Y DAMAGE MC17348 - UNITS 1 and 2 REV CD0 This test was performed on selected 1E cables to atteviate concerns This test was performed on safety train P for specific components. Train A regarding possible damage due to cable putIbys in con &Jit MC1734B. was operable to support att equipment that is necessary to f metion during mode 5 operations. Sit-21 and applicable procedures ensured that the test cables and conductors disconnected, tested, and restored (as wetI as other cables and conductors disconnected and restored) did not af fect equipment or components whose fatture or actuation may increase the probability or consequmces of an accident or malf unction of cvJipacnt important to safety. Plant design and construction ensured adegaate isolation between the test cables and other cables. The possibility for an accident of a different type than previously evaluated was not created. The maargin of l safety, as defined in the basis of any T.S., was not reduced.
** STI.22 DC NICM VOLTAGE TEST #0e SELECTED 1E CASTE WIIM 001ENil AL FOR CABLE PULL 8Y DAMAGE CONDUli MC17288 - UNITS 1 and 2
- sEU 000 This test was pef formed on selected 1E cables to alleviate concerns This test was performed on safety train 8 for specific components. Train A s
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. . - . - . = - .- ._. . . _
s Cage No. 4 02/26/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 N*C ANNUAL OPERATING REPORT SPECIAL TESTS PERFORMED IN 1987 DESCRIPTION SAFETY ANALYSIS i mode 5 operation. The test was performed in accordance with STI-22 and applicable procedures .Aich ensured that the test cables and consbetors disconnected, tested, and restored (as well as other cables and contbctors disconnected and restored) did not af fect egipment or components iAose failure or actuation may increase the probability or consewences of an accident or malfunction of equipment important to safety. The possibility for an accident or malfunction of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
** STI-23 DC MIGN WOLTAGE TEST FOR SELECTED 1E CABLES WITN POTENTI AL FOR caste PULLEY DAMAGE CONOUIT MC1728A - UNITS 1 and 2 REV 000 This test was performed on selected 1E cables to allewlete concerns This test was performed on safety train A for specific components. Train 5 regarding possible damage dJe to cable pullbys in conduit MC17234. was operable to support att e w ipment that is necessary to function during made 5 operation. STI-23 and applicable procedures ensured that the test cables and conductors disconnected, tested, and restored (as well as other cables and conductors disconnected and restored) did not,af fect equipment or components whose f alture or actuation may increase the probability or consequences of an accident or matfmetion of ewipment leportant to safety. Plant design and construction ensured adequate isolation between the test cables and other cables. The possibility for en accident of a different type than previously evaluated was not created. The margin of safety, as defined in the basis of any T.S., was not redJced.
** STI.24 DC NIGN VOLTAGE TEST FOR SELECTED 1E CABLES UliN POTENTIAL FOR CA8tE PULL 8Y DAMAGE CONouti MC1750A - UNITS 1 and 2 REW 000 This test was performed on selected 1E cables to atteviate concerns 1his test was performed on safety train A for specific components. Train B '
regarding possible damage dJe to cable putibys in conduit MC1750A. was operable to support ati equipment that is necessary to function during made 5 operation. STI-24 and appt(cable procedures ensured that the test cables and conductors disconnected, tested, and restored (as well as other cables and conductors disconnected and restored) did not af fect ewipment or components whose failure or actuation may increase the probability or conse w ences of an accident or malfunction of e w ipment important to safety. Plant design and construction ensured adequate isolation between the test cables and other cables. The poss 8 bility for an accident of a
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Dage No. 5 02/26/88 StoUOYAN NUCLEAR PLANI 10 CIR 50.59 1987 WRC AmuuAL OPERAi!NG REPORT SPECIAL TE$is PERFORMED IN 1987 DESCRIPTION SAIETY ANALYSIS i dif ferent type than previously evaluated was not created. The margin of safety, as defined in the basis of any T.S., was not redaced.
** 518 25 DC NIGN VOLTAGE TEST FOR SELECTED 1E CABLES UliN P0f tsfl AL CASLE PLAL8Y DAMAGE CONDUIT MC 1754A - Units 1 and 2 REW 000 This test was performed on selected IE cables to at Leviate concerns This test was performed on safety train A for specific components. Train S regarding possible damage due to cable puttbys in condait MC17544, was operable to stoport att egalpment that is necessary to fiartion during mode 5 operation. 518-25 and agpticable procedures ensured that the test cables and conductors discormected, tested, and restored (as weit as other cables and conductors disconnected and restored) did not af fect egalgzuent or components whose failure or actuation may increase the probability or consequences of an accident or matfunction of egalpment laportant to safety. Plant design and construction ensured adequate isolation between the test cables and other cables. The possibility for an accident of a different type than previously evaluated was not created. The margin of safety, as defined in the basis of any T.S., was not redaced.
** sil-26 DC NIGN VOLTAGE Test FOR SELECTED 1E CABLES WITN POTENTIAL F0E CABLE PULL 2Y DAMAGE MC1 DOS - tmlis 1 and 2 SEO 000 This test was performed on selected 1E cables to atteviate concerns This test was performed on safety train 8 f or specific components. Train A regarding possible damage dae to cable puttbys in conduit NCIDOS. was operable to st@ port att equipment that is necessary to fisiction during mode 5 operation. STI-26 and applicable procedares ensured that the test cables and condactors disconnected, tested, and restored (as weit as other cables and condactors disconnected and restored) did not ef fect equipment or components whose failure or actuation may increase the probability or consequences of an accident or malfunction of egalpment leportant to safety. Plant design and construction ensured adequate isolation between the test cables and other cables. the possibility for en accident of a different type than previously esatuated was not created. The margin of.
safety, as defined in the basis of any T.5., was not redeced. 57I.87 , DC n!GN WOLTAGE TEST FOR SELECTED 1E CABLES WITM POTENTI AL FOR CABL8 PULLBY DAMAGE - CONOUlT MC1751A - tmtis 1 and 2 aEV 000 This test was performed on selected 1E cables to atleviate concerns This test was performed on safety train A for specific components. Train 8
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Page me. 6 02/22/88 SEQUOTAN NUCLEAR PLANT 10 CFR 50.59 1967 NRC ANNUAL OPERATING REPORT SPECIAL TEsis PERf0RMED IN 1967 DESCRIPTION $AFETY ANALYSIS . 571-27 DC MSGN WOLTAGE TEST FOR SELECTED 1E CA8tES WITN POTENII AL FOR CA8tE MILLEY DAMAGE - CONDUIT MC1751A - UNITS 1 and 2
#EV 000 This test asas performed en selected 1E cables to alleviate concerns This test was performed on safety train A for specific components. Train S regarding possible damage due to cable putttys in cordait feC1751A. was operable to support att equipment that is necessary to function daring sede 5 operation. The test was performed in accordance with STI-27 and applicable procedares which ensured that the test caldes and conductors disconnected, tested, and restored (as well as other cables and con & actors disconnected and restored) did not af fect egalpment er components adnose -
fatture or actuation may incresee the probability or consegaences of an accident or metfunction of egalpoent important to safety. Plant design and construction ensured adequate isolation between the test cables and other cables. The possibility for an accident or motfunction of egalpoent of a different type was not created. The margin of safety, as defined in the basis'of any T.S., was not reduced.
- 571 31 DC NIGN WOLTAGE TEST FOR SELECTED 1E CASLES WITN POTENTIAL FOR CA8LE PULLOY DAMAGE - Co e UIT 1732s - UNITS 1 and 2 - !
REV 000 This test was performed on selected 1E cables to alleviate concerns The test was performed en safety train 8 for specific components. Train A ;l regarding possible demoge dae to cable put tbys in conduit MC1732s. was operable to support att equipment that is necessary to fmction during ' ) mode 5 operation. 57131 and applicatde procedares ensured that the test l cables and con 6 actors disconnected, tested, and restored (as mett as other ' cables and conductors disconnected and restored) did not af fect egalpment or components whose falture or actuation mey increase the probability or consegaences of an accident or motfunction of egaipment leporta.x to safety, Plant design and construction ensured adequate isolation between the test cables and bther cables. The possibility for an accident of a different type than previously evaluated was not created. The mergin of
. safety, as defined in the basis of any T.S., was not reduced.
~ sit-32 OC NIGN VOLTAGE TEST FOR SittCTED 1E CABLES Wiin PoituilAL f 0R CA8LE PULL 3V DAMAGE - CONDUIT MC1731s - UNats 1 and 2
- EV 000 This test was performed on selected 1E cables to alleviate concerns This test was performed on safety train 5 for specific components. Train A regarding possible damage due to cable pullbys in conduit MC1731s. was operable to sigport att equipment that is necessary to imction during mode 5 operation. The test was performed in accordance with STI-32 and -
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l Page No. 7 02/22/88 TEQUOTAN NUCLEAR PLANT to Cfa 50.59 1987 NRC ANNUAL OPERATING REPORT SPECI AL TESTS PERFORMED IN 1937 DESCRIPTION SAFETY ANALYSIS g applicable procechares which ensured that the test cables and conductors disconnected, tested, and restored (as well as other cables and conductors disconnected and restored) did not af fect e@ipment or components whose failure or actuation may increase the probability or consequences of an accident or metfunction of equi;snent important to safety. Plant design and construction ensured adequate isolation between the test cables and other cables. The possibility for an accident or malfmetion of a dif ferent type was not created. The margin of safety, as defined in the basis of any T.S., was not reesced.
** STt-33 OC NIGN VOLTAGE TEST FOR SELECTED 1E CABLES W11N POTENTIAL FOR CABLE PULL 87 DAMAGE CONDuti MC14938 - UNITS 1 and 2 REO 00G This test was performed on selected 1E cables to atteviate concerns This test was performed on safety train B for specific components. Train A regarding possible damage due to cable pullbys in conduit MC14938. was operable to set att equipment that is necessary to fmction daring ,
mode 5 operation. STI-33 and applicable procedures ensured that the test cabtes and conductors disconnected, tested, and restored'(as wett es other cabtes and conductors discomected and restored) did not af fect ewipment or components whose fatture or actuation may increase the probability or consequences of an accident or malfunctico of easipment important to safety. Plant design and construction ensured adegante isolation between the test cables and other cables. The possibility for en accident or metfunction of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
** STI-34 DC MIGN VOLTAGE TEST f 0R SELECTED 1E CABLES WIIM POTEhfl AL 90R CABLE PullSY DAMAGE Con 0UIT MC14978 - UN'TS I and 2 REW 000 This test was performed on selected 1E cables to atteviate concerns this test was performed on safety train 8 for specific components. Train A regarding possible damage due to cable pullbys in conduit MC14978. was operable to s(pport att equipment that is necessary to fmetion during ar=3e 5 operation. STI-34 and applicable procedures ensured that the test cables and conductors disconnected, tested, and restored (as weti as other cables and conductors disconnected and restored) did not af feet eg.signent or components whose failure or actuation muy increase the probability or cca.cquences of an accident or matf4.siction of equigewet important to safety. Ptant design and construction ensured adegute isonation between l
I
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_ _. _ ~ _ _ _ _ . ..m_ . _ _ _ ~ . . - . ._. . . _ - . _ _ . _ _ - - . .. -_ _ . . . _ . . . Page he. 8 02/22/88 SEQUOTAN NUCEEAR PLANT 10 CFR 50.59 1987 NaC AmNUAL OPERATING REPORT SPECfAL TCSTS PERFORMED IN 1987 1 DESCRIPT10r SAIETT ANALYSIS the test cables and other cables. The possibility for an accident er metfunction of a different type than previously evaluated was not created. The margin of saf ety, as defined in the basis of any T.5., was not redaced.
** 518-37 CASLE TRACING TEST ON POWER AND CONTROL CA8LES FOR SELECTED 1E EQU!PMENT ERCW PUMP N-S - UNIIS 1 and 2 REW 000 This test perf ormed cable tracing of power and control cable routing to The performance of this test was within the safety evaluation provided in ERCW gamp N-B to verify consistency with applicable plant drawings. FSAR, Section 9.2.2.3.2, and within the T.S. bests described in 3/4.7.4 Cable routing verification introduced a low-vottage, low-amperage trace signal to the power and control cables of ERCW pump N-8. These cables were not esposed to voltages and currents in excess of their destyi. After cable tracing, ERCW gamp N-S was proven completely operationet. ** STI-38 CABLE TRACING TEST ON POWER AND CONTROL CABLES FOR SELECTED 1E EQUIPMENT ERCW PUMP R-A - UNIIS 1 and 2 REV 000 This test performed cable tracing of power and control cable routing to The performance of this test was within the safety evaluation provided in ERCW gump R-A to verify consistency with applicable plant drawings. FSAR, Section 9.2.2.3.2, and within the 7.5. basis described in 3/4.7.4.
Cabte routing verifIca: ion introduced a (ow-vottage, tow-amperage troce signet to the power and control cables of ERCW pump R-A. These cables were not exposed to voltages and currents in encess of their design. After cable tracing, ERCle pump R-A was proven completely operationet.
** STI-40 caste TRACING TEST 04 POWER AND CONTROL CASLES FOR SELECTED 1E EQUIPMENT FCV-67-138 REW 000 Th's test performed cabte tracing of power and control cable routing to this test was within the safety evaluation provided in the FSAR, Section '
containment vent cceter valve 2-fCV 67-138 to verif y consistency with 6.2.4.1, a w1 f.5. 3/4.6.3. valve 2-fCV-67-138 was temporarity taken out of appticable plant drawings, service for this test during cold shutdown. Section 6.2.4.1 of the 75AR states that contairunent isolation is not regaired during cold shutdone. A l ow-vol t ry, tou-aaperage trace signal was introduced to the power and controt :abtes of valve 2-fCV-67-138. These cables were not esposed to voltages and currents in excess of their design. After cable tracing was coeptered, valve 2 fCV-67-138 was proven completely operational. The cables were restored to their originsi configuration, and the vatwe was functionalty tested and documented.
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Dage No. 9 t 02/22/88 SEQUOYAN NUCLEAR PLANT to CFR 50.59 1957 NRC ANNUAL OPERATING REPORT SPECIAL TEST $ PERFORNED IN 1987 DESCRIPTION SAFLtY ANALTSl$
*O sit-42 DC NIGN VOLTAGE TEST FOR SELECTFD UNIT 21E CABtLS (SILICONE RUB 8ER CABLES)
REV 000 This STI arptied a de high potential tc selected silicone reber cables The test was performed on safety train A for specific components. Train 5 inside smit 2 contairment. These are control and power cables, type SROAJ, was operable to support att equipnient that is necessary to f metion during manuf actured by the A!W Corporation, Rockbestos, and Anaconda. The test anode 5 operation. It was ensured that the test cables and conductors was performed to alleviate concerns of possible cable damage. disconnected, tested, and restored (as wett as other cables and conductors disconnected and restored) d'd not af feet egalpment or components idiose fatture or actuation may increase the probability or consegaences of an accident or malfunction of equipment important to safety. Plant design and construction ensured adegJate isolation between the test caldes an6 cther cables. The possibility for en accident or malfunction of equipent of a different type than previously evaluated was not created. The plant operating parameters or system setpoints were not affected or altered. The margin of safety, as defined in the basis of T.S. 3/4.6.3, was riot redaced.
" STI-43 DC NIGN VOLTAGE TEST FOR SELECTED Uhli 21E CA8tES (SILICONE RUSSER CA8tES) eEV 000 This STI arctied a de high potential to selected siticone rubber cables The test was performed on safety train a for specific components. Train A inside unit 2 contaiement. These are SROAJ type controt cables was operable to support att equipment that is necessary to fmction during emnuf actured by the AlW Corporativi. The test was performed to atteviate mode 5 operation. It uas ensured that the test cables and conductors concerns of posslote cable damage. discorwected, tested, and restored (as weit as other cables and conductors disconnected and restored) did not af f cct egatpment or components whose f atture or actuation may increase the protability or consequences of an accident or malfunction of egaipment important to safety. Plant design and construction ensured adegaste isolation between the test cables and other cables. The possibility for en accident or matfunction of equipment of a different type than previously evaluated was not created. The plant clerating parameters or system setpoints were not af fected or attered. The margin of safety, as defined in the basis of T.S. 3/4.6.3, was not reduced.
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fage No. 10 02/22/88 SE000 VAN NUCLEAR PLANT 10 CfR 50.59 1987 NRC ANNUAL OPERAI!NG REPORT
$PECIAL TEsiS PERFORMED IN 1987 DESCRIPit04 SAFETY ANALYSIS
- STI-4 DC NIGN VOLTAGE TEST FOR $ ELECTED UNIT 2,1E CABLES ($ILICONE RUBSER CABLES)
REV 000 This test was performed on selected 1E cables to atteviate concerns This test was performed on safety train A for specific components. Train 5 regarding possible damage to the cables. was operable to sigport att equipment that is necessary to function during mode 5 operation. STI- M and applicable procedures ensured that the test-cables and conductors disconnected, tested, and restored (as wett as other cables and conductors disconnected and restored) did not af fect equipment or components whose failure or actuation may increase the probability or consegaences of an accident or malfunction of egalpment leportant to safety. Plant design and construction ensured adequate isolation between the test cables and other cables. The possibility for an accident of a different type than previously evaluated was not created. The margin of safety, as defined in the basis of any T.s., was not reduced.
- STI47 DC N!GM VOLTAGE TEST FOR SELECTED UNIT 21E CABLES ($!LICONE RUB 8ER CA8LES)
REV 000 This test was performed on selected 1E cables to alleviate concerns The test was performed on safety train 8 for specific components. Train A regarding possible damage to the cables. was operable to st@ port att equipment that was necessary to fmetion daring mode 5 operation. ST!-47 and applicable procedares ensured that the test cables and condactors disconnected, tested, and restored (as wett as other cables and condactors discomected and restored) did not af fect egJipment or components whose f ailure or actuation may increase the probability or consequences of an accident or metfunction of egJipment important to safety. Plant design and construction ensured adequate isolation between the test cables and other cables. The possibility for an accident of a different type than breviously evaluated was not created. The margin of safety, as defined in the basis of any T.5., was not redaced.
- $18-52 DC NIGN VOLTAGE TEST FOR CLASS 1E to CFR 50.49 SILICOkE RUBEER INSULATED CABLES REW OC3 This STI applied a dc high voltage potential to class 1E 10 CTR 50.49 This test was performed on esbtes in both safety train A and 8 for specific silicone ruther insutated cables inside contairenent. These are $R043 type corponents. One safety train was always operable to sspport at t er#sipment control and power cables manuf actured by AlW, Rockbestos, and Anaconda, that is necessary to function during node 5 operation. 518-52 and the test was perf ormed to atteviate concerns regarding possible damage. afpticable procedures ensured that the test cables and conductors a
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- . .m . - __ . - _ - . . . ._ ._- . _ _ _ _ . _-.--.m .. _ ._ _ _ _ . _ _ m Cage uo. 11 02/22/88 _
SEQUDYAN NUCLEAR PLAuf + 10 CFR 50.59 1987 mRC AmmuAL OPERATING REPORT SPECIAL TESTS PERFORMED IN 1967 DEsta!PTION SAFETY ANALYSTS desconnected, tested, and restored (as well as other caldes and conductors discomected and restored) did not af fect equipment or components whose f ailure or actuation may increase the probobility or consegmences of an accident or motfwiction of egJipment leportant to safety. Plant design and construction ensured adequate isolation between the test cables and other cables. The possibility for an accident'of a different type than previously evaluated was not created. The mergin of safety, as defined in the basis of any T.S., was not reesced. q
** STI-54 CAsit TRACIWG !EST ON SELECTED CONTROL CABLES REW 000 This test was performed to verify the roustry of specific cables instatted This test was performed within the safety evaluation provided in Section in the raceways. 9.5.1 of the FSAR and within the 7.5. basis described in 3/4.3.3.8. Att the regJirements of PHYSt-13, Appendix C, were met. Cable routing serification introduced a tou-vottage, low-asperage trace signal to the controt cables of the fire detection zones 127,128, and:133 retay contacts. These cables were not s AJjected to voltages and currents in escess of their design. When cable tracing was completed, the fire 2
detection tone relay contact cae:tes were restored and proven operable in
^
accordance with functiond tests. The probability of an occurrence or -
, consequences of an sicident were not increased. The possibility for an accident or malfunction of egalpment of a dif ferent type than previously evaluated was not created. The margin of safety, as defined in the basis of any T.$., was not reduced. ** 511-41 1RCV/ AUX C041ROL Alt COMPRESSOR TEST l Civ 000 This test was perf ormed on various ERCW equipment to verif y the heat toad The retoestiwt of the throttle volve prevented over-pressurization of the
- removing capability and record the maalaum flow avallatite. This also compressor which has a' tower (esign pressure rating than the ERCW system.
established a new throttle valve and its position foi teth ACA air At no time during the test has ERCW flow at towed to decrease below the eareressors based en a min / man ftow. min / man at towable limit. Att ACA compressor testing was performed after the conpressor had been placed in an inoperable status. Since only a-maximum flow rate was Mied to the existirq minnaue flow rate, th+re w no reduction in the margin of safety for the ACA compensor. The ibw data i
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l rage me. 12 02/22/88
$EQUOVAN NUCLEAR PLANT 10 CFR 50.59 1987 WRC ANNUAL OPERATItG REPORT
$PECI AL TESTS PERFORMED IN 1987 J
otsca selloss LAs(17 Amatysis i ta6ns for other equf gment ises above the minisess flow regaired, and the 6ystc1e was returned to reormat af ter cessplettort of the test.
** $TI-45 D/G 18-B LOAD SEQUENCE TEST - UNIT 1 AEV 000 This test esos perforard to collect data for DesE to ewatuste dieset This test is described in the f SA4, Section 4.3, R.G.1.19 and 1.108. The ,_,
generator 15-8 worst-case loading segaence. test did not inwotwe a change in the plant facility er plant aperating i characteristics from that described in the isAR. The test did not involve new procedares or instructions thet are different from the proceshsres as described in the isAt or plant f.S. The test med performed without a change to the plant'T.S. t i ;
** STI-64 AEsponSE OF THE EGTS Comie0LLERS Amp ENNAUST DAMPER TO A SIfeULATED ACCIDENT CONDITION - UulTS 1 and 2 ~ .
SEV 000 This test is divided into teso ports. The first port consists of iryutting This test had no effect on the safety of the plant because the test esos ' e step change of the mitilano control signet to the I/P damper positioner performed in modes 5 or 6 when the ECTs system ises not respaired to be and smessuring the start of opening and the completion of opening times for operable. A sismateted annutus pressure transient as shoun in f 5AR, figure the EGT5 es%eust dumper. The second part of this test censists of 6.2.3.7, esos used to test the dumper centrol system, and the system asas not inputting a sinutoted accident signet into the damper controtter and operated outside its design limits. This ensured the prebebility or recording the controller output along with riessuring the start of opening consegaences of a metfunction or equipment important to safety asere not and the cass>tetton of opening times for the enhaust damper. - increased. This also ensuPed the possibility for an accident or malfunction of <valgammt of a ditferent type esos not created, the margin - of saf ety, as defirwd in the basis of any T.$., asas not reduced.
? .
** STI-45 C04tAltsMENT SPRAY PUMP PERf0RMA88CE - UNIT 2 mEV 000 This test was performed to test and document the samp performance data and This test is described in tabte 14.1 1, 5 sheet 95, of the fsAR. The test
- other trtated inforsestion. did not irwolve a charvje in the f acility or plant operettrup characteristece f run that described in the f SAR. The test did not irwotwe new procedures or instructions that are dif ferent f rom the procedares as described in the - .,
85A8 or plant I.S. .The test was performal without a change to T.S. h-Y 3.6.2.1. s
) f I
i -133-
m _ _ _ . . - --.__.~-_-----_m.--. -- _ _ _- - _. . _ - - . .m . . . . - . . . _ m__ . _m . . .. Page so. 13 02/22/86 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT SPECIAL TESTS PERFORMED IN 1967 DEsca!PTION SAFETY ANALYSIS
" STI-72
, D/G 1A-A RESTART V!ST - UNIT 1 REW 000 This test was performed to verify the fottowing: This test is described in section S.3 and section 14.1 of the f5AR. The test did not invotwe a change in the facility or plant operating , (1) The dieset wilt trip on N NT, low LOP, and high CP. characteristics from that described in the f5AR. The test did not inwotwe new procedtses or instructions that are different from the proceekres (2) The dieset will not trip on a NNT, low LOP, and high CP trip with an described in The FSAR or plant T.S. The test was performed without a emergency start signal present, change to T.S. 3.4.1.2, T.S. 3.7.3, T.S. 3.7.4, or T.S. 3.7.1.2. (3) Overspeed trip is not blocked eAen en emergency start signal is present. (4) manual control of the dieset is blocked seen an emergency start signal is present. (5) The pwup time of the air cogressors is verified. ' pr (6) The dieset uitt acceterate to rated speed and flash the field from an idle condition following an emergency start. (7) The resetting of the blackout sequence timer by the SI reset timer is verified for the fottowing pumps: AfW pump 1A A, ERCW pump J-A, and CCW pg 1 A- A. C STI 73 D/G 18-8 RESTART TEST - UNIT 1 ' RED CIS This test was performed to verif y the fottowings . This test is described in section s.3 and Section 14.1 of the (SAR. The test did not invotwe a change in the facitity or plant operating. (1) The dieset will trip on a NNT, low 10P, and high CP. characteristics from that described in the f5AR. 'The test did not inwotwe tww procedures or instructions that are dif ferent .from the procedures (2) The dieset will not trip on a nNT, low LOP, and high CP trip with an descritnf in the FSAR or plant T.S. The test was performed wit > cut a emergency r. tart signal present. change to T.S. 3.8.1.2 and T.S. 3.7.1.2. (3) Overspeed trip is not blocked when an emergency start signal is a
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Page No. 14 02/22/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT SPECIAL TEST $ PERFORMED IN 1967 DESCRIPTION SAILf7 ANALYSIS . I present. (4) 8sanuel control of the Jieset is Stocked when an emergency start signet is present. (5) The pump-w time of the air compressors is verified. (6) The dieset will accelerate to rated speed and flesh the fletd from an idle condition f otlowing an emergency start, (7) The resetting ef the blackout segaence timer by the 51 reset t;mer is verified for the AFW pg 18 8.
- 5T1 74 D/G 2A-A RESTART TEST - tmti 2
~
REW 000 This test was performed to verify the following: This test is described in Section 8.3 and Sectlan 14.1 ef'the f54R. The' test did not involve e change in the facility or plant eperating (1) The dieset will trip on a N NT, low LOP, and high CP. characteristics from that described in the FSAR. The test did not involve new procedures or instructions that are different from the procedures (2) The dieset will not trip on a MJWT, low LOP, and high CP wita en described in the F5AR or plant T.S. The testing was performed without a emergency stort slywt present. change to T.S. 3.8.1.2, T.S. 3.7.3, or T.S. 3.7.4. (3) Overspeed trip is not blocked when an emergency start signal is present. (4) The Emmy-w time of the air compressors is verified. (5) The dieset witt accelerate to rated speed and flash the field from an idle condition foitowing an emergency start. (6) The 51 reset timers for ERCW peps E- A and R-A and CCW pump 2A-A reset the blac6out se< pence timer en an SI aignaL. (F) Manual contret of the dieset is blocked when an emergency start signet
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Pope he. 15 02/12/88 SEQUOYAn NUCLEAR PLANT 10 CFR 50.59 1987 mRC Amuunt OPERATING REPORT SPECIAL TEsis PERFORMED IN 1987 DESC&lPil0N SAFETY ANALYSIS is present. (8) The CCW pwp 2A-A will not stort on low header pressure for 20 seconds following a blackout. ST3-75 D/G 2s-s REJTART TEST - UNIT 2 at"J 000 This test was perforand te verify the following: this test is described in Section S.3 and Section 14.1 of the FSAR. The test did not inwotwo a change in the facility or plant operatin8 (1) The dieset wilt trip en e NJWT, low LOP and on higte CP. characteristics from that described in the PSAR. The test did not invetwe new procederes or instructions that are different from the preconsres (2) The dieset will not trip en a NJWT, low LOP, and high CP with an described in the FSAR or plant T.S. The test was perfereed without a emergency stort signet present. change to T.S. 3.8.1.2, T.S. 3.7.3 and T.s. 3.7.4. (3) Overspeed trip is not blocked adwo an emergency start signal is p, ,,,,.t . 8+ (4) manual control of the dieset is blocked when an emergency start signet is present. (5) The pwee time of the air compressors is verified. (6) The dieset witt accelerate to rated speed and f tash the field f rom an idle condition fot towing an emergency. (T) The 51 reset timers for ERCW pop P-8 and M-5 and CCW pump 2s s reset the bisckout sequence timer en an $1 signal. I (8) the CCW pump 25 B witt not start on tow header flow for 20 seconds following a blackout.
- 511 73 CONTROL BulLDimG BAliERY DMAU$T FAN C-B 150t ATION DAMPER TEST - UNITS 1 and 2 DEV CD This test was performed to verify the control building battery room eshaust this test is described in Chapter 14 of,the FSAR. The test did not irwotwe .
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Page to. 16 02/26/88 SEQUDYAN NUCLEAR PLA4T 10 Cf R 50.59 1987 meC ANNUAL OPERATimG REPORT SPECIAL If 515 PERf 0RMED IN 1967 D(5CalPflou SAfElf AeALYSIS l
~
F5As or plant T.S. The test was performed without a change to T.S. 3/4.7.7.
** STI-77 D/G 2A*A ROAD SEQUEeCE TEST OV CI3 This test was performed to cotlect dets for DwE to evetuate dieset this test is described in the isAR, Section 8.3, R.G.1.9 and 1.128. The generator 2A-A worst-case toeding sequence. test did not irwolve a change in the plant facility or plant operating characteristics from that described in the f54R. the test did not invetwo new procedures or instructions thet are different frem the prece 6res as described in the FSAR or plant T.S. The test was perfomed without a change to the plant T.S.
** Sil 78 D/G 25-5 L0a0 SEQUENCE TEST aEW 000 This test was performed to collect date for DuE to evetuate generator 28-8 This test is described in the FSAR, section 8.3, R.G.1.19 and 1.108. The worst-case toeding sequence, test did not inwotwe a change in the plant facility or plant operating characteristics from that described in the f54R. The test did not invetwe new procochares or instructions that are different from the proce&res es described in the FSAR or plant T.S. The test was performed without a change to the plant T.S. '
STI-79 PLANT CONTROL SYSTEN IWit# LOCKS - IND STOPS i DEO 000 This STI functionetty vetidoted proper operation of each plant control Rod stops were provided to prevent abnomet pouer conditlens dich could system interlock defined in the test instruction es it pertained to result from encessive control rod withdramet initiated by either e control blockage of automatic menuet controt red withdrawat. system malfwiction or operator action. The test is described in Section 7.7 of the PSAR. The test did not involve a change to the f acility - i or ' plant operating characteristics f rom that described in the f 5AR. The test, did not involve new procedures or instructions that are different from the procedures as described in the f 5AR or plant T.S. The test mes gweformed uithout a change to T.5. 3.3.1. e
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Page me. 17 02/22/88 SEQUOYAN NUCLEAR PLAuf 10 CFR 50.59 1987 het A44UAL OPERATING REPORT SPECIAL TESTS PERFORMED IN 1967 DESCRIPT104 SAPETY ANALYSIS g
" S11-80 WONDESTRUCTIVE TE5fl#G Of IN-PLACE ComCRETE PER ASTM STA@ARD C803 ST htC DEV 000 This test esas performed on in-place concrete at various locations This test i es performed by met persomet or mRC contractors. Att throughout the EaCW samping station and the crane went to determine the aspticable radiological and safety procedures escre adhered to during the compressine strength of the concrete. performance of the test. The use of emptosive cartridges was in conq>tiance with MCI-M21. The test eens performed in accordance with ASIM Standard C803 and esRC mDE-16. The probe depth did riot enceed 1.6 inches, and tenere esos rio ef fect on entsedded conduit or pipe. The T.S. does not address testing of concrete structures; thus, the mergin of safety, as defined In the beels of the T.S., was eneffected. ** STI-81 N2 ANALYZER VALVES 2A AND 28 FAIL-SAFE POSITION TEST - UNIT 2 RE7 000 This test verified that the hydrogen anatyrer contaivuurnt isolation vatwes This test is described in table 14.1-t-1 of the tsar. The test did not 2-f CV-43-201 A, -202- A, -207-5, and -208-5 f ait OPEN on the 104s of control involve a change in the facility or plant operating characteristics from air and fait CLOSED on the toss of electricot power. that described in the FSAR. The test did not inwotwe new proceesres or instructions that are different from the procedures as described in the FSAR or plant T.S. This test did not inwotwe a T.S. Item regsired for mode 5. ** STI-82 MAeUAL OPERAfl04 AND STROKF TIMs2G OF CCS VALVES AND AUTOMATIC OPERAf tos OF THE Unif 2 TMERMAL 3ARRIER 900 STER PUMPS - UNITS 1 and 2 RUJ 000 This test verified the manual operation of four CCS vatwes, the strcAe tinue This test is described in the FSAR, Chapter 14, table 14.1-1, pages 92 and
- 93. The test did not involve a change in the facility or plant operating of four CCS watwes, and the automatic operation of the unit 2 therwiat berrier booster peps. characteristics from that described in the f 5AR. The test did not inwotwe new proced. ares or instructions that are dif feren". from the procedJres es described in the f 5AR or plant T.S. The test was performed without a change to T.S. 3/4.7.3.
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NUMBER OF PERSONNEL AND MAI6-REM BY WORK AND JOB FUNCTION SEQUOYAII NUCLEAR PLANT 1987 l GROUJ STATION l UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL EMPLOYEES ' EMPIDYEES & OTilERS PERSONS EMPLOYEES EMPLOYEES & OTIIERS M-REMS MAINTENANCE PERSONNEL 2022 20 13 2055 216.745 0.819 1.116 218.680 OPERATING PERSONNEL 118 11 6 135 11.286 0.251 2.861 14.398 IIEALTI: P!IYSICS PERSONPEL 235 47 0 282 40.730 3.662 0.000 44.392 SUPERVISORY PERSONNEL g 37 1 3 41 3 2.536 0.220 0.565 _ 3.321 ENGINEERING PEMsONNEL 261 75 415 751 16.471 11.559 91.802 119.832l 2673 154 437 3264 287.768 16.511 96.344 400.623
~
NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION SEQUOYAll NUCLEAR PLANT 1987 TOTAL NUMBER OF INDIVIDUALS GROUP STATION UTILITY . CON
- PACT TOTAL EMPLOYEES EMPIOYEES 'AND OTI!ERS- PERSONS MAINTENANCE PERSONFEL 706 9 5 720
~~
OPERATING PERSONNEL 8 1 e 15 IIEALTII PIIYSICS PERSONNEL 52' 5 , .0 57 SUPERVISORY PERSONNEL 7 1 2 10 .. ENGINEERING PERSONNEL 65 194 13h 272 TOTK 838 - 2 - 207 1074 g +, t,c" "- 4 1 __. ____a _ -.m .. _ c 4 3 _ , _ __ _ _ _ _ _ _ _ _ _
SEQUOYAll ??UCLEAR PLANT NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION 1.987 M0= REACTOR OPS SURVEILLANCE NUMBER OF PERSONT-EL (>100 "-REM) TOTAL MAN-REM GROUP STATidN UTILITY i CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL PERSONS EMPLOYEES EMPLOYEES & OTHERS M-REMS EMPLOYEE}':MPLOYEESl & OTIIERS MAINTENANCE PERSONNEL Sh3 5 4 Sa2 19.386 0.063 0.045 19.494 OPERATING PEPl.;ONNEL 55 9' O 64 i 5.644 0.241 0.000 5.887 HEALTl! PHYSICS PERSONNEL 57 15 0 72 3?.023 '.. 933 i 0.000 15'.936 SUPERVISORY PERSONNEL 12 0 0 12 1.102 0.000 0 . O rc0 ' 1.102 ENGINEERING PERSONNEL 87 16 110 213 3.128 ! 0.642 5.800 9.570 MO 794 45 114 953 42.283 3.881 5.845 52.009 M0= ROUTINE MAINTENAW 3 GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL EMPLOYEES EMPLOYEES & OTHERS PERSONS EMPLOYEES EMPLOYEES & OTHERS M-REMS MAINTENANCE PERSONNEL 637 7 3 647 69.521 0.321 0.230 70.072 OPERATING PERSONNEL 33 1 0 34 0.386 0.002 0.000 0.388 HEALTH PHYSICS PERSONNEL 61 15 0 76 4.294 0.555 0.000 4.849 SUPERVISORY PERSONNEL 11 0 1 12 0.189 0.000 0.000 0.189 ENGINEERING PERSONNEL 77 21 85 183 2.222 0.199 1.687 4.108 MO 819 44 89 952 76.612 1.077 1.917 79.606 SOURCE DOCUMENT: RIMS S58 880129 876
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M0=IN-SERVICE INSPECTION GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL EMPLOYEES EMPLOYEES & OTIIERS PERSONS , EMPLOYEES EMPLOYEES & OTHERS M-REMS MAINTENANCE PERSONNEL 94 0 1 95 23.833 0.000 0.072 23.905 OPERATING PERSONNEL 2 0 0 2 0.072 0.000 0.000 0.072 HEALTH PIIYSICS PERSONNEL 38 8 0 46 19.691 0.061 0.000 19.752 SUPERVISORY PERSONNEL 6 1 2 9 1.003 0.220 0.565 1.788 ENGINEERING PERSONNEL 19 11 57 87 1.614 8.661 48.604 58.879 MO 159 20 60 239 46.213 8.942 49.241 104.396 M0=SPECIAL MAINTENANCE GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CCNTRACT TOTAL EMPLOYEES EMPLOYEES & OTHERS PERSONS EMPLOYEES EMPLOYEES & OTHERS M-REMS MAINTENANCE PERSONNEL 596 8 5j 609 101.780 0.435 0.769 102.984 OPERATING PERSONNEL 23 1 0 24 0.136 0,006 0.000 0.142 IIEALTil PIIYSICS PEnSONNEL 49 8 0 57 2.506 0.109 0.000 2.715 SUPERVISORY PERSONNEL 4 0 0 4 0.031 0.000 0.000 0.031 ENGINEERING PERSONNEL 75 27 162 264 9.507 2.057 35.711 47.275 MO 747 44 167 958 114.060 2.607 36.480 153.147 M0= WASTE PROCESSING GROUP STATION UTILITY CONTRACT & TOTAL STATION UTILITY CONTRACT & TOTAL EMPLOYEES EMPLOYEES OTIIERS PERSONS EMPT,0YEES EMPLOYEES OTHERS M-REMS MAINTENANCE PERSONNEL 112 0 0 112 , 2.225 0.000 0.000 2.225 OPERATING PERSONNEL 5 0 6 11 5.048 0.000 2.861 7.909 HEALTH PHYSICS PERSONNEL 30 1 0 31 1.116 0.004 0.000 1.120 SUPERVISORY PERSONNEL 4 0 0 4 0.211 0. COO 0.000 0.211 ENGINEERING PERSONNEL 3 0 1 4 0.000 0.000 0.000 0.000 MO 154 1 7 162 8.600 0.004 2.861 11.465
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U.S. Nuclear Regulatory Commission lA#dl 011988 MRH:MJB:DMM cc (Enclosure): Mr. K. P. Barr, Acting Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. C. C. Zech, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission one White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road ,, Soddy Daisy, Tennessee 37379 RIMS, MR AN 72A-C H. L. Abercrombie, O&PS-4, Sequoyah C. E. Ayers, LP 6N 25D-C J. R. Bynum, LP 6N 38A-C E. S. Christenbury, E11 B33 C-K W. H. Hannum, BR IN 77B-C M. R. Harding, O&PS-4, Sequoyah N. C. Kazanas, LP AN ASA-C J. A. Kirkebo, W12 A12 C-K C. R. Mullee, BR SS 168A-C
)
D. R. Nichols, BR SS 100A-C P. J. Polk, Rockville Licensing Office I M. J. Ray, LP SN 105B-C C. L. Rogers, LP 6N 38A-r. S. J. Smith, POB-2, Sequoyah D. L. Williams, W10 B85 C-K l I l i l
144 880301 805 SN 157B Lookout Place - h4 air 011988 10 CFR 50.59 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 centlemen: In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - 1987 ANNUAL OPERATING REPORT Enclosed is the 1987 Annual Operating Report for SQN. It contains a summary of the following items: emergency core cooling system outages, primary system safety or relief valve actuations, facility changes, procedure changes, and occupational exposure data. This report is being submitted to satisty the requirements of 10 CFR Part 50.59 and technical specifications 6.9.1.4, 6.9.1.5, and 6.15.1. If you have any questions, please telephone M. J. Burzynski at (615) 870-6172. Very truly yours, TENNESSEE VALLEY AUTHORITY Odginal Signed By R, L. Oridley R. Gridley, Director Nuclear Licensing and Regulatory Affairs Enclosure cc: see page 2 , l
l l . TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER ' SEQUOYAH NUCLEAR PLANT (UNITS 1 AND 2) l 10 CFR 50.59 l ANNUAL OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION i I- l I ' '
/ /
JANUARY 1,1987 - DECEMBER 31, 1987 l DOCKET NUMBER 50-327 and 50-328 LICENSE NUMBER DPR-77 and DPR-79 y, y.,--.- ,_ _,-,--,,r-- ---y .,v , , - -- ,,w--w, -
SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT TAA_H.L_5 OF CONTENTS Preface - Acronym List I. Summary of Emergency Core Cooling System Outages l' II. Summary of Primary System Relief or Safety Valve 1 Actuation III. Summary of Facility Changes Modifications 2 Temporary Alterations 11 IV. Summary of Procedure Changes Abnormal Operating Instructions 13 Emergency instructions , 24 Surveillance Instructions 26 Special Test Instructions 107 V. Summary of Special Tests 122 VI. Occupational Exposure Data 139 h
SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 NRC ANNUAL OPERATING REPORT 1987 The following criteria establish the bases for the' items. contained in this report. I. Facility Changes A. Modifications The ECN Closure Group reports to Site. Licensing the ECNs that have been closed for_ inclusion in the annual FSAR update. The same ECNs are reported in the annual operating report. Since the ECN Closure Group reports totally closed ECNs, and field complete ECNs were reported in previous annual operating reports, a cross-check was performed. Only the ECNs'not previously reported are included in this report. B. Temporary Alterations Temporary alterations to the facility are reported based on how long the alteration has been in existence. Using the same criteria used for the FSAR update, an alteration will be reported if it has been,-or is expected to.be, in existence for greater than one year. A temporary alteration is documented on a TACF. , Previously reported alterations still in existence are listed by their TACF number only. New alterations meeting the above criteria are described and a safety summary provided. II. Procedures Technical specification surveillance instructions, abnormal operating instructions, and emergency instructions have been determined to be as "described in the FSAR." Changes to these procedures are reported if they satisfied one or more of the following criteria: A. Procedure Changes Before May 20, 1987
- 1. Made a significant change to the scope, technique, or sequential order of steps affecting results or nuclear safety.
- 2. Waived or violated technical specification or licensing requirements.
- 3. Affected a quality control hold point.
- 4. Changed or revised the review / approval authority or responsibility.
- 5. Implemented a temporary alteration to operate CSSC equipnent.
- 6. Changed the acceptance criteria.
)
A summary of the safety evaluation for each procedure i change reported is included. B. Procedure Changes'After May 20, 1987 A USQD was. required for all procedure changes; prior to May 20, 1987. SQA-119 was revised on May 20,~1987, requiring a "screening' review" be performed to provide a record of review for changes to instructions, procedures, the radwaste system or facility, or test _and experiments proposed to be considered at SQN._ If the screening review determined a USQD was not required, the procedure is not reported. l
)
l l
THE FOLLOWING IS A LIST OF ACRONYMS COMMON TO THIS REPORT. ACRONYM DEFINITION ABGTS AUXILIARY BUILDING GAS TREATMENT SYSTEM AC ALTERNATING CURRENT ACA AUXILIARY CONTROL AIR AFW AUXILIARY FEEDWATER AHU AIR HANDLING UNIT AI ADMINISTRATIVE INSTRUCTION ANSI AMERICAN NATIONAL STANDARDS INSTITUTE AOI ABNORMAL OPERATING INSTRUCTION ASME AMERICAN SO;:IETY OF MECHANICAL ENGINEERS ASTM AMERICAN SOCIETY FOR TESTING AND MATERIALS ATWS ATTEMPTED TRIP WITHOUT A SCRAM AUX AUXILIARY AWG - AMERICAN WIRE GAUGE A/C AIR CONDITIONING . BIT BORON INJECTION TANK CAM CONTINUOUS AIR MONITOR CAQR CONDITION ADVERSE TO QUALITY REPORT CATS COMMITMENT ACTION TRACKING SYSTEM CCP CENTRIFUGAL CHARGING PUMP CCS COMPONENT COOLING SYSTEM CCW COMPONENT COOLING WATER CEB CIVIL ENGINEERING BRANCH CEB CIVIL ENGINEERING BRANCH CFM CUBIC FEET PER MINUTE CFR CODE OF FEDERAL REGULATIONS CP CRANKCASE PRESSURE CPM COUNTS PER MINUTE CRDM CONTROL ROD DRIVE MECHANISM CRI CONTROL ROOM ISOLATION CRVI CONTROL ROOM VENTILATION ISOLATION CSP CONTAINMENT SPRAY PUMP CSS CONTAINMENT SPRAY SYSTEM CSSC CRITICAL SYSTEMS, STRUCTURES, AND COMPONENTS CV CHECK VALVE CVCS CHEMICAL VOLUME CONTROL SYSTEM D/G DIESEL GENERATOR DC DIRECT CURRENT DCR DESIGN CHANGE REQUEST DNE DIVISION OF NUCLEAR ENGINEERING DPM DIVISION PROCEDURE MANUALS DPSO DIVISION OF POWER SYSTEM OPERATIONS ECCS EMERGENCY CORE COOLING SYSTEM ECN ENGINEERING CHANGE NOTICE EGTS EMERGENCY CAS TREATMENT SYSTEM el ELEVATION EMSL ELECTRICAL MAINTENANCE SECTION LETTER EOI EMERGENCY OPERATING INSTRUCTION EQ ENVIRONMENTAL QUALIFICATION EQIS EQUIPMENT INFORMATION SYSTEM 9
ERCW ESSENTIAL RAW COOLING WATER ESF ENGINEERED SAFETY FEATURE FCR FIELD CHANGE REQUEST FCV FLOW CONTROL VALVE FQE FIELD QUALITY ENGINEERING FSAR FINAL SAFETY ANALYSIS REPORT FW FEEDWATER HCI HAZARD CONTROL INSTRUCTION HJWT HIGH JACKET WATER TEMPERATURE HVAC HEATING, VENTILATION, AND AIR CONDITIONING ICF INSTRUCTION CHANGE FORM IMI INSTRUMENT MAINTENANCE INSTRUCTION I/P CURRENT TO PNEUMATIC kW KILOWATT LCO LIMITING CONDITION OF OPERATION LER LICENSEE EVENT REPORT LLRW LOW LEVEL RAD WASTE LOP LUBE OIL PRESSURE MA MILLIAMPERE MCC - MOTOR CONTROL CENTER MFIVs MAIN FEEDWATER ISOLATION VALVES HFW MAIN FEEDWATER MPC MAXIMUM PERMISSIBLE CONCENTRATION MS MAIN STEAM MSIV MAIN STEAM ISOLATION VALVE MVAR MILLIVOLT AMPERES REACTIVE M&TE MEASURING & TEST EQUIPMENT NBS NATIONAL BUREAU OF STANDARDS NCR NONCONFORMANCE REPORT NDE NONDESTRUCTIVE EXAMINATION NEB NUCLEAR ENGINEERING BRANCH NQAM NUCLEAR QUALITY ASSURANCE MANUAL NRC NUCLEAR REGULATORY COMMISSION PD POSITIVE DISPLACEMENT PM PREVENTATIVE MAINTENANCE PMP PREVENTATIVE MAINTENANCE PROGRAM PORV POWER OPERATED RELIEF VALVE l PRO POTENTIAL REPORTABLE OCCURRENCE I psi POUNDS PER SQUARE INCH psia POUNDS PER SQUARE INCH ABSOLUTE { 1 psid POUNDS PER SQUARE INCH DIFFERENTIAL l psig POUNDS PER SQUARE INCH GAUGE PT { PRESSURE TRANSMITTER 1 QA QUALITY ASSURANCE QC QUALITY CONTROL l QE&C QUALITY ENGINEERING & CONTROL i QMDS QUALIFICATION MAINTENANCE DATA SHEET RCP REACTOR COOLANT PUMP RCS REACTOR COOLANT SYSTEM i RCW RAW COOLING WATER ! REV REVISION l RHR RESIDUAL HEAT REMOVAL RPI ROD POSITION INDICATOR RSW RAW SERVICE WATER j RTD RESISTIVE THERMAL DETECTOR ' RTV ROOM TREATED VULCANIZATION I 1
RX REACTOR R.G. REGULATORY GUIDE SAR SAFETY ANALYSIS REPORT SCF STANDARD CUBIC FEET SCFH STANDARD CUBIC FEET PER HOUR SCR SIGNIFICANT CONDITION REPORT SE SHIFT ENGINEER SI SURVEILLANCE INSTRUCTION SI SAFETY INJECTION SIS SAFETY INJECTION SYSTEM - SNM SPECIAL NUCLEAR MATERIAL SOI STANDARD OPERATING INSTRUCTION SP STANDARD PRESSURE SPDS SAFETY PARAMETER DISPLAY SYSTEM SPTS SEQUOYAH PROCEDURES TRACKING SYSTEM SQA SEQUOYAH ADMINISTRATIVE INSTRUCTION SR SURVEILLANCE REQUIREMENT SRO SENIOR REACTOR OPERATOR SSPS SOLID STATE PROTECTION SYSTEM STI - SPECIAL TEST INSTRUCTION TACF TEMPORARY ALTERATION CONTROL FORM TAVG AVERAGE TEMPERATURE TI TECHNICAL INSTRUCTION TSC TECHNICAL SUPPORT CENTER T.S. TECHNICAL SPECIFICATION (S) UHI UPPER HEAD INJECTION " UO UNIT OPERATOR USQ UNREVIEWED SAFETY QUESTION USQD- UNREVIEWED SAFETY QUESTION DETERMINATION V VOLT VCT VOLUME CONTROL TANK WC WATER COLUMN WGDT WASTE GAS DECAY TANK WP WORK PLAN ,
'l L l l - O O l 0 SJMMARY OF O l 0 EMERGENCY CORE O O COO.=.ING SYSEM O 1 and O PRIMARY SYS-'EM O l O RE lE F or S A FE-'Y O .
- O VA VE o l O O 4
i I
SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANflUAL OPERATING REPORT I.
SUMMARY
OF EMERGENCY CORE COOLING SYSTEM (ECCS) OUTAGES No ECCS system was declared inoperable while in an applicable mode of operation in 1987. Both units were in mode 5 the. entire year. II. PRIMARY SYSTEM RELIEF or SAFETY VALVE ACTUATION There were no challenges to the primary system relief or safety valves in 1987. I e 9
4 i O O O O O SJMMARY OF O O FACl_OY. O CHANGES O O O MODIFIC A- lONS O
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O O O O
Page No. 1 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1967 NRC ANNUAL OPERATING REPORT CHANGES IN THE FACILITY - MODIFICATIONS DESCRIPTION SAFETY ANALYS!$
" Ec] - L5247 DCR 0535 This modification replaced the volume control tank level controller The proportional only controller allows the divert valve to be operated (1-1C-62-129A) from a proportional plus reset plus derivative to a manualty. If the controtter fails, no safety hazard would be involved and proportional control only. the tevel in the volune control tank is still effectively controlled. The probabitity of an occurrence or consequences of an accident or matfunction were not increased, and the possibility for en accident of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
" ECN - L5314 DCO 0861 This modification retocated the pressure switches PS-3-1408 and PS-3-1508 This modification did not change the equipment being used; it only changed from the west steam valve room to the auxiliary building. This change was the location of the equipment. The pressure switches were moved from a made to tocate the switches in an area of lower temperature. Each of these high energy zone to a low energy zone not subject to a pipe break. The pressure switches serves as one of two pressure switches which will isolate hardware was reinstatted per the same seismic and electrical operation flow f rom the turbine driven auxiliary feedwater pump to the associated criteria. The probability of an occurrence or the consequences of an steam generator on detecting low pressure. accident or malfunction were not increased, and the possibility for an accident of a different type was not created. These instruments are not addressed by, and do not affect, the basis for the T.S. Therefore, the T.S. margin of safety was not redJced.
" ECW - L5353 DCR 0914 This modification disconnected handswitches 1-HS-1-158, -168, -178, -188, The switches are still installed but are conpletely disconnected from the 1-HS-3-338, -478, -878, -1008,1-NS-72-408 and -418 which are not circuits and labeled "spare." These switches were installed for component docunented as envirorsnentally qualified. These switches were used for te's ting only and had no function in accident mitigation. The probability maintenance and local testing of valves in the main steam feedwate. and of an occurrence or the consequences of an accident or malfmetion were not containment spray systec3. increased, and the possibility for an accident of a different type was not created. The margin of safety, as defined in the basis'of any T.S., was
s 9ege No. 2 02/22/88 SEQUOYAM NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL (PERATING REPORT CHANGES IN THE FACILITY - MODIFICATIONS DESCRIPTION SAFETY ANALYSIS i not reduced.
- ECW - L5433 DCR 0424 This modification instatted a wire cage around the hatch at the entrance to This modification was to non-CSSC equipment and did not directly or the incore instrumentation penetration room f rom inside contairment. Ttis indirectly af fect nuclear safety. The probability of an occurrence or the modification was necessary to prevent unauthorized personnel entrance which consequences of an accident or malfunction were not increased, and the may result in overexposures. The existing hatch cover was modified for possibility for en accident of a different type was not created. The operation by one person. The wire cage access door is key operated from margin of safety, as defined in the basis of any T.S., was not redaced.
the outside only.
- ECM - L5499 LCR 0741 This modification provided new logic and new wiring of the SON HVAC system This modification did not change or effect the function of any (system 30) which causes the auxiliary building general supply fans, safety-related equipment. The auxiliary building supply and exhaust fans auxiliary building exhaust fans, and the fuel handling area exhaust fans to are non-divisional power stpplied and electrical safe separation criteria stop toon initiation of an auxitlery buildire train A or train 8 isolation have been met. This electricat modification allows the subject fans to signal. stop automaticatty upon an auxiliary building isolation signal. This decreases the potential for en offsite radiation event. The probability of an occurrence or the consequences of an accident previously evaluated were not increased, and the possibility for en accident of a different type was not created. The operation or operational modes for the auxiliary building supply and exhaust fans are not covered in the T.S. :This change reckJees the potential for an offsite radiation event and enhances the marDi n of safety as defined in the basis of the T.S.
- ECM - L5519 DCR 0738 This modification installed a Rescumatic emergency escape device in the cab The function of the self-rescue device is not nuclear safety related, nor' equipped overhead cranes in the reactor buildings, the auxiliary building does it affect' nuclear safety-related equipment. This device is for plant
. . ._.= - . - _ _ - . .
s Page Ko. 3 02/22/88 SCQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL CPERATING REPORT CMANCES IN THE FACILITY - MODIFICATIONS DESCRIPTION SATETY ANALYSIS I and the turbine building. This device is a sraatt package which is stored personnel safety only. The probability of an occurrence or the in the crane cab. consequences of an accident or malfunction of equipment were not increased, and the possibility for an accident of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
- ECM - L5575 DCR 0972 This modification replaced timit switches for FCO-30-87, FCo-30-107 The new equipment meets or exceeds the quintifications of the original FCO-30-22, and FCo-30-109 on HVAC (system 30) with switches that are equipment. All of the original seismic design requirements are met. The envirorwentatty quellfied in accordance with the guidelines of NUREG 0538. prcbability of an occurrence or the consequences of an accident or malfuction were not increased. The possibility for an accident or malfunction of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
- ECM - L5587 DCR 1159 This change revised the isometric drawings t3 reflect the new analysis This change was for docunentation only, and no physical work was done. No based on the east valve room seismic spectra, plant safety function or feature was chang =d or degraded. Th'e probability of an occurrence or the consequences of an occident or malfunction were not increased, and the possibility for en accident of a different type was not created. The margin of saf ety, as defined in the basis of any T.S., was not reduced.
** ECM - L5624 DCR 1185 This modification changed drawing 47W846-2 to show valve 1-33-704 normatty This was a drawing correction, and no USo was in%tved.
closed per SQ-DCR-1185. The vatve function was shown incorrectly on the i drawing.
. _ _ _ - m _ _ _ _ _
Page no. 4 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CMANCES IN THE FACILITY - MODIFICATIONS DESCRIPTION SAFETY ANALYSIS . .
? ** ECn - L5651 DCR 1170 This modification added to the logic of valves FCV-67-176 and FCV-6-182 an The SIS pum and room cooter are used only for accident mitigation. Adding "or* gate so the valves will open on a $15 ptsp start signal as well as the this logic to the cooling water valve did not increase the probability cf cooting fan motor start signal. This change ensured that coolirsg water to en occurr?nce or the consequences of an accident or malftsiction. The the SIS pt.cp oil cooter is available anytime the fis ptsp is operating. possibility for an accident of a different type was not created. The T.S.
The SIS pump oit .ooter is in parattet with the AMU cooter. states that cooling water must be avaltable to these cooters. This change ensures the mergin of safety is maintained.
** ECW - L5702 ~
DCR 1358 Thismodificationinstattedanadditionstvalvei63-697)downstreamof The new valve is operable by hand only and does not interface with 1E valve 63-564 on the SIS (system 63). talve 63-564 teeked and was egJipment or power supply. It has been seismically evelaasted to show that inaccessible for making repairs. The inaccessibility of valve 63-564 made it is property supported for its location in a category I structure and in repair costs prohibitive. TVA class 8 piping. The probability of an occurrence or the consequences of an accident or malfunction of equipment were not increased, and the 4 possibility for an actident of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
** ECM - L5715 DCR 1297 This modification replaced the plastic cushings in the CRDM cooling suction The brass bushings perform the same flanctions ss the plastic' bushings, and danpers 2-TCO-30-81 84, -89, and -93 with brass bushings. The plastic the operation of the danpers is not degraded. The dampers are still bushings wear out in a short period of time. seismically qualified with the brass bushings. The probability of an occurrence or the consequences of an accident or metitsiction were ret iracased, and the pnsibility for en accident of a dif ferent t,Te aos not.
crt::t-1 the margin of safety, as defined in the basis of arvy T.S., was not reduced. r
Page No. 5 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPQ'tT CHANCES IN THE FACILITY - MODIFICAi!ONS s DESCRIPTION SAFETY ANALYSIS
} ** E0J - L5974 DCR 1077 This modification was made to relocate the main feed pimp turbine vibration This modification did not degrade the logic, control, or ftmetion of the recorder sequencer / selector switch from the back side of panel M-3 to a feedwater control system or other features required to perform nuclear spare location on the front side of panel M-3. This attows the operator to safety functions. This did not invalidate compliance to existing seismic conveniently monitor the indLviduat 'fibration channets for specific and QA requirements. The probability of an occurrence or the consequences information needed during high vibration alarm conditions without having to of an accident or malfunction were not increased, and the possibility for go tehind the panel. an accident of a type different than that previously evaluated was not created. The margin of safety, as defined in the basis of any T.S., was
, not reduced.
** ECM - L6122 DCR 2271 This modification voided spring stoports H10-696, M10-616, and The spring supports were originally instatted to prevent Large toeding on 47A-464-3-135 on the CCW. the nozzels downstream of the supports. CEB analysis showed that removal of the spring supports did not invalidate the seismic qualification of the piping. Since there was no change in the function or operability of the piping, the probability of an occurrence or the conaequences of an accident
~
or malfunction of equipment were not increased. The possibility for an accident or malfunction of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced. 9
** ECM - L6175 --
~ '
DCR 2478 This modification was made ko reduce the setpoints for FS-32 62 and Reducing the setpoint to 80 psig did not affect the system's ability to PS-62-88 from 84 psig to 80 psig. The change was needed due to the control provide 70 psig to the air header for equipment which uses air supplied by air <;ospressors operating excessively. ~ th'is system. Att equipment which uses air is purchased to operate on a minimum of 70 psig. The probability of an occurrence or the consequences of an occident or malfunction were not increased, and the possibility for an accident or malfunction of a dif ferent type was not created. The. k k
Page No. 6 02/22/88 SEQUOYAH FILEAR PLANT 10 CF2 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES IN THE FACILITY - MODIFICATIONS s DESCRIPTION SAFETY ANALYSIS , i essential control air system is not specifically defined in the basis of the T.S. However, the control air affects the basis by its requirement to make valves and systems available. Since this change did not affect the 4 system's ability'to provide this function, the margin of safety was not reduced.
" ECm - L7092 DCR 2259 This modification was made to seal att spare mechanical sleeves in the The seating of the reactor building shield well penetrations below et 724 i shletd building well @ to et 724.0. This was done to maintain the sealing will preclude water seepage in the event of site flooding. The changes did integrity as required by FSAR, Section 6.2. The sleeves were capped and not degrade the fire rating of the shield watt, and the cover plates welded seat welded to prevent floockater entering the annulus. - on the penetrations did not degrade the seismic design of the shield building watt or the mechanical penetrations. The probability of an occurrence or the consequences of an accident or malftmetion were r.ot increased, and the possibility for en accident of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced. " ECN - L7096 DCR 1791 This modification installed temperature thermocouples in the radiochemical This was done to ensure steam cycle samples are within the proper laboratory titration room on each sampting cooling colt outlet. This also tenperature range. FSAR, Section 10.3.5, describes secondary side water installed tenperature selectors and indicators on the titration panel and chemistry but does not describe sampling techniques or instrumentation.
connected them to thermocouples. This change enhances the sanpling techniques and will ensurd compliance with the water chemistry guidelines referred to in Section 10.3.5 of the FSAR. 1
" EC3
- L7105 OCR 2259 This modification abandoned the nunber 16 AWG TSQ teads in penetration Changing the cable from one lead to another within the same penetration
s Pege No. 7 02/22/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NCC ANNUAL OPERATING REPORT CHANCES IN THE FACILITY - M001FICATIONS CESCRIPTION SAFETY ANALYSIS . f . nureers 19, 38, 45, and 49. The cables were reterminated to number 16 AWG does not affect system operability or seismic analysis. The probability pf TSP teads in the same penetrations. The green leads of the T50 cables had an occurrence or the consequences of an accident were not increased, and deformed insulation causing concern as to idiether they meet EQ the possibility for an accident of a different type was not created. The requirements. By changing to the TSP cables, there is no problem in modifications to these electrical penetrations were not directly addressed meeting Eo requirements, and att 1E requirements are met. in the T.S. T.S. 3/4.8.3 (overcurrent protective devices) was not affected. The margin of safety remained unattered.
- ECM - LT137 DCR 2293 Performed physical modifications to various pipe supports to qualify the The modification on various pipe supports was performed to make sure the supports for the design basis events as required by the applicable design pipe supports were qualified both envirormentatty and seismically per criteria. These modifications were performed on the fullowing systems: applicable design criteria. The safety furetion of the associated CVCS, AFW, SIS, RCS, and MS. mechanical systems uas not jeopardized. Since the systems are more reliable, the probability of an occurrence or the consequences of an accident or malfunction of equipment laportant .to safety are reduced. Each modification was supported by an indivi&at calculation,' and the offects on miscettencous structures were considered. The margin of safety, as defined in the basis of any T.S., was not reduced.
- ECM - L7147 DC2 2293 Performed physicat modifications to various pipe sw ports to qualify the The modification on various pipe s @ ports was performed to make sure the supports for the t'esign basit events as required by applicable design pipe supports were qualified both envirorimentally and seismically per .
criteria. These modifications wese performed on the fottowing systems: applicable design criteria. The safety function of the associated CCS, CSS, and R W , mechanical systems was not jeopardized. Since the systems are more reliable, the probability of an occurrence or the consequences of an accident or matfunction of equipment inportant to safety are redJced. Each modification was s@ ported by an individual calculation, and the effects on miscellaneous structures were considered. The margin of safety, as defined in the basis of any T.S., was not reduced.
s Page No. 8 02/22/88 SEQUOYAN NUCLEAR FLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES IN THE FACILITY - MODIFICAi!ONS DESCRIPTION SAFEIY ANALYSIS ,
** ECD - L7157 DCE 2259 This modification replaced the non-qualified AFW discharge pressure gauges Replacing these gauges with seismically qualified gauges ensures the with qualified seismic 1 (L) pressure gauges. The pressure gauges involved pressure boundary integrity of the section of the AFW system where these in the change were 2-PI-3-1228 and 2-PI-3-1328. gauges are connected. The pressure gauges are only used for tocal pressure indication of the AFW punps discharge. The probability of an occurrence or th'e consequences of an accident or malfuction of equipment were not increased, and the possibility for an accident of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced. ** ECW - L7160 DCE 2259 This modification was made to the control Logic and circuit wiring of the This modification did not affect the design requirements of the shutdown auxiliary building ventitation and cooting system to eliminate the board room chitters, but ensures their cont nued operability should the 8
automatic stancby start function of the shutdown board room water chit ter circuit located in the control building fall. This functional change to package S-B when it is in the backtp control mode and isolates att wiring the chitter packages did not invalidate any system design requirements as routed to the control building when switches XS-31C-303 and MS-31C-338 are identified in SON-DC-V-13.9.3 and FSAR, Section 9.4.2.2 4 "Shutdown Board in the AUX position. Room Air Conditioning Systems." T.S. 3.4.8 requires these chitters to be operable. This modification ensured the continued op ration of these chillers, and ro margin of safety was reduced.
** ECJ - L7223 DCR 2259 This modification deleted the tenperature modulating feature from the lower Deleting the tenperature modulating feature from the tower conpartment compartment cooters. This modification was required for the upgrade of the cooters will maintain adequate flow to the cooters without significantly coolers to safety grade, because ternperature control valves 2-tCV-67, -84, reducing flow to other safety-related equipment. The probabit:ty of an
-92, -100, and -108 are not environmentatty quatified. The valves have had occurrence or the consequences of an accident or malfunction of equipment power, controtters, and air lines disconnected to keep the valves in the were not increased, and the possibility for an accidant uf a different type-
_9_ A _ _ - __ - _ _ .M
Page No. 9 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 hRC ANNUAL OPERATING REPORT CHANGES IN THE FACILITY - MODIFICATIONS OESCRIPTION SAFETY ANALTSIS fully OPEN position. They will maintain this position with the air supply was not created. The margin of safety, as defined in the basis of any removed. T.S., was not reduced.
- ECM - L7228 DCR This modification added or revised supports on ducting for tht- tower This modification qualified and upgraded the duct supports for the lower compartment cooling system (system 30). compartnerit cooters to meet seismic Category I regairements. No safety-related system, component, or structure was adversely affected by this modification. The probability of an occurrence or the conse p es of an accident or malfunction were not increased, and the possibility for an accident of a different type was not created. The margin of safety, as ,
defined in the basis of any T.S., was not reduced.
- ECN - L723T DCR 2259 The modification replaced vital battery rooms I, II, III, and IV exhaust The new exhaust fans are seismicatty quotified and seismically supported.
fans with Class 1E qualified fans. The new fans do not create extra electrical loads and do not effect cable ampacity. The probability of an occurrence or t'ne consequences of an accident or malfunction were not increased, and the possibility for an accident of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced. t
l I i - 1 i O O O O S.MMARY O F. l O F A C l _l-' Y O l j O CHANGES O O O i O
EMPORARY O ~ A_ ERA"lONS
, O O l O O 1
s OPEN TACFs PREVIOUSLY REPORTED
============================================================___ =======================================
C-79+3633-079 0-82-0340-410 0-85-0077-039 1-82-0168-062 1-84-0057-085 2-80-0537-090 2-83-2036-062 0-80-00d8-012 0-83-0347-057 0-85-0079-317 1-82-0213-062 1-84-0065-050 2-81-2298-014 2-83-2047-062
- 0-80-0089-012 0-83-0349-077 0-85-0090-234 1-82-0214-062 1-84-0081-062 2-81-2341-087 2-83-5057-068 l 0-81-0297-014 0-83-0366-245 0-86-0005-079 1-82-0240-079 1-84-0107-003 2-81-2342-087 2-84-2004-062 0-81-0328-077 0-83-0375-030 0-86-0019-317 1-82-0242-062 1-85-0063-094 2-81-2343-087 2-84-2008-013 C-81-0429-031 0-83-0400-030 1-80-0152-079 1-82-0266-077 1-85-0064-046 2-81-2344-087 2-84-2016-062 0-81-0458-067 0-83-0411-241 1-80-0576-062 1-82-0339-006 1-85-0066-025 2-81-2564-001 2-84-2039-003 0-81-0465-027 0-84-0007-031 1-80-0625-068 1-82-0341-013 1-85-0067-025 2-81-2565-001 2-84-2046-001 l C-81-0529-014 0-84-0084-059 1-81-0215-055 1-82-1001-090 1-85-0070-030 2-81-2566-001 2-85-2009-062 i 0-82-0127-077 0-84-0101-025 1-81-0467-062 1-83-0007-062 1-85-0684-079 2-81-2581-055 0-02-0130-077 0-84-0103-077 1-82-0062-002 1-83-0026-050 1-85-0085-317 2-81-2607-055 0-82-0229-057 0-84-0110-079 1-82-0103-234 1-83-0367-245 1-85-0088-062 2-82-2039-002 i 0-82-0258-067 0-85-0022-241 1-82-0107-090 1-84-0001-062 1-85-0091-030 2-82-2050-068 l 0-82-0275-077 0-85-0040-062 1-82-0140-090 1-84-0039-031 1-85-0092-026 2-82-2077-090 l O-82-0315-410 0-85-0073-077 1-82-0154-062 1-84-0052-085 1-86-0006-068 2-83-2022-079 t
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l , I ( Page No. 1 I C2/22/88 SEQUOYAH n:UCLEAR PLANT ., 10 CFR 50.59 ! 1987 NRC ANNUAL OPERATING REPORT l FACILITY CHANGES - TEMPORARY ALTERATIONS l l l CESCRIPTION SAFETY
SUMMARY
** TACF NUMBER: 0-86-0007-317 This change used two spare breakers in the hot shop 480V MCC to provide This alteration is not evaluated in the FSAR and only affects non-CSSC temporary power for temporary of fice space in the service building. equipment. The probability of an occurrence or the consequences of an accident or malfunction were not increased, and the possibility for an accident or malfunction was not created. The margin of safety for this equipment is not defined in the basis of any T.S. ** TACT NUMBER: 0-86-G009-317 Thl3 alteration added a "Ya connection in fire hose cabinet 0-26-715 to provide This alteration does not affect any CSSC equipment. The probability of an o cooling water se rce for temporary A/C unit, and added two threadotets to the occurrence or the consequences of an accident or malfunction were not increased, servica building roof and floor drain piping for cooling water discharge. Also, and the possibility for an accident or malfunction of a different type was not o connection was added to the potable water in the Laborers' shop for a water created. The margin of safety for this equipment is not defined in the basis of cooter in a temporary of fice. any T.S. ** TACF NUMBER: 01-82-0097-87 Thl3 atteration lif ted a wire on accumulator weight indicating switches The accunulator weight indicating switches have been declared defective by 1-WIS-87-21, 23, and -24 to disable the starm input to annunciators Westinghouse. Def eating the alarm input f rom the system will not increase the 1-xA-55-6C/27 and 1-XA-55-6A/28. probability of an occurrence or malfunction. This TACV is sche &ted to be cleared when work for DCR P-1400 is complete. ** TACF NUmsER: 2-86-2014-031 Tr.i3 atteration removed the RTV foam insulation f rom a 4-inch sleeve between the DNE calculations, $0 NAP P53-035 (845 861125 235), ensure environmental hot tide and the sample side of the post accident sampling f acility. This was qualification is not affected. The margin of safety, as defined in the basis of done ts (Llow increased air flow from the sample side to the hot side of the any T.S., is not reduced. This TACF 'is scheduled to be cleared post triit 1, post accident sappling facility. cycle 3.
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s Page No. 1 02/22/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL Or[ RATING REPORT S CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
4
** AOI-003 MttFUNCTION OF REACTOR MAKEUP CONTROL - UNITS 1 AND 2 REV No. 007 This revision deleted inunediate actions and combined the thr** sections for Insnediate actions for dilution accidents are cmtained in A01-34. The' inadvertent dilution into one section. ~
probability of an occurrence or the consequences of accident or malfunctico . were not increased by this revision. The possibility for an accident of a different typt was not created. This revision did not make any T.S. N equipment inoperable.
** A01-004 NUCLEAR INSTRUNENTATION MALTUNCTIONS - UNITS 1 AND ? -
REV NO. 009 This revision deleted the issnediate actions of source range monitor failure The deleting of imunediate actions and reformating the instruction did not and combined it witt. audio count rate failure. This revision also deleted increase the probability or consequences of an accident er matfinction. inssediate actions for Intermediate range f ailure and changed the symptoms The T.S. tesis was not af fected, and the mergin of safety was ret 'teduced. to asstane sirrJt e power range channet f ailure in the power range f ailure saction.
** A01'45 dNSCHE00LtG .*EMOVAL OF AN RCP LS; COW F UNITS 1 AND 2 REY O 010 This revision revised etersvin:iications to the core probable ir-d delat.ed The insnediate operator actions are hanoted in an emergency instruction.
snusediate operator actions. The procedure was also revised to be The probability of an accident was not increased. and the possibility for consistent s' 3 Westinghouse N-7 peh e w s,
~
an accident of a dif ferent type was not cicatW. The margin of safety, as definrd in the be:!s e-! any I.S., wc5 ret e- 4ed.
** A01-006 SMALL REACTue COOLANT SYSTF". LE4 - UNITS 1 AND 2 '
REV No. 017 This revision rhed the irc:edia e operetor actions and symptom alarms This change did not have any affect on the T.5. basis. The probability pf section, and also revised the generat f v mat of the instruction. An occurrence or the consequences of an accident or metfunction were not L ', increated, and ti.e possibility of an accident or autfurction of a dif ferent d
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~
IC CfR 50.57 .6 1987 ERC ANNUAL OPERATING REPORT
- + - -
CieANGES TO PROCEDURES AS DESCRISED is THE SAR . .- DESCRIPi!Ost 5AffiY %WY g i type was tot created. ' i ,_ n 4
- . . . - y Act s*2 10REA00 WATCN/ WARNING - 121TS 1 AND 2 REW mo. 812 This revision updated the dm - tic.t and made it consistent with TSAR, this revision made the procedure consistent 'with comettments in the FSAR. ~
Section 3.8.4. It was also revised to power , tornado dampers per SCR SON This revision was also consistent with the T.S. In that LCO 3.0.3 is - EES 86136. entered when both treins of control room emergency ventitation are made inoperable by closing the tornado dagers. .This does not increase the probability of an accident or create the possibility for an accident cf a , different type. REW a0. 013 This revision added 24 fire doors which must be breached for tornado these fire doors are breached per T.S. 3.7.12.' The probot:ltity for o ' werning. This is per meno s25 870721019 from D#E and CAOR $0f870022. The previously evaluated accident was not increased. The possibility for an' " .4 revision also added a step to ensure automatic-closing fire door A51A is accident of a dif ferent ' type was not created, and the margin of safety, as . a apen, defined in the basis for any T.S., was not redaced. REV WO. 014 This revision replaced the ERCW strainers automatic backwash with a manuel The ERCW system witt not be degraded by placing the backwesh features of backwooh by utilizing $01-67.1 which describes the manuel operation of the the screens arvt straintrs in the menuet mode. ' The appropriate procedural; traveting screens. modification, and dose rate considerations have been addressed ard l
. evaluated ensuring that the systeer integrity is maintained. The
- probaultity of an occurrence or the consequences of an accident or -
metfunction were not increased, and the possibility for an accident of a ,
.different type was not created. The mergin of safety, as defined in the j basis of any T.S., was nat redaced.
** A01-009 EARTMOUAKE - UNITS 1 AND 2 '
REV 20. 007 This revision added a step for checking local seismic alare panet and a Att of these changes are procedure enhancement changes thich did not affect" N Y
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___. . _ _ - - _ . _ ..~ . _ _. _ _ _ - - . . _ . . . _~ - . - .- - _- - -. a- -. . -- .u______.
_. . . . - - ._ _ _ _ .___=___ _ __ _. . . . Page No. 3 02/22/86 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
reference to AOI-7 and AO!-22 in case of a dam break. Also added a step to any T.S. basis. check the ERCW traveling acreens.
- A03-011 LOSS OF CONDENSU VACUUM - tmITS 1 AND 2 REV NO. 035 The revision an';ed Westinghouse reconsmendation to manustly trip the turbine The main condenser is not included in the T.S. The probability of an when the cortmer pressure is >1.7 psia eAen operating below 30 percent occurrence or the consequences of an accident or metfunction of e<pipment power. were not increased, and the possibility of an accident or sielfunction of a different type was not created. No margin of safety Wes re(bced.
- AOI-012 LOSS OF CONTAINNENT INTEGRITY - UNITS 1 AND 2 REW NO. 006 This revision reduced the issnediate operacor action time and changed the The reduction of the launediate operator action time and changing the formet formet of the instruction. of the instruction did not increase he probability or consequences of an -
accident or matfunction. The loss of contairement integrity is not - addressed in the FSAR. It is address ! in the T.S. for modes 1 through 4; a one hour acu an time is allowed. The mergin of safety, as defined in the basis of any T.S., was not redaced.
- A01-013 Loss CF ESSENTIAL RAW COOLING WATER - UNITS 1 AND 2 REW NO. 010 This revision reduced issnediate operatr r actions, cond>ined pump trip and The reduction of lasnediate operator actions and changing the format of the gassing f ailure sectic.as, and deleted toss of att ERCW pmps and operating instruction did not increase the probability of an occurrence or requirements f or various plant site conditions. Also added Appendia R consequences of an accident or malfunction. The possibility for en valve information. accident of a different type was not created. and this revision had no affect on the T.S. basis.
1
4 s Page ho. 4 02/22/88 SEQUDYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY SUMARY g
** Aot-016 LOSS OF NoamAL FEEDu4TER - UNITS 1 AND 2 REY No. 009 This revision reduced Isenediate operator actions and added a section f or The format changes eruf the reduction of luenediate operator acticos did not MFW pupp speed metfunction. This also deleted a section for total toss of increase the probability or consequences of an accident or metfunction nornut feedwater since it la covered by emergency instructions, previously evaluated in the ISAR. This did not create an acciuent of a different type and had no affect on any T.S. basis.
A01-01T TLMBINE AND GENERATOR TRIPS - UNITS 1 AND 2 , REV No. 013 The revision deleted part ITA (turbine trip above P-9), since this is This procedure change is consistent with FSAR handling of turbine trip covered by E-0. Also deleted discussion section and revised part 17B to tetow P-9; therefore, the probability of the occurrence or consequences of maintain ax power tevet instead of decreasing to approatmately two percent. an accident or matfunction of equipment were not increased. This procedere change did not affect any T.S. basis.
** A01-021.1 LOSS OF 125v DC VITAL sATTERY ; aRD I - UNIT 1 REV No. 010 This revision reduced lemmediate operator actions and reconcited the The reduction of f amediate operator actions and removal of the PD charging procedure with emergency instructions. The PD charging pung usage pLup reference had no af fect on the probability or Conse@Jences of an reference was deleted, and annunciations were corrected. accident or malfunction. The PD charging pump is a nonsafety item, anr8 the change had no adverse affect on any safety system.
OI 021.2 LOSS OF 125v DC v!TAL BATTERY 80ARD II - UNIT 1 REV NO. 011 This revision reduced issuediate operator actions and reconciled the The reduction of issnediate operator actions and removat of the PD charging procedure with the emergency instructions. The charging pmp usage pmp reference had no af f eet on the probability or consegmences of an reference was deleted, and annunciations were corrected. accident or malfunction. The PD charging pump is a nonsafety Item,.and the change had no adverse affect on any safety system.
s" Pese No. 5 02/22/88
$EQUOYAM NUCLEAR PLANT 10 CFR 50.59 1987 NRC AhWUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
** AOI-021.3 LOSS OF 125V DC bJi AL SATTERY BOARD III - UNIT 1 REV NO. 007 This revision deleted tassediate operator actions, corrected annunciations, The deletion of immediate operator actions and addition of information had and added a reference to fifth vital i>attery. no affect on the probability or consequences of an accident or matfunction.
The immediate operator actions are now located in the sshsequent actions section, and the margin of safety was not affected.
** A01-021.4 Loss OF 125V DC VITAL SATTERY BOARD IV - UNIT 1 REY NO. 007 This revision moved issnediate actions to stbsequent actions section and The relocation of issnediate actions had no affect on the probability or torrected the annunciations. consequences of an accident or malfunction. No ananatyred condition was introduced, and the margin of safety was not effected.
** AOI-021.5 L0ss of 125V DC VITAL sATTERY SOARD I - UNIT 2 REV NO. 005 This revision moved issuediate actions to subsequent actions sections and The relocation of issnediate actions had no effect on the probability or corrected the annunciations, consequences of an accidcnt or malfunction. No unanaly2ed Condition was introdJced, and the margin of safety was not af fected.
** AOI-021.6 Loss OF 125V DC VITAL SATTERY BOARD II - UNIT 2 REV NO. 006 This revision moved issuediate actions to subsequent actions section and The relocation of insnediate actions had no affect on the probability or corrected the annunciations, consequences of an accident or matitmetion. No unanalyzed condition was introduced, and the margin of safety was not affected.
1 Dage No. 6 02/32/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
y AOI-021.7 LOSS OF 125V DC VITAL BATTERY BOARD III - UNIT 2 REV NO 007 This revision corrected amunciations and deleted the PD char 9 ing purp This revision did not incre',se the probability of an accident or reference. malfunctiori previously evaluated in the FSAR. The PD charging pump is a nonsafety item, and the margin of safety was not affected. " A01-021.8 LOSS OF 125V DC VITAL BATTERY BOARD IV - UNIT 2 REV NO. 007 This revision corrected emunciations and deleted the PD charging purp This revision did not increase the probability of an accident or reference. malfunction previously evaluated in the FSAR. The PD charging pump is a nonsafety item, and the margin of safety was not affected. _
- AOI-022 SREAK OF DOWNSTREAM DAM - UNITS 1 AND 2 REV NO. 006 This revision reduced inusediate operator actions and ses a general revision The format changes and the reduction of immediate operator actione did not of the format. increase the probability or consequences of an accident or malfunction previously evaluated in the FSAR. The possibliity for an accident of a dif ferent type was not created, and the change did not af fect any T.S.
basis. REV NO. 007 This revision added step E for manual operation of ERCW screens and There are no specific design requirements which specify that the automatic strainers. feature for tuckwashing be in service or that manual backwash is preferred over automatic or vice versa. DNE calculation (844 870918 011) provided graphs of flow versus pressure drop for clogging of the strainers and indicated when backwashing should be laptemented to clean the strainers. The calculation also established that the continuous backwash teature of the strainers could be placed in service without degrading the ERCW system or flow requirements. Based on the safety evaluation, the probability of
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s Page No. 7 C2/22/88 . SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
occurrence or the consequences of an accident or metfunction of equipment were not increased. The possibility of an accident or metfunction of a different type than those previously evaluated was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
- AOI-023 REACTOR COOLANT PUMP SEAL ABWORMALITIES - UNITS 1 AND 2 REV NO. 006 This revision deleted Inunediate operator sctions and deleted section 8 Seat abnormatities prior to ptmp startup are to be included in 501-68.2.
(seat abnormalities prior to puup starttpi. These changes did not increase the probability of an occurrence er consequences of an accident or malfunction previously evaluated in the FSAR. These changes did not create the possibility for an accident or malfunction of a different type. A01-23 does ret affect any T.S. basis.
- AOI-024 STEAM GENERATOR TUSE LEAa: - UNITS 1 AND 2 REO NO. 006 This revision reduced insnediate operator actions, revised the procedure to lhe reduction of laemdiate operator actions ord the general revision to the te consistent with E-3, and transitioned to ES-3.2 for cool down. AOI did not increase the probability of an occurrerce or consequences of an accident or matfuction previously evalueted in the FSAR. The possibility for a different type accident was not created, and the change had no affcct on any T.S. basis.
A01-025.2 toss OF 120V AC vlTAL INSTRUMENT P0utR BOARD 1 UNIT 1 REV No. 005 This revision streamlined operator actions and celeted appendices A and 8. Moving isonediate operator actions to subsequrmt operator actions section and deleting appendices A and 8 dies not increase the probability ef an occurrence or the consequences of an accidrent. Immediate operator actions are not of an urgent nature. A new Apperviin A, ' Load List." was placed in the instruction. The possibitity of an accident of'a different type was Page No. 8 02/22/88 SEQUOYAH huCLEAR PLANT 10 CFR 50.59 1987 NRC AhMUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY SUMMART , not created, aruj the margin of safety as defirux! in the basis of any T.S. was not reduced. AOI-025.3 LOSS OF 120V AC VITAL INSTRUMENT POWER BOARD 1-III - UNIT 1 - REV NO. 005 This revision streamlined operator actions and deleted appendices A ard B. Moving imunediate operator actions to subsequent operator actions and the deleti a of appendices A and S did not increase the probability of an occurrencs or the consecpaences of an accident or malfunction. Immediate operator actions are not of an urgent nature. A new Appendia A, "Load List," was placed in the livstruction. The possibility for en accident of a dif f erent type was not created, and the margin of safety, as defined in the basis of any T.S., was not reduced. A01-025.5 LOSS OF 120V AC VITAL INSTRUMEhi POWER BOARD 2-I - UNIT 2 REV NO. 004 This revision streamlined operator actions and deleted appendices A and 8. Moving inusediate operator actions to the subsequent operator action section and deleting appendices A and 8 did not increase the probability of an occurrence or the consequences of an accident or metfunction. lausediate operator actions are not of an urgent nature. A new Appendix A, "Load List," was placed in the instruction. The possibility for an accident of a d;f ferent type was not created, and the margin of safety, as defined in the basis of any T.S., was not redJced. C A01-025.7 LOSS OF 120V AC INSTRUMENT POWER BOARD 2-III - UNIT 2 - REV h0. 004 This revision streamlined operator actions and deleted errorwous appendices The actions perf ormed on safety equipment were unchanged. The probability A and B. of an accident was not increased, and the possibility. for an accident of a different type was not created. The margin of safety, as defined in the
h.-_ o Page No. 9 02/22/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CMANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
g basis of any T.S., was not reduced.
- A01-03.8 LOSS OF 12dV AC VITAL INSTRUMENT POWER BOARD 2-IV - UNIT 2 REV #0. 004 This revision streamlined the operator actions and deleted appendices A and Moving iemediate operator actions to the subsequent op*rator actions B. section did not increase the probability of an occurrence or the consequences of an accident. Innediate operator actions are not of an urgent nature. The new appendix A, which contains the 1.B. alarms and indicators, is sufficient to identify malfunctions to the operator. The possibility for an accident of a different type was not created, and the margin of safety, as defined in the basis of any T.S., was not reduced.
- A01-028 FUEL CAD 0!NG FAILURE OR HIGH ACTIVITY IN REACTOR COOLANT - UNITS 1 AND 2 REV NO. 001 This revision reduced issuediate operator actions and combined Sections A The format chnages and the reduction of immediate operator actions did not and 8 into one section. Increase the probability or consequences of an accident or metfunction previously evaluated in the FSAR. The possibility for an accident of a different type was not created, and the change did not affect any T.S.
basis.
- AOI-029 DROPPED OR DAMAGED FUEL ASSEMBLY OR REFUELING CAVITY SEAL FAltuRE - (mITS 1 AND 2 REV No. 003 The format was roesed for hunan f actors, reduced isonediate operator This revision was written to handte an accident. The probability of an actions, and revised organizational name changes. The revision added a accident was not increased and the possibility for an accident or reference to SOI-30.5E for verification of an auxiliary building isolation. matfunction of a different type was not created. These changes do not affect any T.S. basis.
Dage No. 10 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CNANGES TO PROCEDURES AS DESCRIBED IN THE SAR l DESCRIPTION SAFETY
SUMMARY
A01-030 PLANT FIRE - UNITS 1 ANO 2 REV No. 005 This revision reduced inanediate operator actions and clarified possible The operator actions are essentially unchanged. The strematining of the storms. procedure had no ef fect on the probability or consequences of an accident or malfmetion. The margin of safety, as defined in the basis of any T.S., was not reduced.
** A01-031 ASNORMAL RELEASE OF RADIOACTIVE MATERIALS - UNITS 1 AND 2 REV NO. 004 This revision reduced the symptoms section and the insnediate operator This was bastcatty a procedure format revision. The changes did not actions section. A general revision to the automatic actions and the increase the probability of an occurrence or the consequences of an stbsequent action sections was made, accident or matfmetion. - The possibility for an accident or malfmetion of a different type was not created, and the change did not affect any T.S.
basis.
** A01-033 CNLORINE RELEASE - UNITS 1 AND 2 REV NO. 002 This revision reduced the issnediate operator actions section and clarified This instruction handles an abnormal event as analyzed in the FSAR. The the chlorine instrument setpoint. A general revision to the format of the changes made did not increase the probability of an occurrence or the instruction was made, consequences of an accident or malfunction. The possibility for an accident of a different type was not created, and the changes had no effect on any T.S. ,
~
** A01-034 EMERGENCY BORAT10N - UNITS 1 AND 2 REV NO. 002 This revision reduced the uncontrotted increase in reactor power as Reducing the uncontrolled increase in nuclear power as indicated by nuclear indicatni by nuclear instrumentation and reduced inenediate operator instrumentation and reducing lainediate operator actions did not increase actions. The section for local boration (which is not used) and the the probability or corncquences of an accident. Local boration is not e
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9, Page 100. 11 02/22/88 SEQUDYAN NUCLEAR PLANT 10 CfR 50.59 ., 1967 NRC AseMUAL OPERATIteG REPORT CHANGES TO PROCEDURES AS DESCRISED IN THE SAR T DESCRIPTION SAFEif SupetARY section for boron injection tank injection (which is reserved for ECCS/A1WS mentioned in the fSAR and may be deleted without effecting the FSAR. This conditions) were deleted. AOI contains steps for checking the 1.5. timits, and the margin of safety- - was not re& ced. i & 1 Y e i k, 1 4
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.Page No. 1 02/22/88 SEQUOYAN IfUCLEAR PLANT 10 CFR 50.59 1987 NRC ANefUAL OPERATlhG REPORT CHANGES TO PROCEDURES AS DESCRISED IN THE SAR DESCRIPTION SAFETY
SUMMARY
j
** E-0 REACTOR TRIP OR SAFETY INJECTION REW se0. 002 This revision added step 17 to check ERCW operation. This step was The ERCW screen wash system, as sedified by TACF 82-258-67, is capabte of required to fulfitt the requirements of the DNE 0S00 for TACF 82-258-76 meeting the requirements of the ERCW system. The TACF requires the system (525 870413 501). This TACF was implemented to remove the "loss of signat" to be operated in the manual mode, which is acceptable, provided the to automaticatty start the wash ptsup and screens and to stop their special requirements recomumended br feEB are implemented. The probability continuous operation caused by the tat ture of the levet instrunentation. of an occurrence or the consequences of an accident or matfisiction of Other changes incorporated were procedural enhancements. equipment were not increased. '
Temporary deletion of the automatic feature for starting the screen and wash system has no effect on system performance or operator action during loss of offsite power. With the special requirements laptemented, toss of annunciation of differentist pressure across the screen for operator information is not essential. An accideat of a different type was not created by the TACF. TACf 82-258-67 does not affect the margin of safety, because the basis for the T.S. was not redJced. E2 STEAM GENERATOR TUBE RUPTURE REV ss0. 001 This revision provided enhancements to the procedure to assist the operator These enhancements do not increase the occurrence or the consequences of an in determining a faulted steam generator and other guidance. accident or malfunction of equipment evaluated in the FSAR, They do not create an accident or matfisiction of a dif ferent type than previously evaluated. This change did not affect any T.S. basis; therefore, the margin of safety was not reduced.
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Page No. 2 02/22/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 mRC ANNUAL OPERATING REPORT CHAtoGES TO PROCEDURES AS DESCRIBE 0 IN THE SAR i DESCRIPTION SAFETY
SUMMARY
** ES-1.2 TRANSTER TO RNR CONTAINMENT SUMP REW NO. 003 This revisf on changed the contalrunent suip auto swepover setpoint f rom 10 The procedure was revised to agree i.l n new auto swepower setpoint. The' percent to 11.25 percent levet to comply with the new bistabte setpoint. probability of an occurrerts or the consespences of an accident were not L increased, and the posolbility for an accident of a type different from that previously evaluated was not created. The mergin of safety, as defined in the basis of any T.S., was not seibced.
4 ll 1 , 1 o 9 d
t I O O O O SJMMARY OF O PROCE)JRE O O CHANGES O O O O,S L R V E l _ A N C E O I N S Ril C -' l O N S
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O O O O
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SUMMARY
3
" 58-001 SURVEILLANCE PROGRAM - (MITS 1 AND 2 REV m0. 019 This revision added the requirement, in accordance with h0AM, Part II, This change did not affect physical plant configuration. It provided a section 4.9, for DNE to review at t eresolved test deficiencies and more accountable method of reviewing unresolved test deficiencies. The implemented the recuirements of NOAPt, Part I, Section 2.16 (SPTS 861218 A content of specific M!s and sis was not ef fected by this change.
and 8701190). Therefore, the probability of an accident or malfmetion of plant equipment was not increr_ sed, nor did it create any different type of accident. Because the content of the T.S. was not changed, the eersin of safety was not reduced. C 51-002 SN!FT LOG - UNITS 1 AND 2 REV mo. 041 This revision deleted references to figure 3.1.2 which no torger emists in the changes to incorrect figure reference and administration had no adverse the T.S. It etso included correction to various date units ard T.S. timits effect on equipment or safety, the correction did not increase the and deleted 27T51A, e, and C relays f rom degraded voltage retey operability probability of an accident or malfunction, nor did it create any of a verification. different type. The correction made in this revision had no ispect on saf ety; therefore, the margin of safety was not redaced. REV NO. 042 This revision added a ruber (3.21.1) to the instructim for Clarification of notes and information about collecting data neither clarification, added a ruber in the note section of the data sheet where increased the probabitity of an accident or metfunction, nor created a more then one instrument can be used, added panet numbers on several items ditferent type of accident. These clarifications did not reduce the mergin to pir, point location, corrected identification of Contairunent Pressure of safety. Plant Operating Instructions, and completed inf ormation to note 12. CO 51-003 DA!LY, UEEKLY, AND MONTNLY LOGS - UNITS 0, 1, AND 2 REV NO. 052 This revision changed vital battery V distribution panets A and 8 f rom Making the procedure agree with plant configuration in no way increased the circuit tweaker 1 and circuit breaker 2 to circuit breakers 104, 105, 106, probability of an accident or matfunction of equipment, nor did it create a
. __ m ._ _ . _ _ _ _ < _. __ _ _ . . . _ _ _ _ _ _ . . _ - . _ . =_ .. .. _ Page uo. 2 C2/22/88 SEQUOYAN NUCLEAR PLANT to Cfa 50.59 1987 WRC ADHfUAL OPERATING ReORT CNANGES TO PROCEDURES As DESCRIBCD IN THE SAR DESCRIPTION SAIEf f simMAaf 4 and 107. These breakers were relatseted by way of a work request to conform different type of accident or natissiction. Since the tograde in the with print 454703-5-1 (RO). The procedure change reflects this plant procedure did not adversety affect plant safety, the margin of safety was configuration change. not degraded in any manner.
- SI-006.1 CouTAlmMENT BUILDlWG VENTILATION !$0LATION (100 HRS /7 DAT) - UNITS 1 AND 2 REV NO. 005 This revision deleted att liquid-fitted and closed-loop system valves from Only the valves, hatches, doors, etc., ahich provide direct access from the the 51. containment atmosphere to the outside atmaagdiere are regJired to be checked. The probability of an accident was not increased, and the possibility for an accident of a different type was not created. The margin of safety, as defined in the basis of any T.5., was not redaced.
- SI-007 ELECTRICAL POWER SYSTEM: DIESEL GENERATORS - tjulf 0 REW No. 037 This revision added part 6.3 to the instruction body, added a note to Clarification of this instruction of shen to cettect data ensures further clarify when Data Sheet 3 is to be performed, and added blanks to ensure compliance with safety analysis. This clarification did not increase the both engine parameters are checked. probability for an accident or malfuriction, nor create a dif ferent type of accident or metfunction. This revision did not atter the margin of safety as defined; therefore, it was not reduced in any manner.
REW m0. 038 This revision was prompted by T.s. Change 107. This changed the testing The changes to the instruction clarified the scope, implemented T.S. f recysency and gave attowance for less frequent ambient starts, added changes, and did not af fect the actual performance of the test. Therefore, signof fs f or logging starting and loading times, corrected references (DPMs the probability or conseqJences of an accident or metfunction were not have been superseded by technical standards), added a note dealing with increased, and the margin of safety, as defined, was not affected by the emergency stops and/or relay actuations, and corrected Data Package Cover changes.
$heet in accordance with 51-1.
REW #0. c39 This revision added a signof f for verif ying that MvAas are within range The actual scope and intent of the instruction was not changed. secause of
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s Page eso. 3 02/22/38 510UOtAN NUttEAR PLANT 10 CFR 50.59 1957 NRC ANNUAI_ OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBE 0 IN THE SAR DESCRIPTION SAFETY StAe44RY g (.75 to 2.38). This change is due to the removat of the exciter voltage the modification, the procedure was revised to ensure correct performance regulator min-man modute. Added D/G capability curves as references. by the operator, The possibility of an accident or ogsipment metfunction was actuelty decreased by ensuring MVARs were within the acceptable range of the capability curve. The margin of safety, as defined in the basis of ' any T.S., was not # educed. REV h0. 040 This revision was made to change approminate rumbers to a range for several The scope and intent of the procedure were not attered. The probability of parameters and added minisman and amminue rumbers to severat items on the an accident was not increased, and the possibility for an accident of a D/G running condition checklist, different type was not created. This revision did not reduce any margin of safety as defined in the basis of any T.S. REV NO. 041 This revision was made to increase the 0/G continuous and 2-hour load The new limits are based on DNE calculation SON-53-002, "Diesel Generator ratings to comply with a T.S. change. This revision increased the 0/G Load Analysis." These new limits do not exceed the D/G capability curves. toeding from 4000kW to 4400kW and from 2000kW, when both units are in modes The probability of an accident was not increased, and the possibility for 5 or 6, to 2200kW. an accident of a different type was not created. The margin of safety, as described in T.S. 3.8.1.1 and 3.8.1.2, was not redJced.' SI-007.1 DIESEL CENERATOR AC ELECTRICAL POWER SOURCE OPERA 81LITT VERIFICATION (DIESEL GENERATOR /0FFSITE SOLWCE) - UNIT 0 REV h0. 010 This revision added a note to state when ambient starts are required, This revision clarified when ancient starts were required end added signoff clarified note emplaining when to stop the stopwatch for the 10 seconds, for recording time. This did not affect the probability of an accident or and added space to record the actunt time of each start. the consequences of accidents or malfunctions. This revision did not alter any T.S.; therefore, the margin of safety was not reduced.
$1-007.2 DIESEL CEhERATOR SURVEILLANCE FREQUENCT - UNIT 0 ' #EV ho. 003 This revision deleted superfluous information f rom the scope, added a data AIt of the changes to this instruction, other than T.S. and acceptance sheet for recording inoperables and added several more lines for rriteria changes, were of an administrative nature. The T.S. change
- - -. . . - . . _ , .- ~ . - . . ., . - - . . . - . .- -- ..
s Dage me, & 02/25/88 SEQUOYAN NUCtEAR PLANT ', 10 CfR 50.59 1987 hec ANNUAL OPERAllNG REPORT CHANGES TO PROCEDURES As DESCRISED IN TME SAR DESCRIPTION SAFETT SupmART I performers' signatures. The data sheets were sigttfied, und new emanple involvM the testing frequency based on the rumber of f altures per valid tables were made. The title of Attachment B was changed to Definitions" tests (20 test and 100 test windows). The rumber of tests and f altures is - and addressed T.S. change which changed acceptance criteria. now determined on a per D/G unit basis instead of a per nuclear unit basis. This revision also contained provisions for declaring the 0\G inoperable and hec reporting requirements. The changes did not af fcct the margin of safety or increase the probability of an accident. s1-007.3 0 EsEL GENERATOR fu2L OIL TRANSFER PUMP PERf0RMANCE TEST - UNIT 0 REW m0. 000 This instruction was written to establish a guideline for measurement of The test methods remain the same as when they were perforacd in SI-7. The each D/G fuel oil transfer ps, flow rate and vibration monitor 6ng. This probability of an occurrence or the conseysences of an accidmt or instruction was previously incorporated in SI-T. SI 7.3 will now stand matfunction were not increased. The possibility for an accident of a alone, different type was not created, and the margin of safety, as defined in the 4 basis of any T.S., was not reduced. REV NO. 001 This revision added a note stating that the fuet oil transfer p g shalt operation of the fuet of t transfer pg 5 minutes before takins data is an . run 5 cinutes before performance data is taken and corrected a transposed ASME re wirement and does not affect the margin of safety or increase the
. watve number (0-Lt-18-T613). probability of an occurrence or the consequences of an accident or malfunction of equipment important to safety. Correction of transposed valve number has no aspect related to safety. " $1-008 80RIC ACID FLOW PATNS - TEMPERATURE VERiflCATION - UNITS 1 ANO 2 REW NO. 009 This revision changed the title page to reflect unit 1 and unit 2, added This revision conptics with 51-1, Appendia F. It was administrative in SPO approval of test, arad corrected typographical errors. nature and did not increase the probability of an accidcest or metfunction and did not create an accident of a different type. There was no safety surgin degradation realized by administrative changes in this instruction revision.
w
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Page No. 5 02/22/88 SEQUOTAM NUCLEAR PLANT 10 CfR 50.59 1987 NRC ANNUAL OPERATING REPORT CNANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAftty
SUMMARY
** $1-009 ACTUATION OF AU'0MATIC VALVES VIA SI SIGNAL FOR NON-TESTABLE BORIC ACIO AND ECCS FLOW PATH WALVES - tmITS 1 AND 2 REV NO. 021 This instruction has been revised to identify phase A and contairueent vent This revision in no way increased the probability of an accident or.
Isolation handswitches by use of proper equipment identification rumbers malfunction, nor did it create a different type of accident. Since the $1 and to correct boron injection tarA recirculation valve identification. scope, intent, and T.S. remain the same, the snargin of safety was not ' reduced. SI-014.2 VERIFICATION CF CONTAINMENT INTEGRITY - tm!T 2 REV NO. 014 This revision esos stade to include at t vents and drains between att This revision brought the instruction into futi co,tlance with LCO 3.6.1, contairement isolation valves with the exception of main steam,, AfW, Mf W and SGN T.S., and NRC's T.S. Inte mretstion 3/4.6.1.1 dated Decenter 12, 1966. ECCS systems. There was no change in plant configurathr. iAlle performing this ,- instmetion the probability of an accident was not increased; and the' possibility of an accident or malfunction was not creat,ed. There was no redaction in the margin of safety, as defined in the bests of any T.S.
*O SI-015 EMERGENCY CORE COOLING SYSTEM RNA LOOP 4 RCS ISOLATION - UNITS 1 AND 2 REW No. 011 This revision clarified the St. changed notification f rom SE to SRO, and The revision complies with SI-1, Appendis F, and cid not alter any T.S. or designated by step signoff at what pressure the valves actuotty close. the intent of the instruction. Therefore, the probability of an accident or matfmetion was set increased, and the margin of safety esas not reduced.
'o
** SI-016 BIT NEAT TRACINC - LMITS 1 AND 2 REW No. 008 This revision changed step 6.1.1 tacontrot penet" changed to "control This revision did not alter any T.S. and did not change the intent or thermostet"), ivtuded the purpose of storm in step 6.1.3, attered note 1 result of the instruction. Therefore, the mergin of safety remains to include verification of burned out light as requested in step 6.1.3, and unchanged, and there was no increase in the probability of an accident or
. ~ . ~ . .- ~ ~ , . . -- . .. . - . .. - . - - . - - - - . . ~ . - . ._ - - - . - _ . _ . - - ..-- .
E g Page No. 6 02/22/86 SEQUDYAN NUCLEAR PLANT 10 CFR 50.59 1557 Nec ANNUAL OPERATING REPORT CNANGES TO PROCEDURES AS DESCR18ED IN THE SAR DESCRIPil04 SAFETT
SUMMARY
g changed title of instruction to occurately reflect the intent of neu init malfunction. addition SIT heet tracing and Sli strip heaters. 4
'(.
** SI-61T CONTAINNEWT SNIELD SulLDING EMERGENCY GAS TREATMENT SYSTEM f LOW - UNITS 1 AND 2 2
PEW NO. 019 This revision added administrative signof f to data sheet, SRO approvat of This revision complies with $1-1, Appendix F. These administrative changes a test performance, clarification of SR, and corrected russerous typographical and ordiancements did not increase the probability of an accident er errors, metfunction and did not reshace the mergin of safety.
;~
** SI-019 ComiAlmuEsf SYSTEMS D!v10ER SARRIER, rem 0VAOLE CURSS, PERSONNEL ACCESS DOOR AND EQUIPMENT NATCNES - UNITS 1 AND 2 aEW m0. 010 This revision changed the organizationet name from e4 to OESC on Data This revision complies with $1-1, Appendia F, and uns administrative in Package Cover Sheet, changed SE to S40, and identified dets sheet to match nature. This did not redace the mergin of safety and did not increase the 1 instruction. probability of an accident or malfunction of plant espalpment.
** SI-021 AUNILIARY sulLD!st GAS TREATMENT SYSTEM - UNITS 1 AND 2 mE7 40. 416 This revision changed estit designetten to -0 , added Sao approvat prior to This revision in no way affects the intent or results of this proceshare.
testing, added aucteer mettability Date System technician signof f for There mes no increase in the probability of an accident or motfunction dae sustified Itointenance Date System purposes, added instrument identification to these changes, and the mergin of safety uns not redaced. en bour meters for each f an, and corrected various typogragAnical errors.
** SI-026.14 LOSS OF OFFSITE POWER W:TN SAFETY INJECfl0N
- D/G 14-A CONTAINMENT ISOLATION TEST
- UNIT 0 WEW 1s0. 013 This revision added f acW pump toad sequence verification and added a toad This revision enSused the ERCW pumps and alternate feeder are property shed test of the alternate supply breaker to the shutdown board. tested. This decreased the probability of an accident or malftssction of egaipment. The possibility for an accident of a ditferent type uns not '
created, and the margin of safety, es defined h the basis of any T.S., mes 4 4
.l
-_ .m_._ . _ . . . - - _ . m. m -_ __m _ _ _ _ _m -- . - -_______..---s .---.m--m_..m . = . - -
Page 90 T I- 02/22/98 SEQUOVAN NUCLEAR PtANT 10 CFR 50.59 198T meC Abuunt OPERATING REPORT CMAWGES TO PROCEDURES AS DEscalSED IN THE SAR DESCRIPTION SAFETY SUMMAftf , not reduced. SI-026.2A LOSS OF OFFSITE PNER WITN SAFETY INJECT!0m - 0/G 2A-A CONTAIMMENT ISOLATION TEST
- UNIT 0
#EV m0. 414 This revision upgraded the procedare to reflect T.S. changes, additionet The testing of previously untested egalpaent does not increase the SRs, CATS items, WP additions, PRO /LER, and corrected nasmerous probability or consegJences of an accident. The sporade reflects the typographical errors throughout the instruction. current T.S., and property reflecting the SAs does not degrade any safety function nor create any new accident or estfunction.
** CI-02T tmR LOOP FLOW RATE - Uu!TS 1 AND 2 3 aEV a0. 008 This revision changed notification f rom SE to Sao, CA to OE&C, clarified This revision did not'increese the prebebility of an accident or the data sheet regarding acceptabte flow rate, and what to add for 2 toop ' metfimetion and did not create any different type of occurrence. seeking the operation, and corrected various typographical errors. procedure comply with SI-1, Appendin F, did not atter the T.S. and did not reduce the margin of safety in any menner.
** SI-032 COMPontui C00 Lies WATER valves (POSITIou VERIFICATI0s) - UNITS 1 AND 2 WEV u0. 01T This revision corrected valve identification numbers. Correction of vatve identification rumbers evenanced safety, created no new accident or metfunction, and did not increase the probatJtity of an accident or metfunction. Correcting the vatwe identification raabers did not reduce the margin of safety in any way.
sEV #0. 020 This revision added position checks of throttled valves servicing safety Positioning the CCS throttle vatves et a required position or a set rmAEber ogsipment or of fecting safety equisument flows. of turns f rom futt open ensures the minisese regsired flow rates to safety-related equignmmt during the most LCO. The or.ty f teu ra'es dif ferent f rom those anatyred in the FSAR are the ministse flow requirements to the C5P iAich have been revised from 6 gaso to 5.3 :ssa, and flow rates to I
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I Page no. 8 02/25/88 SEQUOYAN NUCLEAP PLANT l 10 CfR 50.59 1987 WRC ANNUAL OPERATING REPORT CHAEGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
l nonsafety-related equipment. Changing the CSP cooling water flow will not prevent the ptmp from performing its safety function. None of the other revised flow rates af fect safety-related equipment or equipment used to mitigate the effects of an accident. SI-033 ERCW VALVES SERVICING SAFETY RELATED EQUIPMENT (COMMON) - UNIT 0
#ED NO. 022 This revision added references, stated prerequisites, changed notification Clarification of the procedure and notification changes to compty with from SE and SRO, CA to OESC, and designated dod>te verification en $1-1, Appendix F, guidelines in no way reduced the margin of safety and did signoffs. not increase the probability of an accident or metfunction of plant equipment. " $1-033.1 ERCW WALVES SERVICING SAFETY RELATED EQUIPMENT (UNIT) + UNITS 1 AND 2 REV mo. 006 Th s revision corrected procedure titles, mode operability recpirement, Correctly identifying a proced;re ord grouping valves t,gether correctly in added prints to references, changed notification f rom SE to SRO, put A no way offect the probabitity of an accident or malfunction and do not train valve on A train ilst and put 8 train valve on S train list, create any type of dif ferent occurrence. The clarification of the corrected various typographical errors, instruction does not atter any T.S.; therefore, the margin of safety was not reduced.
REW Wo. 007 This revision deleted the tenperature control valves f rom the SI, because The deletion of non-CSSC valves did not increase the probability of art they are not CSSC equipment, and the physical construction of the valves occurrence or the consequences of an accident. The possibility for an makes it lepossible to determine their operability by visual inspection.' It accident of a different type than previously evaluated was not created. also deleted one valve which does not exist and provided a note for one The margin of safety, as defined in the basis of any T.S., was not redated. watve eAlch exists cn unit 2 only. REW #0. CD8 This revision added a note to clarify the intent of the instruction, The clarificatiew', ciad.: in the revision ensures all valves are property clarified what to do for a "throttled
- valve, clarified footnote =, and verified. The scope and intent of the instruction are clarified with the e
e- _ = - - - + _ - _ e w ____s +_-n-- -- ar 1----v--n - -,.-.gr -i.-.mq, p+, +, -r-'V-a -- T-----$' r e--P-+ y e.- y v'- w - , , . , ,
~ . ~ ~ - . ~~-._-----.-n.-._---._ - - - . ._ - _--~t r. .. - .- -~. ._ .-~ ~ .
T Page No. 9 02/22/88 SEQUOTAN NUCLEAR PLANT ' to Cf a 50.59 1987 NRC ANNUAL OPERATING MPORT CHANGES TO PROCEDUK $ AS DESCRIDED IN THE SAR DESCRIPTION SAFETY
SUMMARY
g added a position for four valves. notes and valve positions added. These changes did not increase the probability of an accident and did not redate the margin of safety, because the T.S. and acceptance criteria remained anchanged.
" SI-03 CONTAINMENT SPRAY STSTEM VALVE POSITION VERIFICATION - UNITS 1 AND 2 REV NO. 008 This revision changed notification from SE to $40, GA and OE&C, and deleted Changes in notification and clarification of the entire instruction in no references to flow diagrams, way increased the probability of an accident or selfunction and did not create a different type of accident. Clarification and change in notification requirements did not alter any T.S.; therefore, the mergin of safety was not reduced.
** 23-036 VERIFICATION Or 100 hours OF SUSCRITICALITY - UNITS 1 AND 2 RE7 NO, 003 This revision removed instructions from the data sheets and incorporated The procedural change was aede to meet administrative regsirements.
them into the body of the test. Also, it added a reference section and Instruction steps were removed from dete sheet and placed in the body of ' updated Data Package Cover Sheet in accordance with SI-1, the test. This change did not increase the probability of an accident or metfunction, nor was the margin of safety decreased.
" SI 038 SnUTDOWN MAAGIN - theITS 1 AND 2 REW No. 021 1his revision corrected an error in step 5 of Data Sheet 5 which indicated Correcting an error in the data sheet to indicate a correct data source and M* incorrect source of data. correcting the methodology to obtain accurate data did not increase the I
- probability of an occurrence, nor create the possibility for a different type of accident or malfunction. Since correcting an error in the methodology did not alter any T.S., the margin of safety was not reduced.
Page No. 10 02/25/86 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANCES TO PROCEDURES AS DESCRISED IN THE SAR DESCRIPTION SAFETY
SUMMARY
t
** SI-040 CENTRIFUGAL CMARGING PLpqP - UNITS 1 ANe 2 REV mo. OM This revision corrected inadequacies and added enhancements. It was This method of testing requires the opposite train to tee operable and revised to make part C a separate instruction. Part C has a frequency of sn-service, stpplying charging and seat flow, and the ptmp being tested to -
31 days, and the pump test f requency is quarterly. It was also wbed to be on recirculation flow. This attows more positive controt of the pamp test the pump on miniflow only, instead of maniflow plus saat/ charging being tested, attows a more accurate flow measurement, futfills T.S. flow, to atlow a more accurate flow measurement. 4.5.2.F.1 (which states that on recirculation flow, the pump witt develop a discharge pressure of greater than or equal to 2400 pstgl, and attows testing of one train withcut af fecting the other train, flow will be measured as required by ASME, Section XI.
** SI-040.1 CENTRIFUGAL CHARGING PtsqP CASING AND DISCHARGE PIPING VENTING PROCEDURE - UNITS 1 AND 2 REV N0. 000 This new instruction incorporated att the requirements of 58-40, Part C, The methodology incorporated into this SI is the same as that described into $1 40.1. Acceptance criteria and action to be taken if not met were prewlously in SI-40, Part C. The addition of acceptance criteria and added, and a valve nuuRser was corrected, correction of a valve rumber had no af fet.e. on the margin of safety.
** 53-045.4 ESSENTIAL RAW COOLING WATER PUMP M UNIT 0 RfD WO. 000 This instruction was written in two parts for the testing of the ERCW pump This instruction is in accordance with SI-1, Appendia F. The probabit4ty 94-5 and the discharge check valve, of an accident has not been increased, and the possibility for an accident of a different type was not created.
** 51-045.5 ESSENTI AL RAW COOLING WATER Pump N UNIT 0 REW WO. 000 This instruction added the use of test instrunents, made each pump test a The use of test instruments and test'ns at a single L;ed flow rate did not separate procedure, and changed testing at severet flow rates to a single redace t*e s.orgin of safety. The prrbability of an occurreece or the fined flow rate, consequences of an accident were not increased, and the poosibility for an
- . . _ _ _ . _ ..- .-_.._m .=_ .___..--___.__m _ _ _ _ . m__ _ _ . . .. . .-_ .
_ _ . _ ~ . - . -_ _. , 4 Page No. 11 02/22/88 SEQUDYAN NUCLEAR PLANT , 10 Cf t 50.59 1987 mRC AeNUAL OPERATING REPORT CNANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFEif SUMMART , accident of a different type was not created.
** SI-045.6 ESSENTIAL RAW COOLING WATER PUMP P-S - UNIT 0
#EW #0. 000 This instruction was written in two parts for the testing of the ERCL pump This instruction is in accordance with $1-1, Appendia F. The probab6lity and discharge check vetwe, of an accident was not increased, and the possibility of an accident of a different type was not created, s
** $1-065.8 ESSENTIAL RAW COOLING WATER Pump R-A - Uulf 0
#EW 20. 000 This instruction added the use of test instrssments, mode each pump test e The use of test instrtaments and testing at a single fined flow rate did not saperate procedsre, and changed testing at sever.' ..a rates to a single redxe the mergin of safety. The probability of an occurrence or the 2
flued flew rate, conseepaences of an accident were not increesed, and the possibility for.an accident of a different type was not created.
** 58-066.1 COMPouENT COOLING WATER PUMP 1A-A
- UNIT 1 AEV NO. 000 This instruction full strokes the CCs pwp discherge check watwes and Att of the requirements of SI-4 for CCs pump 1A-A vere incorporated snto establishes e one-point test et a set flow rete. Each pg is tested by a en irufswiduet procedure. The establishment of s one-point test et a flued seperate procedure. 58-4 has been cancetted. flow rate for verifying fuit stro6e of the discherge check vetwe did not increase the probability of an accident or creete the po.sibility for en 2
accident or metfunction of a different type. The margin of safety was not ' redJced.
** SI-046.2 COMPoutui C00Linc WATER Pump 15 UNIT 1 REV No. 000 This instruction futt strokes the CCS pump discharge chesk valves and A'tt *he requirenents of SI-4 for CC$ pump 18-8 were incorporated into an establishes e one-point test at a set flow rate, Each pg is tested by a individaat procedure. The establishment of a one-point test et a fined
-k
Page to. 12 02/25/88 SEQUDYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE $AR DESCRIPTION EAFETY SUMMART t separate procedere. 53-46 has been cancelted. flow rate for verifying futt stroke of the discharge check valve did not increase the probability of an accident or create the possibility for an accident or malfunction of a different type. The margin of safety e not r & cd. " 51-046.3 COMPONENT COOLING WATER PUMP 2A-A - Unit 2 REV ho. 000 This instruction futt strokes the CCS pimp discharge check valves ard Att the regairements of SI-46 for CCS pmp 2S-A were incorporated into an establishes e one point test tit a set flow rate. fac% pupp is tested by a individual procedure. The establishment of a one-point test at a fixed separate procedJre. 51-46 has been cancetted. flow rate for verifying futt stroke of the discharge check valve did not increase the probabetity of an accident or create the possibility for an accident or matfunction of a different type. The anrgin of safety was not reduced. " SI-046.4 COMPONENT COOLING WATER PUMP 28 0 - UNIT 2
- EV NO. 000 This instruction fuit strokes the CCS psp discharge check valves and Att the recpirements of 51-46 for CCS ptap 28-8 were incorporated into an establishes a one point test at a set flow rate. Each ptsp is tested by a individet procedere. The establishment of a one-point test at a fined separate procedure. 51-46 has been cancelled, flow rate for verifying futt stroke of,the discharge check valve did not increase the probability of an accident or create the possibility for an accident or malfunction of a different type. The margin of safety was not reduced.
- $1-046.5 COMPONENT COOLING WATER PUMP C UNIT 0 REV Wo. 000 This instruction futi strokes the CCW pro discharge check vatwes and Att the requirements of $1-46 for CS ptmp C-5 were incorporated into en estabtishes e one-point test at a set flow rate. Each pep is tested ty a individual procedure. The estabtisheimt of a one point test at a fined separate procedure. St-46 has teen canceited. flow rate f or verif ying f utI stroke of the discharge check valve did not s
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- CMAwGES TO PROCEDURES AS DESCRIBED IN TNE SAR DESCRIPi!ON SAFETY
SUMMARY
?
l
~
increase the probability of an accident or create the possibility for an accident or malfunction of a alfferent type. The mergin of safety ur.s rot rechred.
** 51-050 72-NOUR CNEMISTRY REQUIREMENTS - tJNITS 1 ANO 2
#E7 #0. 026 This revision clarified f requency requirement for Reactor Coolant These cG.ges did not af f-ct the intent or results of tt*, instruction.
Dese-Equivalent I-131 in accordance with T.S., indicated complete or Therefo-a, the pirobability of an accident er metfunction was not encreased, partiet T.S. cogliance, included changes required by Discrepancy Report and an accidmt or metfunction of a dif ferrat type uns not creoted. The 86-281R, and clarified the gross activity of cootant systems. This 51 was tssis of any T.S. was not affected; therefore, the mergin of safety uns not revised in accordance with SI-1, Appendia F. reduced in any manner. "*'
** SI-052 MoututY CNEMISTRY REQUIREMENTS - tNITS 1 AND 2 REW #0. E19 This revision to the 51 included the addition of an objective section to Sampling of tsbine building exhaust was eliminated, and the tritlue limit the scope of this instruction. This objective section states the was ecHed after receipt of mRC IE Suttetin 80-10 and the Tennessee requirements and their source documents. The arpticable modes have tseen Department of Mealth end Environamt requirements. The mergin of safety added to the appropriate sections. The sampling of the turbine building e,as not degraded in any manner.
exhaust has been deleted because of the a5sence of a requirement for this analysis. An acceptance criterien of 2.0 E - 05 tJC./ML tiennessee Depetment of heeith and Environnent) has been acued for the tritlue analysis of the drinking water.
** SI-053 SPECIFIC 10 DIME 150 topic ACTIVITY C0esCE&TRATIou AN0/OR D.E.1-131 DETERMINATION - (JNIIS 1 AND 2 RE7 mo. 012 This revision ernformed to 51-1 review guidelinas and took into The chang s made to this SI ef fect the formet and adequate flush times and
- consideretion the predaninete bete emitter tritius. Also, it aMed conform to SI-1 guidellres. The charges in this revision did not of fect acceptance criteria f or modes 1, 2, 3, 4, and 5. plant safety and did not present any r h safety aspects differect from -
M* 9-M DO C
s Page No. 14 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CMANCES TO PROCEDURES AS DESCRIBED IN THE SAR - DESCRIPTION SAFETY
SUMMARY
p those previously evaluated in the FSAR.
^
M 51-054 REACTOR COOLANT E DETERMINATION - UNITS 1 AND 2 - ' REV h0. 010 This revision conformed to SI-1, Appendia F, provided claria;eation, and The idkfition cf the doeninant tutta emitter tritium-40 tne E catculad on did 'j took into consideration the dominant beta emitier tritiun. not sffect plant equipment,- safety, or the f5/:A. Therefore, the se gin of ) safety was not tecated. eed thase chanNs dQ not increase the possibility l cf an wc! dent or's Qtfut 074 i ~ N ! s SI-056 3YP5090CT MATERI AL INvtNIORY ANO SEALED SOURCE LEAaC TEST - UNITS 1 AND 2 -{ e REV 110. 014 The revision was made to correct the T.S. refe ence and to remove $NM fr(se Ihis revision af fected only_th T.S. refercru.s and included SR 4.7.3.0.1 the C'._ ( which has st%fs Ace 4 perfonneeT. - SNM is no.i in TI-101. The protmaitity of an occurrence or the consequenceF of an accident or halfunction were not increasedi and tne possibility for en accident of a different type was not created. The margin of safety, as defined in the basis'of any T.S., was l _ not reduced. 1 b ** SI-058 ICE CONDENSfR CHEMISTRY - UNITS 1 ANO 2 REY 800. 013 This revision complied with SI-1, Appendia F, format, clarified arr* . . condensed ths % truction section, added an "additional co n" sheet, auf The chwnges to the instruction in tais revision were adt.inistrative and Y i
' ~
formet-complying in nature and did not increase the probability of an aodedthe73Ahimitsonboronforfittinginurposes,(rSp3ed from boron n accident or spelfunction. The margin of safety was not reduced. i( 1950 ppe o 2100 ppm to n 1900 ppm); \ J"- -- 1.-
% _y
.s s .
L " i ' ** $1-062 CONTAINMENT VACUUM RELIEF VALVES AUTO-OPEN - uni!$ 1 ANO 2 - -
~
l Jiv IIC. 0*: This revision clarified requirements, test frequency test method. and N The performence of this tcst consists of'cpening each contsinment. vacuum A. N P x s. ,
, " K. n: ,
T Ks k s
~w w m a- (. , = ss : . .
~
Y[ . N i
~ ~
m
*y..
Page No._ 6 02/25/68 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANCES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
I sleptified acceptance criteria. It addressed and specified actions to be relief valve eed measurir9 the force reo; ired for opening. It also verifies taken when acceptance criteria are not met and added required accuracies operability of the contairveent vacuun relief valves which ensures that and ranges to test equipment. containment internal pressure does not Leeccme more nesstive the. 0.1 psid. s The performance of this test dces notalace.the plant in an mdocunented LCO or unanatyred condition;' therefor *','the n.argin of safety, ws defined in tle basis of any T.S., w + not reduced.
- )
-** SI-067 PERIODIC CALIB?Ai!ON OF RP! "".i[H - LMITS 1 AND 2 REV No. 004 This revision was made to coeply with SI-1, Appendix F, and to include the The SI has been revised to ir.clude finst hot channel calibration contained first hot channet calibration. This revision will also clear CAIS 86-529. In IMI-85-RPI. The remaining sections of IMI-85-RPI will be performed by SI-67. Previously, IMI-85-RPI met att T.S. requirements. ALL original requirements are stilt met. This revision did not increase the probability of an accident or malfunction and did not create a different type of accident. Because all T.S. requirements were met, the safety margin as defined was not reduced.
o* SI-067.1 PER'0DIC CALIBRATION OF THE RC3 POSITION INDICATION CHANNELS - UNITS 1 AND 2 REV No. 002 This revision incorporated the electrical calibration, cable connection This SI has been revised tn include att but the final hot calibration verification, and cold shutdown channet calibration sections formerly sections ccntained in IMI-85-RPI. The final hot calibration will be-retained in IMI-85-RPI, and steps to calibrate the bypass module. performed by SI-67. This procedure affects existing equipment only. This' procedure and SI-67 will perform all other secti ms previously performed by IMI-85-RPI, which met at1 T.S. requirements. Therefore, the method of-tefting has not changed, s.ti the margin of safety has not decreased. REV NO. 003 This revision removed calibration of, the bypass modules and corrected The testing and calibration of'the bypast modules are performed in tolerance on rod bottom bistables. This revision also removed verification IMI-85 RPI and are not required for this instruction. XA-55-48-28 actuates Page 53. 16 02/22/83 SEQUCYAH hUCLEAR PLANT 10 CF' %.59 1987 NRC ANN 8r ;ATING REr0RT CHANGES TO PROCEDu b ASCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
g of XA-55-48-28 and removed repeatability statements from ste.> 10, because from the same relay as the rod bottom bistable lignts. The lights are setpoints are not being checked, only indications. checked by this instruction and prove the associated relays are functioning property. This annunciator is verified to function during startip *en the rod banks are all off the bottom. There were no T.S. Setpoints or L. 4ts changed. The probability of an accident or malfunction was not increased, and the possibility for an accident or nelfunction of a type different.than previously evaluated was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
** St-068 FUNCTIONAL TEST Of CONTAINMENT SPRAY PUMPS AND ASSOCIATED VALVES - UNIIS 1 AND 2 (FREQUENCY 550 DAYS)
REV NO. 003 This revisien incorporated SR for CSP and automatic valve alignment from The testing methods did not change, and the margin of safety was not containment pressure high-high test signal. This was prevtcusly part of affected. SI-471 which has been cancetted.
** S1-071 DISSOLVED NITROGEN AND AIR CONCENTRATION IN UPPER HEAD INJECTION WTER-FILLED ACCUMULATORS - tmtTS 1 AND 2
.REV No. 009 On Data Sheet 1.0, the acceptance criteria of <80 SCF as the dissolved - This revision did not increuse the possibility of an accident ce nitrogen and air concentration in the UNI water-filled accumulator was malfunction of equipment. Thi*. revision was to formt the SI and to state added. Changed wording to correct various typographical errors. that it fully satisfies T.S. requirements. Sirre the instruction satisfies T.S. requirewents, the margin of safety was not f t:cbced.
** $1-072 CUARTERLY CHEMISTRY REQUIREMENTS - UNITS 1 AND 2 REY wo. 012 This revision cancelted SI-72. T.S. SR 4.11.1.3.2 has been eliminated.
Em
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g
- SI-078 POWER RANGE NEUTRON FLUX CHAkNEL CALIBRATION GY MEAT BALANCE COMPARISON (DAILY) - UNITS 1 AND 2 REV50. 010 This revisico added a reference section, revised the Data Package Cover The corrections in this revision made the procedure more consistent with Sheet for consistency with AI-4, corrected LCO numbers for consistency with plant Als and the T.S. It did not increase the possibility of an accident, each unit s T.S., added a prerequisite to obtain SRO permission to perform and the margin of safety was not reduced.
the test, and allowed performance of the test with an inoperable channel.
- SI-079 POWER RANGE NEUTRON FLUX CHANNEL CALIBRATION SY INCORE - EXCORE AXIAL IMBALANCE COMPARISON (MONTHLY) - UNITS 1 AND 2 REV No. 008 This revision added steps for performance of TI-36 and corrected figure 1 Th* addition of steps and correction of figure 1 enhanced and clarified the -
to reflect a more realistic incore computer output. Also added steps to methodology of the procedure. Satisfying LCO 3.3.3.2 ensured that source satisfy LCO 3.3.3.2 moveable detector system operability. data used to perform SI-79 was accurate. The probability of an accident was not increased and the possibility for an accident or metfunction of a different type was not created. The margin of safety was not reduced.
- SI-080 POJER RANGE NEUTRON FLUX CHANNEL CALIBRATION AND FUNCTIONAL TEST (QUARTERL* UNITS 1 AND 2 REV No. 011 This revision added SRs that are partially satisfied by this Si and added This revision did not change the meth6d of' testing or sequence cf events.
references to other instructions that completely satisfy SR 4.3.1.1.1.8.2 None of the T.S. setpoints or tolerences were changed. The probability of and SR 4.3.1.1.1.B.7. This revision also' clarified the acceptance criteria an accident was not increased, and the possibility for an accident or section and added reference to TI-54/54.2. malfunction of.a different type was not created. The margin of safety was not affected.
- SI-082 FUNCTIONAL TESTS FOR THE RADIATION MONITORING SYSTEM - UNITS 1 AND 0 REV NO. 013 This revision incorporated changes made by two separate ICFs (ICF 87-273 These ICFs did not affect the margin of safety. These changes were intent and ICF 87-135) changes and were incorporated. ICF 87-135 was incorporated so that SI-82 could be performed and would work as written. 2CF 87-273 was incorporated,
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SUMMARY
g ICF 87-135 clarified instruction step for measuring high voltage, added because the tolerance placed on RM-90-102 and -103 was too tight. This instruction step to clear att alarms before testing for malfunction eteros, tolerance was established, because RM-90-102 and -103 are GM tube-type and corrected window numbers for RM-90-103 and -126, and block switch detectors. The +/- 25 volts high voltage value tolerance is adequate since position for fiM-90-126. the GM tube plateau curves are fairly constant at the calibrated high vottage setting. This change corretts errors made by ICF-87-135. These ICF 87-273 changed tolerance on the calibrated high voltage valve for changes ensure the SI con be performed the w3y it was written and do not radiation monitors RM-90-102 and RM-90-103 from "As found" +/- 10 volts and alter the margin of safety. The probability of an accident or malfunction "As left" +/- 2 volts to "As Found" +/- 25 volts and "As Left" +/- 25 was not increased. volts. The tolerance originalty specified is for scintittation-type detectors and does not apply to the GM tube-type detectors. Radiation monitors 90-102 and 103 are GM tube-type cetectors.
** SI-082.2 FUhCTIONAL TEST FOR THE RADI ATION MONITORING SYSTEM - tmIT 2 REV NO. 006 This revision added vendor "CPM" values equivalent to T.*;. values. The T.S. allowable values specified in "CPM" were corrected to coincide with the vendor sensitivity plots s q lied under contract 92759. Since the "CPM" values are equivalent per vendor documentation, the margin of safety was not affected.
** SI-090.12 REACTOR TRIP INSTRUMENTATION FUNCTIONAL TEST OF DIFFERENTIAL TEMPERATURE /TAVG CHANNEL I, RACK 2 (T-68-2) - UNIT 2 REV NO. 003 This revision corrected deficiences in technical adequacy as evaluated the test methodology was unchanged. The revised procedure ensured that the using $1-1, Appendix F. This revision also combined IMI-99 with $1-90.12 toop performed its intended function by verifying additional input . to the and cancetted IM1-99. overpower dif ferentiat temperature and overtenperature dif ferential temperature setpoint calculators. The probability of an occurrence or the consequences of an accident were not increased. The possibility for an adcident or malfunction of a different type was not ireated, and the revision ensured that the T.S. requirements were fully satisfied.
~43-
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i
** SI-O R 32 REACTOR TRIP INSTRUMENTATION DIFFERENTIAL TEMPERA!URE/TAVG CHANNEL II, RACK 6 (T-68-25) - UNIT 2 REV No. 003 This revision corrected deficiencies in technical ade.juacy as evaluated The test methodology was unchanged. The revised procedure ensured that the using SI-1, Appendix F. This revision also comuined IMI-99 with $1-90.32 toop performed its intended function by verifying additional inputs to the and cancettus IMI-99. overpower dif ferential tenperature and overtemperature dif ferential tenperature setpoint calculators. The probability of an occurrence ,r the consequences of an accident were not increased. The possibility for an accident or malfunction of a different type was not created, and the revision ensured that the T.S. requirements were fully satisfied. " SI-090.42 REACTOR TRIP /ESF INSTRUMENTATION QUARTERLY FUNCTIONAL TESTS (RACKS 7 AND 8) - UNIT 2 REV NO. 002 This revision added applicable references, prerequisites, performance This revision did not increase the Fossibility of an accident, because any modes, and corrective action when "As found" data are not withir' desired T.S. that is covered remains the same. These changes are mainty tolerance. adninistrative in nature which ensure compliance with the T.S.
requirements.
'** SI-090.52 REACTOR TRIP INSTRUMENTATION FUNCTIONAL TEST OF O!FFERENTIAL TEMPERATURE /TAVG CHANNEL III, RACK 10 (T-68-44) - UNIT 2 REV C:3. 003 This revision corrected deficiencies in technical adequacy as evaluated The test methodology was unchanged. The revised procedure ensured that the using SI-1, Appendix F. This revision also conbined IMI-99 with SI-90.52 toop performs its' intended function by verifying additional inputs to the and cancet ted IMI-99. . overpower dif ferential tenverature and overtenperature dif ferential tenperature setpoint calculators. The probability of an occurrence or the consequences of an accident were not increased. The possibility for an accident or malfunction of a different type was not created, and the-revision ensured that the T.S. requirements were fully satisfied.
Page No. 20 02/22/83 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBE 0 IN THE SAR DESCRIPTION SAFETY
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j
- SI-090.72 REACTOR TRIP INSTRUMENTATION FUNCTIONAL TEST OF DIFFERENTIAL TEMPERATURE /IAVG CHANNEL IV RACK 13 (T-68-67) - UNIT 2 CEV NO. 003 This revision corrected deficiencies in technical adequacy as evaluated The test methodology was unchanged. The revised procecure ensured that the using SI-1, Appendix F. This revision also conbined IMI-99 with SI-90.72 toop performs it , intended function by verifying additional inputs to the and cancetted IMI-99. overpower differential temperature and overtemperature differential tewperature setpoint calculators. The probability of an occurrence or the consequences of an accident were not increased. The possibility for an accident or malfunction of a different type was not created, and the revisions ensured that the T.S. requirements were futty satisfied.
- SI-090.8 REACTOR TRIP INSTRUMENTATION MONTHLY FUNCTIONAL TEST (SSPS) - L,' NIT 1 REV No. 004 This revision incorporated consnents from the SI-1, A@endin F, added SR These revisions did not increase the probability of an accident. The 4.3.1.1.1.C.22.A, and added signofia in various points to docunent return changes did not change the intent or method of testing. They helped to to normat conditions. ensure compliance with T.S. and ensure adequate and proper equipment operation. The T.S. SRs were met, and no setpoint was changed; therefore, the margin of safety was not reduced.
- SI-090.82 REACTOR TRIP INSTRUMENTATION MONTHLY FUNCTIONAL TEST (SSPS) - Unit 2 REV No. 005 Revised the instruction according to SI-1, Appendix F. This revision added The scope and intent of this instruction did not change. The addition of SR SR 4.3.1.1.C.22.A revised surveitLance frequency, added return to normat 4.3.1.1.C.22.A was a documentation change only because the procedure has signoffs, added mechanical and technical equipment requirements, and 'always satisfied this SR. The method was not changed,'and no T.S.'was corrected various typographical errors. af f ected by the revision. No possibility of a new accident or malf unction -
was created, and the margin of safety was not decreased, t Mb
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** SI-093 REACTOR TRIP INSTPUMENTATION FUNCTIONAL TESTS CONDITIONAL 7 DAYS (PRIOR TO STARTUP) - UNITS 1 AND 2 REV NO. 010 This revision addressed T.S. interpretation 79, revised the reference The testing methods conform to NRC generic letters 83-28 and 85-09 and NCR section, added TSC points, and clarified the acceptance criteria. 79-4 and 79-5. This method does not increase the probability of an accident. The addition of TSC point verification increased reliability of computer information. No margin of safety was reduced.
- St-396 FUNCTIONAL TEST OF INTERMEDIATE AND POWER RANGE NEUTRON FLUX CHANNELS AND THE P-7 INTERLOCK - UNITS 1 AND 2 REV NO. 003 This revision removed the contents of the St, because SR 4.10.4.2 is a Removing the contents of this SI and rewriting it when soecial conditions conditional surveittance test that is required when the T.S. allows less exist do not reduce any margin of safety.
than four reactor coolant pumps running in modes 1 and 2 (LCO 3.4.1.1). This LCO will not be suspended unless required by special conditions or tests. If required by special conditions or tests, this surveillance test will have to be evaluated and rewritten to conform to the actual spectat test requirements. " SI-097.2 CALIBRATION OF AUXILIARY FEE 0 WATER FLOW RATE FOR REMOTE SHUTDOWN AND ACCIDENT MONITORING (550 DAYS) - UNIT 2 MEV No. 001 This revision corrected tolerances on flow loop F-3-142. The correction of these tolerances enhanced safety. It also ensured proper flow indication and proper calibration of the loop components. No T.S. criteria were affected by this change.
- SI-100.3 ANNUAL 125-v0LT VITAL BATTERY SYSTEM INSPECit0N - UNIT 0 REV NO. 000 This new instruction was written to fulfill SR 4.8.2.3.2.C.1, SR When the vital battery changes are inspected, the spare vital battery 4.8.2.3.2.C.2, and part of SR 4.8.2.4.2 which was formerly fulfilled by charger is removed from service. The probability of an occurrence or the'
$1-105. consequences of an accident or malfunction are not increased, and there is
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I no reduction in the margin of safety.
** S1-102 INSPECTION OF DIESEL CENERATORS - UNITS 1 AND 2 REV No. 007 This revision cancetted the instruction. It is being replaced by SI-102M This instruction has been cancelled and replaced by two more detailed
.and SI-102 E/1.5Y. instructions in new procedures, SI-102M and St-102E/1.5Y. These more detailed instructions do not increase the probability of an accident or malfunction and do not create any of a different type. Because the basis ~
of any T.S. remained unaffected, the margin of safety was not reduced.
** SI-102 E/1.5Y DIESEL GENERATOR (18 MONTHS) ELECTRICAL INSPECTIONS - UNITS 1 AND 2 oEV NO. 001 This revision cancelled this instruction. The manufacturer-recomended maintenance is not an SR. . Inspections are now ,
made on an IMI.
** SI-102 E/M DIESEL GENERATOR MONTHLY ELECTRICAL INSPECTION - UNITS 1 AND 2 REV No. 004 This revision added a reference to EMSL-A3o,' "Comon Mode Failure," added 'The intent of this instruction remains the same. The various reference an SR number to the procedure scope, and changed clarity note to step information was added to meet the requirements of SI-1. These changes did 6.4.4. not increase the possibility of an accident or malfunction of equipment.
The addition of reference information did not alter the T.S. in any way; therefore, the margin of safety was not reduced.
** SI-102 M DIESEL CENERATOR MECHANICAL INSPECTIONS - UNITS 0, 1, AND 2 LEV No. 001 This revision adJed a note to first perform the steps required white the The steps in the SI will be performed in a sequence that is most efficient engine is tagged out and attowed inspection of the oil filter check valves. to work schedules. ALL inspections will be performed as required.
Therefore, there will be no increase in the probability of an accident or
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the creation of an accident of a different type, because the results of the SI witt not be affected. Also, the basis of any T.S. will not be affected, and the margin of safety will not be reduced. SI-102 M/M DIESEL CENERATOR MONTHLY MECHANICAL INSPECTION - UNITS 0, 1, AND 2 LEV NO. 003 This revision deleted the inspection of internal fuel system during The fuel system internal manifold is inspected with the engine shutdown and operations at full load. the fuel system pressurized by the priming pump. The deletion of the inspection at full toad prevents opening the top deck covers at full load. Deletion of this inspection at full load did not increase the probability of an accident, because it is performed & ring shutdown. The possibility for an accident of a different type was not created, and the margin of safety, as defined in the basis of any T.S., was not reduced.
** SI-104 AUXILIARY BUILDING CRANE INTERLOCKS - UNIT 0 REV NO. 011 This revision clarified performance and applicable modes. Signoffs for unit The margin of safety from the previous revision was not altered by this 1 and unit 2 SE/SRO wete added, and a Deficiency Log was added. revision to the instruction. The enhancement changes in this revision only clarified the scope and added signof fs for deficiencies and ccennon equipment signoffs. The nurgin of safety, as defined in any T.S., was not reduced.
SI-105 VITAL BATTERY BANK AND NORMAL CHARGER PERFORMANCE TEST - UNIT 0 KEV No. 021 This revision incorporeted SR 4.8.2.3.2.F to increase procedure frequency No system Configuration chan9es were made tar this revision. The due to degradation. protability of an occurrence or the consequences of an accident were not increased. The possibility 'or en accident of a different type was not c r crit 41, mi t he avirgin (,f .a f et y w.. . rw,t nom e*l.
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I C SI-106 ICE CONDENSER - ICE BED - UNITS 1 AND 2 REV No. 011 This revision adheres to the requirement of St-1, Appendix F, and enhances The revisions to the instruction were for clarification and enhancement. the procedure. The revision removed the requirements for weighing the ice removed to provide access for the basket lift rig. The ice removed is considered negligible and will not affect the acceptance criteria for this St. Ihcref ore, the margin of mafety was not reduced and the possibility f or en accident or metfunction was not increased.
- 3 SI-108 ICE CONDENSER DOORS - UNITS 1 AND 2 REV No. 009 This revision conpties with T.S. SR 4.6.5.4.8 and SR 4.6.5.3.2.s. SR 4.6.5.3.2.8 requires an inspection of the intermediate deck door vent assenblies. The acceptance criteria were revised conservatively to attow for the accuracy of the measuring and test equipment to ensure T.S. values .
were not inadvertently exceeded. This change did not affect safety as previously evaluated and served to maintain the levet of safety. No new accident or matfunction was created.' co 51-112 TESTING AND SETTING OF SETPOINT OF PRESSURIZER SAFETY VALVES - UNITS 1 AND 2 REV NO. 009 This revision incorporated ANS!/ASME OM-1-1981 requirements for testing of ANSI /ASME OM-1-1981 was writteo specifically for .in-service testing of pressurized safety valves and deleted requirements specified by power test safety valves and is a source docment improvement as compared witti the codes 25.2 and 25.3. power test codes. The probability or consequences of an accident were lessened by inptementing OM-1-1981 requitements. The possibility for an accident or malfunction of a different type was not created. The margin of
- safety was not reduced.
~49- .
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j
- 58-114.1 ASME SECTION XI IN-SERVICE INSPECTION PROGRAM - UNIT 1 REV NO. 008 This revision incorporated the use of a CAOR in accordance with SP T.S. This change incorporated the use of a CAOR in accordance with NOAM, Part F, 861127D and corrected various typographical errors in the procedure tables. Section 2.16, and AI-12 as additional reporting and tracking requirements.
It did not increase the probability of an accident or malfunction of equipment and did not alter the scope, intent, or T.S. The margin of safety was not reduced. " SI-114.2 IN-SERVICE INSPECTION PROGRAM FOR TVA SEQUOYAN NUCLEAR PLANT - UNIT 2 ONLY REV NO. 009 This revision incorporated the use of a CAOR in accordance with SP T.S. This change incorporated the use of a CAOR in accordance with NQAM, Part F, 870119E and corrected various typographical errors in the procedure tables. Section 2.16, and Al-12 as additional reporting and tracking requirements. It did not increase the probability of an accident or malfunction of equipment and did not alter the scope, intent, or T.S. The margin of safety was not reduced.
- 'S1-117 ERCW SYSTEM OPERATING - UNITS 1 AND 2 REV NO. 003 This revision included changes of organizational designctinn from QA to This revision was for clarification and flow indicator inclusions. The flow CE&C on the Data Package Cover Sheet and added flow indicators 1-F1-67-222, indicator inclusions give the performers more positive indication that the 2-FI-67-222, and 0-FI-67-226 to te used in conjunction with the pressure ERCW pumps are delivering flow to the headers. With pressure only it could' indicators. Changed notification from SE to SRO. be questionable, because the Pis are on the discharge of the ptmps, and valves could be isolated downstream, thus blocking flow into the auxiliary building. These revisions and inclusions did not increase the probability of an accident or malfunction, nor decrease the sorgin of safety.
50-- -
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l
- SI-118.1 TURBINE-DRIVEN AUXILIARY FEEDWATER PUMP AND VALVE AUTOMATIC ACTUATION - UNITS 1 AND 2 REV No. 015 This instruction was revised to conply with SI-1, added signof fs to verify The revision did not change the scope, intent, methodology, or result of~
turbine driven AFW p m p off and in auto prior to initiating each test this test. Therefore, the probability or consequences of accidents or signat, and corrected acceptance criteria for low-tow steam generator levet malfunction were not increased. This revision did not create any new test. accidents or malfmetions, and the margin of safety was not decreased.
- SI-119 ERCW AUTO ACTUATION FROM AN SI SIGNAL - UNIT 0 REV NO. 009 This revision changed unit designation f rom 1 and 2 to 0, corrected These corrections did not change the intent or technique of this test in typographical errors (St should have been safety injection), changed any manner. The margin of safety was not redated assi the probability for notification from SE to SRO, and included organizational change from QA to an accident or malfunction of equipment was not increased._This test did ,
QE&C. not create a new type of accident or malfunction.
- SI-127 RCS AND PRESSURIZER TEMPERATURE AND PRESSURE LIMITS - UNITS 1 AND 2 REV NO.'015 This revision was made to isptement corrections needed to resolve technical The evaluation of past performances of $1 127 with the technical-inadequacies identified by 51-1, Appendix F, and to ensure titeral inadequacies indicated no violation of the plant T.S. Ensuring Literal compliance with the plant T.S. compliance with the plant T.b. did not increase the probability of an occurrence or the consequences of an accident or malfunction of equipment.
The possibility of an accident or malfunction of a different type was not created, and the margin of safety, as defined in the basis of any T.S., was not reduce <*.
- SI-128 EMERGENCY CORE-COOLING SYSTEMS RESIDUAL HEAT REMOVAL PUMPS - UNITS 1 AND 2 REV NO. 019 This revision cancelled this instruction. All T.S. requirements have been transferred to St-128.1, SI-128.2, SI-128.3, SI-128.4, and SI-128.5 for testing each ptsrp.
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l
** $1-128.2 RESIDUAL HEAT REMOVAL PUMP 1A-A PERFORMANCE - UNIT 1 REV No. 000 This new instruction was written to replace SI-128 and to separate the There have been no changes in the method of testing or acceptance criteria.
testing of each ptmp to an instruction by itself for clarity and The margin of safety, as defined in the basis of any T.S., was not reduced. enhancement. All requirements of SI-128 have been incorporated. Test instruments that meet the accuracy and range requirements of ASME, Section XI, have been added. 4 ** S1-128.3 RESIDUAL HEAT REMOYAL PUMP 19-8 PERFORMANCE - UNIT'1 REV NO. 000 This new instruction was written to replace SI-128 and to separate the There have been no changes in the method of testing' or acceptance criteria. testing of each ptmp to an instruction by itself for clarity and The surgin of safety, as defined in the basis of any T.S., was not reduced, enhancement. All requirements of $1-128 have been incorporated, and test instrunents that meet the occuracy and range requirements of ASME, Section MI, have been added.
'** SI-128.4 RESIDUAL HEAT REMOVAL PUMP 2A-A PERFORMANCE - UNIT 2 REV No. 000 This new instruction was written to replace SI-128 and to separate the There have been no changes in the method of testing or acceptance criteria.
testing of each ptmp to an instruction by itself for clarity and The margin of safety, as defined in the basis of any T.S., was not reduced. enhancement. All requirements of S!-128 have been incorporated, and test instruments that meet the accuracy and range requirements of ASME, Section XI, have been added. .
- ** SI-123.5 RESIDUAL HEAT REMOVAL PUMP 28-8 PERf0RMANCE - UNIT 2 CEV No. 000 This new instruction was written to replace SI-T28 and to separate'the There have been no changes in the method of testing or acceptance criteria.-
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testing of cach punp to an instruction by itself for clarity and The margin of safety, as defined in the basis of any T.S., was not reduced. enhancement. All requirements of S!-128 have been incorporated, and test instruments that meet the accuracy and range requirements of ASME, Section XI, have been added.
- SI-131 THERMAL POWER DE!ERMINATION DURING PHYSICS TESTING IN MODE 1 - UNITS 1 AND 2 REV NO. 002 This revision deleted requirement 3.2.1 (Axial flux Difference) and added a The deletion of the requirement 3.2.1 (Axial Flux Difference) results in reference section to the scope. the nonperformance of the requirement for the power physics test using power range instrumentation. This deletion did not increase the probability of an accident and did not reduce the margin of safety in any manner.
- c. Sg.135 EGTS CLEANUP SUBSYSTEM AUTOMATIC START - UNIT 0 REV NO. 010 This revision to the SI changed notificatico requirements from SE to SRO, The corrections and procedural clarifications in no way affect the intent, added a T.S. SR reference, clarified system operating instructions scope, or result of this test. They did not increase the probability of an reference,'and added signoff for verification of system operating accident or matfunction and did not create any new type of accident. The instructions and return to normal per attached copy. margin of safety, as defined in the basis of any T.S., was not reduced.
- Q St-136 ECTS CLEANUP SUBSYSTEM FUNCTIONAL TEST - UNIT 0 REV NO. 009 This revision changed unit designation f rom units 1 and 2 to tritt 0, The changes made are for clarification and compliance with SI-1, Appendix changed notification from SE to SRO, made organizational corrections from F. They did not affect the scope or intent of this procedure in any CA to CE&C, made data sheets for f an AA and BS the same, and corrected manner. The probability for an accident or malfunction of plant eqJipment various typographical errors. was not increased, nor did the changes create a new type of accident. The changes did not affect the T.S. The margin of safety was not reduced.
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g
** S t - 137.1 REACTOR COOLANT SYSTEM - UNIDENTIFIED LEAKAGE MEASUREMENT - UNITS 1 AND 2 REY NO. 014 This revision added M&TE documentation, replaced unvalidated methodology, The intent of this procedure was unchanged, and no new system Lineups or reorganized and restated for clarity, changes were initiated. There was no increase in the probability of an accident or malfunction of equipment. All T.S. requirements and regulatory guidelines were met- therefore, there was no degradation of the margin of safety.
** $1-137.2 REACTOR COOLANT SYSTEM WATER IN'dNTORY - UNITS 1 ANO 2 REV NO. 018 This revision added a reference section, incorporated signoffs into the No accident or malfunction of a different type than previously analyzed was data sheet, and rounded off conversion factors to comply with the required created. The margin of safety, as defined in the basis of any T.S., was accuracy of the procedure. Also adoed the requirement to perform SI-137.2 not reduced.
if the acceptance criteria of SI-137.1 are not met. This ensures compliance with SR 4.4.5.2.1.9 and SR 4.4.6.2.1.6. e
** $1-137.3 MEASUREMENT OF THE CONTROLLED LEAKAGE TO THE REACTOR COOLANT PUMP SEALS - UNITS 1 AND 2 ' REV No. 004 This revision was made to require, in addition to the explicit T.S. Requiring verification of the minimum 100 psid pressure drop property requirement, verification of the SON specific bases for the SR. The change augments the surveillance and ensures that both the explicit T.S.
required the pressure drop across the seat injection lines to be verified requirements and the basis for the SR are satisfied. Adjustment of the equal to or greater than 100 psid during performance of this test. seal back-oressure valve to reach desired pressure drop prior to checking Guidance is given to allow adjustment of the RCP seat back-pressure valve, maxinun flow rate does not alter the validity of the surveillance. FCV-62-89, to assist in obtaining the equal to or greater than 100 psid Erhancement of the surveillance ensures ECCS capability will be consistent pressure drop. with that assuned in the safety analysis. These changes did not increase the probability or consequences of an' accident or reduce any sargin of safety. 54-- L_.-__.-._.___._ _ _ _ . . _ _ _ . _ - . . . _ . _ . _ _ _ . _ _ _ _ _ _ _ . _ _ - _ - _ _ _ _ _ _ _ _ .
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SI-138 CONTAINMENT SPRAY - SPRAY NOZZLE TEST - UNITS 1 AND 2 EEV No. 006 This revision corrected various technical details and provided conformance This instruction ensures that the containment spray nozzles are functional, with SI-1, Appendix F. There is no modification to permanent plant equipment laptemented by the performance of this instructi e. The proced2re ensures operability of T.S. equipment in accordance with T.S. guidelines and frequency. There was no ' margin of safety degradation and to increase in the probability of an accident or malfunction. SI-141 RESULTS FROM TEST LABORATORY ON CHARCOAL TEST CANISTER - UNITS 1 AND 2 REV NO. 009 This revision included T.S. requirements for modes and frequency, added a Adding information to the procedure for reference did not increase the reference, and contined instructions with data sheets. probability or the consequences of an accident, and it did not create a different type of occurrence. Adding information for reference had no affect on the T.S. The margin of safety, as defined in the basis of any T.S., was not reduced.
^
** SI-149 AUXILIARY BUILDING CAS TREATMENT SYSTEM VACUUM TEST - UNIT 0 REV NO. 014 This revision r W a note stating that the equipment is common to both Adding consnon equipment note, permission requirement,~ and clarification did units, added a requirement for unit I and unit 2 SRO permission to perform not increase the probability of an accident, and it did not create a test, and added a sentence to clarify the formula. different type of accident. Cecause the T.S. remains unaltered, the margin of safety was not reduced.
** St-151 Six MONTH TEST REQUIREMENT ON ELECTRIC HYDROGEN RECOM81NER SYSTEM - UNITS 1 AND 2 -
REV NO. 012 This revision changed approvat and verification from SE to SRO, deleted this revision in no way aff6cted the intent or scope of the instruction; I
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j superfluous information, corrected organizational designation from QA to therefore, the probability of an accident or malfunction did not increase. OE&C, and clarified the instruction in accordance with SI-1, Appendix F. The changes did not create a new type of accident or malfunction. Since the clarification did not alter any 1.S., the margin of safety was unaffected. REV NO. 013 This revision clarifiew* the procedure steps and the acceptance criteria. The clarifications made to the instruction ensured that the equipment was tested to satisfy the scope of the instruction. The probability or consequences of an accident or malfunction were not increased. The possibility for an accident or malfunction of a different type was not created, and the margin of safety, as defined in the basis of any T.S., was not reduced. o* St-152 $HUTOOWN MARGIN SPECIAL TEST EXCEPTION - ROD OROP VERIFICATION - UNITS 1 AND 2 REV NO. 002 This revision made the test more applicable to actual special test Compliance with plant design requirements and special test requirements did exception requirements and current plant design requirements if the test is not increase the probability of an accident. This revision made the $1-ever performed because of relaxation of the shutdown margin requirement, more applicable to the SR d ich La designed to ensure that no margin of safety is reduced. c* S1-155 REACTOR COOLANT FLOW VERIFICATION - UNITS 1 AND 2 , REV NO. 012 This revision added data sheets for recordinn voltages of the RCS flow This revision did not affect any systems in such a way as to increase the transmitters and requires the St.to be performed concurrently with TI-2 and . possibility of an unanalyzed accident. The margin of Safety is increased 5t-246. by ensuring the RCS flow transmitters are in the proper sensitivity. band and by requiring $1-246 to be performed concurrently.
\.
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j
** St-159.1 PERSONNEL AIRLOCK OPERABILITY AND CVERALL LEAKAGE TESTS - UNITS 1 AND 2 REV NO. 010 This revision clarified the instruction, corrected discrepancies, clarified The clarifications and corrections made by this revision did not change the the calculation procedure, ar.J corrected errors discovered by the SIReview intent or function of the procedure. The method of testing and the Task force. Also, it has tested the ranges / accuracies of test equipment, acceptance criteria were not altered by this revision. The timit of-made the data sheet more detailed, and included additional signoffs, teakage and the test frequency were not changed. Therefore, the.
probability of an accident or matfmetion was not increased, no new accidents or malfunctions were introduced, and the margin of safety was not reduced.
** SI-15).2 AIRLOCK RESILIENT SEAL LEAK RATE TEST - UNITS 1 AND 2 REV NO. 012 This revision clarified the procedure, specified ranges and accuracles for The actual testing method has not changed from the previous revision of test equipment used in performing the procedure, and included correct this procedure. Containment integrity is maintained and not affected by references used in preparing the procedure. The value used in the performance of this test. The acceptance criteria value change ensures acceptance criteria was revised f rom 2.37 SCFH to 2.25 SCFN. that T.S. timits are met. ** $1-159.3 CONTAINMENT HYDROGEN ANALY2ER SYSTEM LEAKAGE IEST REV NO. 005 This revision deleted references to procedures that have been cancetted, At least one train of the hydrogen analyzer is ensured operable at att added other references, clarified instruction calculations, and added LCO times, and containment integrity is maintained. The probability of an requirements to the acceptance criteria. accident was not increased, and the possibility of an accident or malfunction of a different type was not created. The margin of safety as defined in the T.S. was not reduced.
en $g.g59.4 PERSONNEL AIRLOCK OPERASILITY - UNITS 1 AND 2 EEV NO. 002 This revision deleted steps that notified the UO prior to entry into The intent remained unchanged, and the instruction is still technically
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g contairment neuf added extra wheets to the irmtruction so that enic 51 gerf oemed in the Leme namner. There was no increene in the gu t4mtallity of package could cover both airlocks on one unit. an accident or malfunction. The margin of safety was not reduced, because the T.S. remained unchanged. C* S1-159.5 LEAK RATE IEST ON CONIAINMENT PRESSURE INSTRUMENTATION - UNIIS 1 AND 2 REV NO. 000 This revision included test methods and data sheets necessary to quantify The procechare is still performed in the same manner; however, it is now teakage f rom the containment pressure instrunentation tested ander this clearer and provides for quantification of leakage. The probability of an procedsre. This also made provisions to add "As Found" teakage to the occurrence or the consequences of an accident or metfunction were not total integrated contairuient teak rate. increased. The possibility for an accident or matftoction of a different type was not created. The quantification of teakage ensures compliance with the T.S., and the margin of safety was increased.
- J $1-160 PRIMARY CONTAINMENT LOCAL LEAK RATE
SUMMARY
- UNITS 1 AND 2 REV NO. 004 This revision added the RHR spray valve's teskage to the inventory leakage the revisions affected no equipment or components within the plant. The requirements and added provisicns to keep a rtoning total of Led soe procedure is used only to keep a current suunary of contairment Leakage associated with containment integrated leakage rates. 'This revision also rates. No new conditions that could affect safety were created. The deleted ERCW valves's leakage from inventory requirements and changed limiting factors (values) for containment teakage as delineated in the I.S.
acceptance criteria value for containment spray valves inventory leakage have not changed. The SI still provides for the same margin of safety. requirement.
- $1-162.2 SNUBBER FUNCTIONAL TESTING (HYDRAULIC AND MECMANICAL) - ll NITS 1 AND 2 REV No. 005 This revision provided hydrautic snubber seat life history and clarified This revision did not reduce the margin of safety. It strengthened the mechanical snteber functional testing methods. snubber program and increased the margin of safety, because it provided a stronger in-service inspection program as defined in T.S. 3/4.7.9. -This revision did not increase the possibility of an accident, because the
~
Page M. 34 '02/26/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAf E T Y St>94ARY changes enhanced compliance with FSAR. REV NO. 006 This revision was made in accordance with SI-1, Appendin F. This revision This revision did not alter the equipnent's design or change the FSAR and also added test method considerations for testing the targe mechanical T.S. requirements. The probability of an occurrence or the consequences of snutbers and hydraulic snubber seat service-life sonitoring program. an accident or malfunction incre not increased, and the possibility for en accident of a different type was not created. The revision strengthened conpliance to T.S. 3/4.7.9 by enhancing at t snubber testing SRs.
** SI-164 TESTING SETPOINT OF SAFETY AND REtIEF VALVES (ASME, SECTION Mt. CATEGORY C VALVES)
REV NO. 009 This revision was made to implement ANSI /ASME OM-1-1981 in accordance with This revision enhanced the safety and relief valve test program.- The TWA memo L44 861212 808 instead of power test codes. revision did not affect the method of safety vatve operation and did not change the method of verifying valve operability. No defined margins of safety are applicable for the valve addressed by this St. The set pressure specifications for these valves remain unchanged.
** SI-1*5 CHANNEL FUNCTIONAL TEST OF SIS ACCUMULATOR TANC WATER LEVEL AND PRESSURE INSTRUMENTATION (MONT ILY) - LMITS 1 AND 2 REV h0. 008 This revision deleted the requirement for date-taken signature on att data The scope a d intent of this instruction have not been altered by the sheets and added rack number identification in step 7.11.6. deletion of the regairement for data taken signatures and the addition of a rack identification. This revision did not increase the p obability of an accident, d:d not create an accident of a different type, and did not alter-any T.S. Tae margin of safety was not reduced. ** SI-166
SUMMARY
OF VALVE TESTS FOR ASME, SECTION XI
- UNIIS 1, 2, AND COMMON REV NO. 011 This revision divided the in*truction into parts A, B, C, and D for the This reorganization change did not alter any Section XI code requirements purpose of reorganizing the $1-166 valve test program and clarifying- and did not increase the probability of an accident or the malfunction of
l Page No. 35 . l 02/32/58 l SEQUOYAN NUCLEAR PLANT ( 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN T"E SAR DESCRIPTION SAFETY StieARY g Section XI code requirements. In addition, part D contains an appendix equipment. Since this revision did not impact or a*.ter any T.S., the margin containing data sheets for stroke testing att category "A" and "B" valves. of safety was not redJced.
** SI-166.01 FULL STROKING OF CATEGORY "A" and "d" VALVES DURING OPERAT*0N - UNITS 1 AND 2 REV NO. 037 This revision removed data sheets and replaced them witti St .66.6, Valve This reorganization of the instruction did not alter Section XI code Checklist. Individual valve data sheets that will be attached to the Valve requirements and did not ippact any T.S. The probability of an accident Checklist are now in SI-166. or malfunction was not increased, and the margin of safety was not redJced.
"O SI-166.01.1 FULL STROKING OF CATEGORY "r" AND "S" VALVES REQUIRED It ALL MODES - UNITS ., 2, AND COMMON RiV NO. 000 This is a new instruction for futt-strde testing Section XI, Category "A" This change did not alter any Section XI code requirements, and the T.S.
and "B" valves, once per quarter while in any mode. This new instruction response time for safety-related valves within#the instruction remained the also reorganized entire SI-166 valve test program to clarify Section XI same. The probability of an accident or malfunction was not increased, and code requirements and to improve the test procedure format. the margin of safety was not reduced.
*0 SI-166'.02 PARTI AL STROKING OF MAIN STEAM ISot ATION VALVES DURIgG OPERATION - UNITS 1 AND 2 REV NO. 007 This revision deleted the individual valve data sheets from SI-166.2 and This teorganization of the instruction did not alter Section XI code -
placed them in SI-166. The valve checklist in SI-166.2 will specify which requirements and did not inpact any T.S. The probability of an accident or data sheets must be putted from SI-166 for a performance of $1-166.2. malfunction was not increased, and the margin of safety was not reduced.
$1-166.03 FULL STROKING OF CATEGORY "A" AND "B" VALVES DURING COLD $HUTDOWN - UNITS 1 AND 2 REV e60. ON This revision deleted the individu.*t valve data sheets from SI-166.3 and This reoraanization of.the instructicri did not alter Section XI code peaced them in 51-166. The valve checklist in $1-166.3 will specify which requirements and did not irpact any T.S. The prehability of an a:cidant or-data sheets must be putted from SI-166 for a performance of SI-166.3. matforiction was not increased, and the margin of. safety was not reduced.
l { l l Page No. 36 l 02/22/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANCES TO PROCE00RES AS DESCRI8E0 IN THE SAR OESCRIPTION SAFETY
SUMMARY
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** SI-166.03.1 IULL STROKING OF POWER OPERATED VALVES REQUIRED OPERABLE DURING ALL MODES - UNITS 1 AND 2 REV No. 000 This new instruction is for futt-stroke testing Section XI, Categories "A" This instruction did not alter any Section XI code requirements, and the and "B" valves, once per quarter white in cold shutdown. This new T.S. response times for these valves remained the same. The probability of instruction also reorganized entire SI-166 valve test program to clarify an accident or matfunction of equipment did not increase. The T.S.
Section XI code requirements and to improve tei,t procedure format. remained unchanged, and the margin of safety was not affected. SI-166.03.2 FULL STROKING OF RHR VALVES FCV-74-1 AND FCV-74 UNITS 1 AND 2 REV NO. 000 This is a new SI for the full-stroke testing of Section XI, Category "A" This instruction did not alter any Section XI code requirements, and the RNR valves FCV-74-1 and FCV-74-2, during startup, shutdown, and cold - T.S. response times for these valves remained the same. The probability of shutdown. This was necessary because of a reorganization of the entire an accident or matfunction of equipment did not increase. The T.S. SI-166 valve test program to clarify Section XI code requirements and to remained unchanged, and the margin of safety was not affected. improve test procedure format.
** SI-166.06 TESTING OF CATEGORY A & 8 VALVES AFTER MAINTENANCE OR UPON RELEASE f ROM MOLD ORDER - UNITS 1 AND 2 REV NO. 022 This revision removed data sheet and replaced it with SI-166.6 valve This reorganization of the inGtruction did not atter Section XI code checklist. Individual valve data sheets are now in SI-166 end will be requirements and did not impact any T.S. The probability of an accident or-attached to the valve checklist. malfunction war % t increased,' and the margin of safety was not reduced.
" SI-166.03 INCREASE 0 FREQUENCY TESTING OF CATEGORY "A" AND "B" VALVES - UNIIS 1 AND 2 REV NO. 006 This revision rr.aoved the data sheet and replaced it with 51-166.6 valve This reorganization of the instruction did not alter Section XI code checklist. Individual valve data sheets are now in St-166 and wilt be requirements .nd did not irpact any T.S. The probability of an accident or attached to the valve checklist. malfunction was not increased, and the margin of safety was not reduced.
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SUMMARY
** SI-166.12 SIS /RNR/UN! CHECK VALVE OPENING TEST - UNITS 1 AND 2 REV NO. 013 This revision was made to require the flow rates used in the T.S. The test method was not changed. The revision required additional flow to meet nusters listed in the T.S. and to meet NRC requirements in the ASME, Section XI, pump and valve safety evaluatim repurt. The prteability of an occurrence or the consequences of an accident or malfunctior,were not increased, and the possibility for an accioent of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
** $1-166.21 FULL STROKING OF THE COMMON ERCW AND CCS CATEGORY "A" AND *B" VALVES DURING OPERATION - UNIT 0 REV NO. 012 This revision deleted the individual valve data sheets from 51-166.21 and This reorganization of the instruction did not alter Section XI code placed them in 51-166. The valve checklist in SI-166.21 wilt specify which requireuents and did not ispect any T.S. The probability of an accident or data sheets sust be putted f rom SI-166 for a performance of $3-166.21. metfunction was not increas.ed, and the saargin of tafety was not reduced.
** St-166.22 SAFETY INJECTION CHECK VALVE TEST DURING COLD SHUTD("A - UNITS 1 AND 2 REV NO. 009 This revision added references and precautions, e4 ated d Data Package Cover The restriction of addi sure than 10 gations of demineralized water to Sheets, rewrote the requirement section, and specified that no more than 10 the SIE eni not require the cafety injection pianos to run on recirculation.
get tons of deeineralized water be added to the SIS. The reestivity was not increased enough to require the ptanps to be run. These changes made the instruction more conservativ e. The probability of an' . accident was not increased, and thr possibility of an accident or, matfunction of a different type was not created.
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- SI-1M.23 ERCW CHECK VALVE TEST DURING COLD SHUTDOWN - WiliS 1 AND 2 REV NO. 004 This revisi m added references, reworked the requirement section, Making the changes listed in the change description did not increase the incorporated the data shcets into the instructions, updated the Data probability of an accident or malfunction and did not reduce the margin of Package Cover Sheet, added steps to remove and replace pipe caps, added safety, as defined in the basis of any T.S.
statement about SI 158,1 being perforord if the valves fait, added that a work request be writtert if they fait, and added unit, mode, and date to top of data sheeth. " $1-166.24 ERCW CHECK VALVE TEST DURING OPERATION - UN1?S 1 ANO 2 REV 20. 004 This revision conbined the instructions and data sheets, added a statement Adding the precaution stating that if the unit is in modes'1-4, the removat about initiating a work request to remove and replace the pipe caps, of the pipe caps requires compliance with LCO 3.6.1.1 to maintain revised the Data Package Cover Sheet, and added references and contairunent integrity, and adding the precaution requiring the pipe caps to prerequisites. It added a precaution which states that if the unit is in be returned to their "At Found" position no later than one hour after they modes 1-4, the removal of the pipe caps regJires compliance with LCO were initially taken off, increased the margin of safety. 3.6.1.1 to maintain centainment integrity. This revision was made to correct deficiencies in technical adequacy.
- SI-166.26 CCnONENT COOLING UAl[R CHECK VALVE TEST DURING OPERAi!ON - UNITS 1, 2, AND COMMON LEY NO. 005 This revisios; clarified the instruction by combining the instruction Bringing this instruction into compliance with SI-1, Appendix F, by section and tne data sheets, making the test description clearer, updating combining the instructions and data sheets, clarifying the test the references, and artjing signof fs for both SROs and 00s. This brought- description, updating the references, and adding SRos and 00s signoffs, did the instruction into conpliance with SI-1, Appendia F. not increase the possibility for an accident or s.alfunction not previously evaluated in the SAR. These changes did not involve any 1.5. The margin of safety was not reduced. ,
1 Page No. 39 02/26/88 SEQUOVAN NUCLEAR PLANT 10 CFR 50.59 1987 MRC ANNUAL OrtRATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SM E TY SUMMAR f i S8-166.27 PRIMARY WATER CHECK VALVE TEST DURING COLD SHUTDOWN - UNITS 1 AND 2 REV No. 005 This revision changed the reference section, cont >ined the data sheets and The possibility for an accident or malfunction of a different type other instructions, corrected gransnatical errors, and added a statement about the than any previously evaluated in the SAR was not created by revising the T.S. applicable modes of this St. These changes brought the St into ref erences, requirement section, containing the da;a sheets and compliance with the St-1, Appendin F. St-1 W may also be performed to instructions, and correcting gransnatical errors. If SI-158.1 is performed futfitt the requirements of this St. In lieu of this test, it is to be noted on the Da'ta Package Cover Sheet of this test. No T.S. was changed or affected by this instruction. The margin of safety was not reduced. St-166.30 VCT CV VALVE TEST DURING OPERATION (62-504) - UNITS 1 AND 2 REV No. 002 This revision changed the format of the instruction to a format censistent Valve 62-502 is normatty closed. The valve is not operated in any way. It with other sis and added normatty closed valve 62-502 to the initial system is only verified in its proper position.' This step is being added as a lineup verifications. precautionary measure to ensure minimet water loss during testing. Changing the format of the procedure brings this instruction in line with other $1 formats. Because there is no change in valve alignment and valve 62-502 is <erified closed, the possibility of an accident or malfunction of a different type has not been increased. Because valve 62-502 is maintained closed, the margin of safety, as defined by T.S., was not rMaced.
** SI-166.31 FEEDWATER CHECK VALVE TEST DURING COLD $NUTDOWN - UNITS 1 AND 2 .
REV No. 002 This revision added steps to record steam generator tevet before the test - The test method has not changed. This revision has made the procedere more and after waiting 30 minutes. It also added acceptance criteria of less conservative in verif ying that the check valve closes. The probability of than a 5 percent drop in 30 minutes. an accident or matfunction was not increased, and the possibility for an 1
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SUMMARY
defined in the basis of any T.S., was not reduced. SI-166.35 UH1 CHECK VALVE OPENING TEST DURING REFUELING OUTAGE - UNITS 1 AND 2 REV NO. 003 This revision changed the forsut in accordance with $1-1 and included This test is performed after the upper head injection spool pieces are actions that are to be taken if valves fait the test. It also added removed and the valves are exercised af ter being removed f rom the system. signoffs for att prerequisites. The valves are tested when they are not required to tee operable. Because no changes were mede m t!.e performance of the test,' the probability of an accident or malfunction was not increasuf, and the margin of safety was not reexed.
- SI-166.36 DIESEL STARTING AIR VALVE TEST - UNIIS 1, 2, AND COMMON REV NO. 006 This revision was made to attow testing of only two valves per D/G start. The probability of an occurrence or the consequences of an accident or The other two starting motor sets are isolated to ensure the D/G starts metfunction of equipment were not increased. The procedure did not cause with the two air start valves being tested, any new series of events not previously evaluated. The eergin of safety, as defined in the basis of any T.S., was not reduced.
SI-166.38 INSPECTION OF DIESEL GENERATOR ERCW DISCHARGE CHECK VALVES - UNIIS 1 AND 2 REY NO. 003 This revision deleted system line m prior to inspection. detettd System tirg prior to volve inspection was accomplished by requiring that verification of flow af ter valve ine.pection, and added scoptwwe tr6teria. a cIcarsence te establishnt in accord..nce with AI 3. Full flow through each check, valve is verified quarterly by 51-166.45. These changes did not create any new occioent scererlos.
- St-1M.40 PkESSURIZER PORV AND BLOCK VALVE OPERASILITY IEST - UNIls 1 AND 2 RE*J No. C31 This revisiert removed data sheets and specific test instructions and placed This change did not alter any Section XI code requirements. Reorganization
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SUMMARY
g then in a single instruction, SI-166. This clarified Section XI code of this instruction did not create a new accident or malfunction, because recpirements and improved test procedure format (part of SI-166 series Section XI code requirements have not been af fected. The P0RV i S. was not rewrite). This also removed the 96-hour review requirement on the Data impactedbythischange,andthemarginofsafetywasnotreducQ Package Cover M eet. This requirement applies only to Section XI pi g tests. ,
** St-166.41 REACTOR NEAD VENT VALVE STROKE TEST DUR,NG A REFUELING 0;,AhE _ UNtis 1 AND 2 ~
REU NO. 000 This is a new instruction to stri,ke test the reactor head <ent system block The reactor head vent system valves will be esercised in mode 5 with RCS and throttle valves to satisfy the ASME, Section XI, valve test pressure sufficiently high to effect a blowdown. This will not increase x requirements. Valves will be timed remotely and tested acoustically to the probability or consequences of an accid &t since isolation capability I verify that remote indicators accurately reflect vetve operation for each is maintained during testing. (Block valves can be c!csed whit'e throttle valves are stroked and vice verse.) Themarginofseietywillnotbe reactor operator. e affected, because the system is designed to vent noncondensibles from the tg;per head regim to promote natural circulation for .kci-jents that might m occur in modes 1, 2, or 3. Exercisitx the 7tves wili 71ct' Create M _ # manalyzed condition, since the systa d espSte cf being isolateC in e' event the valves fait. Of g
** SI-16dL45 FULt. STROKING OF THE DIESEL CENERATOR ERCu CNECK VALVES - UNITS 1, 2, AND COMMON i aEV No. OC.s this is a new instruction to futty stroke the 0/G ERCW check valves. The normat and alternate cooling water paths will be checked in the
, designed alignment to ensure that there is no blockage from the check .j valves binding. Because the designed aligrunent is used, there is no ' ,
increase in the probability of an accident. .The designed alignment is used - '
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and checked to verify that it can perform its function._The possibility of p __ , - - a'dif ferent ty.)e of accident is not created. It is also be:ng tested to
) ' f s ensure that the margin of safety, as defined by T.S., was not reduced.
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__L-f* ss 1(4.46 kORP.AL CRARGING LINE CMcCK VALVE ILST DURIri COLD SMIIDOWN (C1) - UNITS 1 ANO 2 ~ m -~ - . . \, - (, - w. I:2V CJ, 000 This instruct,gn verifies ctosing of the ncy chargir1 tine check valve This instructionpriptemented the mitwenOnQto the h&C concerning the . 62-543 in the CYCS. 1his wit t be accompt ished ty applying presvere f ram a ALME, $cction XI, m and'vstve program. w_ test rig to close the check valve, m s
** SI-1 J FIRE HEADER VALVE LINEUP INSPECTION - UN175 O. 1, AND 2 '
REV NO. 019 This revision deleted att non-T.S. valves and dropped locked requiremmt The proirdty of an occurrence or the consequences of an accider.t or f or valves which are now double verified as beles seated. malfunction were not increased. .The possibility for an accident or , matftrictich cf a dif ferent type was not created. The margin of safety is enhanced by the sealing of att valves. x
** SI-169.1A PERIODIC CALIBRAfl0N OF DIESEL GENERATOR INSTRUMENTS IN CONTROL ROOM AND AUXILI ARY CONTROL ROCH - UNITS 1 AND 2 REV NO. 000 This instruction was i.ritten to establish the frequency of every 18 months The probability of rsi eccident was not increased, and the possibility for f or the calibration of the D/G instruments. en accident of a differe9t type was not created. The margin of safety was f not reduced. because?t he compilence instruments in SI-169.1A do not have l T.S. setpoir.ts o W erences in TiO (.
l y , _h - 'i y y SI-t h 5 ( M .InDIC C El6aiATION OF DIESEL GENERATOR INSTRUMENi$ IN CONTROL ROOM AND AUXILIARY CONTROL IAND 2 ROOM - Uma REV NO. 000 'it.is iAtruction estcb* ished the f requvv of every 18 months for the The probability of an7hident was not increased, and the possibility for
^
catibration hf the D1s instruments. I" 3 , an accident of a dif ferent type was not created. the me.glo of safety was ' I g ,, not reduced, tmuse the compliance instruments in St-169.18 do not have r f.S. Setpoints or tolerances. Th y are calibrated to,mcrt the tolerances 3 in TI-54 -
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3 g Page No. 43 G2/22/88 - SEQUOYAH NUCLEAR PLANT 10 CTk 50.59 1987 NRC ANNUAL OPERATIN" REPORT
- CHANGES TO PROCEDURES AS DESCRlbl0 IN THE SAR s
w DESCRIPTION SAFETY
SUMMARY
g ,', s Vi
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SI-169.2A PERIODIC CAllGAQAo' DIESEL GEt .:ATOR INSTRUMENTS IN THE CONTROL ROOM AND AUXILIM Y CONTROL ROOM - UNITS 1 AND 2 REV NO. 000 This instruction est4A f shed A itequency to calibrate the D/G indicating This procedure established a frequency to calit; rate the indicetine -- instrunents in the enntrol roce and auxiliary control room. instrunents and to verify that they are calibrateo. The probabli!!y of an accident is not increased. No new possibilities for an accident or matfunction were created, because the pr cedure ensures that att instruments are calibrated correctly and that a functional tes: Is perforsned af ter the calibration to verify the instrtments are returned to service. The margin of safety was not redaced, because the compliance indicating instruments in the procedure do not have T.S. setpoints or tolerances but are calibrated to meet the tolerance in TI-54. REV No. 001 This revision added wire designatics, added acceptance criteria to the The wire desigrations added to this' instruction ensured disconnected wires data sheet, and changed the seqe=:nce of data sheets. were property identified for reconnection. The addition of the acceptance criteria to the data sheet and sequence change of the data sheets enhanced the instruction. The probability of an accident of a different type was not created. The te changes in no way reduced the margin of safety, as - defined ir the he_4is of any T.S.
** S* 169.28 PERIODIC CALIBRATION OF DIESEL CENERATOR INSTRUMENTS IN THE CONTROL ROOM AND AUXILIARY CONTROL ROOM - UNITS 1 AND 2 REV 30. 000 This instruction estabitshed a frequency to calibrate the dieset generator The probability of an accident was not increased, because this instruction indicating instrunents in the otrot room and the auxiliary control room. established a f regJency to calibrate the indicating instruments and to verif y the instrument & ore calibrated correctly. No energin of safety is reduced. .These instru ents do not have T.S. for setpoints or tolerances.
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I reduced. These instrtmients do not have T.S. for setpoints or tolerances.
** SI-174 FIRE SYSTEM SPRAY AND/OR SPRINKLER SYSTEM TESTABLE VALVE CYCLING - UNITS 1 AND 2 REV No. 006 This revision added a statement to give exenption for performance if The clarification made to this instruction and the addition of FCV-26-243 51-166-1 is in frequency, clar8fied the acceptance criteria, and added did not change the intent or the effects of the performance of this test.
FCV-26-243 which had been oc-;tteu. Therefore, there was no increase in the probability of an accident or mat function of equipment, and the margin of safety was not redaced.
** SI-175 Lou-PRESSURE C'2 SYSTEM LEVEL AND PRESSURE VERiflCATION - IMIT 0 REV NO. 004 Changed organhational designation f rone f oE to OE&C and unit designation on the changes indicated did not affect the performance or intent of the titie page from units 1 and 2 to unit 0 in accordance with Arpendia F of instruction. The changes made were for ascinistrative enhancement onty.
51 1. Therefw e, the probability or consequences of an accident or malfunction were not increased, and the margin of safety was not reduced.
** SI-177.3 SPRAY AND/OR SPRINKLER SYSTLMS FUNCTIONAL - UNITS 0, 1, AND 2 REV NO. 005 This revision added the requirement for both unit SRO's approvat and made This revision reduced the probability of an accident or mal' metion, and no corrections and clarifications to the instruction. new accident or malfunction was created. The margin of safety, as defined in the basis of any T.S., was not reduced. ** SI-178 MOVEA8LE DETECT'*t DETERMINATION OF QUADRANT POWER TILT RATIO - UNITS 1 AND 2 REV NO. 004 This revision was made to ensure compliance with LCO 3.3.3.2, to Complying with the T.S., implementing Westinghouse secommendations, incorporate vestinghouse reconnendations to atlow use of the tr<, ore attowing use of incore conputer code, and generst clarification ensure conputer code, to add a reference section, and to provide additional monitoring of Guadrant Power Tilt Ratio and do not reduce any T.S. margin clarity. of safety or increase the probability of an accident.
. ~ ~- .. .-- . -. ._ _ _ - .__ _. . . ..
l' age No. 45 02/26/88 SEQUOYAM NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT - CHANGES TO PROC 8')URES AS DESCRIBED IN THE SAR DESCRIPTION SAFETT
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** SI-180 FIRE PUMP START TEST - UNITS 1 AND 2 SEV No. 004 This revision charged the time required to perform the test f ran 2 hours to The margin of safety for this instruction was actually increased. This I hour, added step to place fire purps not being tested in "STOP" prior to ensured that LCO 3.7.11.1 is entered when the fire pw ps control sw'tches beginning of test, and provided SRO signof f blanks for when the LCO is are placed in "STOP" and that the action of the LCO is complied with. The entered and emited. Refer m e CAQR 500 870399 SIT. This change also probability of an accident or malfmetion was not increased. The margin of included correction of various typographical errors. safety was not reduced. ** S1 181.5 MIGM-PRESSURE FIRE PROTECTION STRAINER CLEANING / INSPECTION (18 MONTHS OR REFUELING OUTAGE) - UNIT 2 REV NO. 002 This revision added T.S. Information to the scope and added a signoff for The addition of acceptance criteria to the scope of this instruction did the SE prior to beginning the test. not affect the probability of an accident, the possibility for an accident of a dif ferent type, or the margin of safety. ** SI 182.1 EMERGENCT CAS TREATMENT SYSTEM A & B ELAPSED TIME METERS CALIBRATION VERiflCATION - UNITS 1 AND 2 CEV NO. 001 This revision ad&d verification by a second person, corrected rubering This instruction verifies cotibration of the elapsed time meters. The test.
and format, and added information to clarif y the instruction. will not af fect operation of the ECTS f an or filter trains. The regairement to verify calibration of the meter is not addressed in the FSAR. The changes made to isprove the procedure did not affect uperation as described in the FSAR and did not affect the acceptance criteria. The margin of safety was not reduced.
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REV NO. 002 This revision changed 6 percent to 1 percent on page 5, step 5.2.2.6. This SI does not satisfy a T.S. but calibrates a cceptience instrument 'used to fulfilt SR 4.6.1.8.A and SR 4.6.1.8.C. The margin of safety as defined in the basis of any T.S. was not reduced by correcting the percent number.. 4
Parr C , 46 0'.,te/88 SEoOOTAH NUCLEAR PLANT 13 CFR 50.59 a 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCR18ED IN OtE SAR DESCRIPTION SAFETY
SUMMARY
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- $1 182.2 AUXILI ARY SUILDING GAS TREA? MENT SYSTEM A AND 8 ELAPSED flME METERS Call 8RAi!ON VERIFICATION - UNIIS 1 AND 2 REV NO. 000 This instruction was wrfiten to verify ca.libration of the ABGTS elapsed The meter does not affect the operation of the fans and filter trains. The time meters. The ABGIS f!!ters are required to have samples of the requirement to verify the meter is not addressed in the FSAR; verification charcoat taken after 720 hours. The meter on the filter is to be verified of the meter will not affect operation as described in the FSAR. The on en 18-month cycle as a conptlance instrument. Since the minimum testing of the meter is performed by monitrring its function during the division on the meter is 1/10 of 1 hour, a tolerance of +/- 1 percent for 10-hour run and verifying it against a calibrated time source. There tre the 10-hour required run is used to verify proper operation. no connections or conditions that might degrade the equipment; no new .
accident condition can occur. The use of +/- 1 percent tolerance us the meter is consistent with the capability of the egalpment and ervares an extremely conservative rWr to meet the NRC SR.
- SI-153 LOWER CONTAINMENT CASEOUS AND PARTICULATE RA510ACTIVliY MON!f0 RING DURING PERIODS OF RADIATION MONITOR INOPERASILITY - UNiiS 1 ANJ 2 REV NO. 006 This revision included title changes becaue M vganitational changes and These are only title and format changes to the instruction in this revision clarification of the instruction by forwat chan, 1. because of St-1, Appendix F. These changes in no way increased the possibility of an accident or metfunction and did not redJce the margin of saf ety, because the cf>-w did not af fect any .'.S. or acceptance criteria.
St-185 FIRE HOSE CONNECT 10N CON'.Ru VALVE OPERASILITY TEST - UNITS 0, % AND 2 REV NO. 006 This revision corrected <ganizational designations, added requirement for 6e chr,.ges did not affect the intent or result of the instruction. These SRO approvst prior er .esting, corrected unit designation on titte page, changes brought the procedure into conpliance with SI-1, Appendix F. The and corrected typor, aphical errors in the instruction. The revision was margin of safety was not reduced, and the probability of an accident or made in accordae ,with SI 1, appendix F. matfmetion was not increased.
m . _ __ _ , . . C' age Co. 47 02/22188 SEQUOTAH NUCLEAR PLANT 10 CTR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPilON SATETT
SUMMARY
g SI-137 CONTAINMENT INSPECTION - UNiiS 1 AND 2 REV #0. 007 This revision was made to verify the closure and the securing of the polar L e doors have been verified previously in 50I-88, and the new drains have crane wat t doors and to add informaticn on the new drains in the No. 3 and been analyzed per WP12369. These revisions ensure there is no decrease in-No. 4 accumulator rooms. the margin of safety. The probability of an occurrence or the consequences of m accident or matfunctions were not increased.
** $1-188.2 EMERGENCY CAS TRf ATMENT SYSTEM CGit AINMENT ANNUttfS PRESSURE CONTROL REV No. 000 This is 4 new instruction e6ict provides a more comrehensive checkout of The probability of an occurrence or the consequenr.es of an accident or the cJntainment annuius pressure control functions of the EGTS. metfunction of equipment important to safety previously evaluated in the SAR were not increased. No new possibility of an accident uns created.
The margin of safety, as defined in the basis of any T.S., was not reduced, es $3 139 PERIODIC CALIgAAtiON OF CONDENSATE SYSTEM COMPLt ANCE INSTRUMENTS - units O AND 1 REV No. 008 This revision changed instructions for F-2-256 and F-2-257 because of a The new instruments Isr roved reliability and accuracy. The T.S. bases do change in the Instrument type and revised the vacuum purp rotometer not apply to the condenser vacuum exhaust instruments. The margin C,f instructions, safety, as defined in the basis of any T.S.~, was nct reduced.
** $1-190 FIRE HCSE STAit0NS INVENTORY
- UNITS 1 AND 2 REV No. 010 This revision added mode applicability, added Data Sheet 5 for temporary This revision added Data Sheet 5 and clarified the instructions for-hose instatlations, and clarified instructions. performance. No new methods of inspection have been created, and the acceptance criteria has not been changed. This revision also clarified the mode applicability and instructions pertaining to the inspection of tesnporary fire hoses. The T.S. for this instruction has not changed. The
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probability of an occurrence or the consequences of an accident or matfunction were not increased. The margin of sa8ety was not reduced. i SI-193.2 CONTAINMENT BUILDING AND AUXILIARY BUILDING VENilLATION SYSTEMS - UNIT 2 WEV NO. 000 This in;gruction was written to provide for the ce*fhration of unit 2, No T.S. timits were affected, and no abnormal plant operating conditions system 30, instruments which previously were sc:.eduled for catitwatton by were created by this instruction. When equipment is made inoperabte, SI-193, redmdant 100 percent capacity equipment is avaltable for service. The margin of safety, as defined in the basis of any T.S., was not reduced. SI-195 PERIODIC CALIBRATION OF TLUID COPwC h 'S. INC. FLOW SWITCHES (SYSTE.5 30, 3' 45) ' C.* .*NNUAL) - UNITS 0, 1, AND 2 REV NO. 003 The calibration sheets for the ECTS flow swise w e revise 1 *a " m These changes erhanced the procedure and ensured the applicable contact action and to change setpoints on FS-65-31-A/8, -8/A and instrtmentation operated as designed. The setpoint changes for FS-65-55-A/8, -8/A. FS-65-31-A/S, -8/A and FS-65 55-A/8, -8/A are in accordance with the latest TVA drawings. The probability of an accident was not inc. eased, and the' possibility for an accident of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
** $1-198.2 CAL 18 RATION OF COMPLIANCE & TECHNICAL SPECIFICATION INSTRUMENTS (10 MONTHS) - UNIT 2 REV NO. 000 This instruction was written to calibrate the unit 2 instruments previously There were no changes to plant setpoints or T.S. timits. The probability calibrated under SI-198. It also clarified work instruction and deleted of an occurrence or the consequences of an accident or malfuretion of instrtsnents iAlch are no longer identified as coupliance instrisnents. egalpment were not increased. The possibility for an accident or malfunction of a different type than any previous 8y evaluated was not .,
created.
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** SI-198.3 CALIBRATION OF SHIELD, AUXILI ARY, AND SERVICE BUILDING GASEOUS EFFLUENT IS0 KINETIC SAMPLING SYSTEM REV NO. 000 This SI was created to ensure proper calibration of shield, auxiliary, and The probability of an occurrence or the consequences of an accident were service building gaseous effluent isokinetic sanpling syst w. not increased. No new possibility of an accident was created. The margin of safety, as defined in the basis of any T.S., was not reduced.
** SI-204.2 FUNCTIONAL TEST FOR RADIATION MONITORING SYSTEM (MONTHLY) - UNIT 2 f.EV NO. 006 This revision clarified steps for measuring high voltage and proper This revision clariffes instruction steps and ensures that data is recorded annunciation, added note to instruction allowing loops to be tested as intended. It is needed to ensure that the procedre can be worked as independently, added high voltage tolerance valves, and corrected written. Placing a tolerance on the high voltage value of the detec*ar gransnatical errors. will help to ensure that the calibration of the radiation monits. d nr.S -
does not drift. This revision did not decrease the margin of safety and did not increase the probability for en accident. It did not create the possibility for an accident or malfunction different from that previously' evaluated. ,
** $1 -2012 RADIATION MONITORING SYSTEM SAMPLE FLOW CALIBRATIONS AND FUNCTIONAL TESTS - UNIT 2 (12 WEEKS)
REV NO. 011 This revision cancetted the instruction. To improve the organization and performance of testing of the radiation monitoring system maapte flow instrumentation, an integrated revision of SI-206, 51-206.2, SI-302, and $1-302.2 was developed along with the addition of two new tests: $1-206.3 and $1-206.4. The testing of gaseous-radiation monitors was moved to $1-302 and St-302.2. The testing of pressure gauges contained in gaseous radiatico monitors was moved to S1-206.1 and 51-206.4. N o new tests were written to catibrate rotometers. Nnn-T.S. CSSC liquid -W particulate CAM radiation monitors were moved to a periodic matrum.ence program. These organizational changes left only the
Page tas. SC 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING LEPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY SUMMART g tiquid radiation monitors for which there are T.S. SRs to be addressed by 51-206 and St.206.2. Because there is only one liquid radiation monitor in unit 2 that falls toder this category, the testing of this monitor was added to 51-206. These changes attowed canceltation of $1-206.2.
** S1-206.3 RADIATION MONITORING SA*@LE FLOW twDICATOR AND VACUUM GAUGE CALIBRATION - UNITS O AND 1 REV NO. 300 This new instruction wes writt n to resolve CATS 86700 by calibrating This test was performed by connecting a N85 standard to the radiation radiation monitor flow rotometers and vacuum gauges in place. monitors intet test tees. The test complies with the LCOs associated with each monitor and ensures the proper removat and the return to service of equipment tested. This test ensures that gauges used to meet T.S.
requirements are property certified to a specified accuracy, thus increasing the margin of safety.
** S1-2C$.4 RADIATION MONITORING SAMPLE FLOW INDICATOR AND VACUUM CAUGE CAllBRATION - UNIT 2 (550 DATS)
REV No. 000 This new instruction was written to resolve CATS 86700 by calibrating This test was performed by connecting a NSS standard to the radiation radiation monitor flow rotometers and vacuun gauges in place, monitors intet test tees. The test complies with the LCOs associated with each monitor and ensures the proper removat and the return to service of egalpment tested. This test ensured that gauges used to meet T.S. requirements are property certified to a specified accuracy, thus increasing the margin of safety.
** SI-209.2 FERIODl'* CALIBRAil04 Of VOL? METLES IN A550CI AilD LLECTRICAL SYSILMS 120V ac,125V de, 480V, 6.9kV (18 MONIHS) - UNIT 2 REV NO. 002 This revision mede the acceptance criteria Consistent with the DPSO field The protubility of an accident was not increased, because the change test annual, vtrifics that the instrumets are entitwated within the required limits in the DPSO field test manual. Since the instrunents do not perform any
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y equipment protection function, the possibility for an accident or malfunction of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not redJced.
** 58-212 ECCS THROTTLE VALVE MECHANICAL STOP POSli!ON - UNIIS 1 AND 2 REV NO. 017 This St incorporated organizational acronym changes f rom OA to OESC and These changes did not af fect the intent or performance of this instruction conplies with SI-1, Appendia F. and did not reduce the margin of safety or increase the probability of an accident. The intent or scope of the instrection was not attered. ** SI-215 a004-INDICATING R00 POSITION DETERMINATION - UNITS 1 AND 2 REW No. 001 This revision incorporated requirements of SI-1, Appendia F, ensured Ensuring compliance with T.S. and allowirw Mutation of more than one compliance with T.S. functions by ensuring acceptance criteria, referenced nonindicating rod in no way increewv the probability of an accident or the appropriate LCO, added a calculation to ensure rods are within required malfunction. Ensuring compliance with T.S. to make sure att regJirements timits, and attowed determination of more than one rod position. are enforced did not reduce the margin of safety.
SI-218.1 PERIODIC CALIBRATION OF REP UNDERFREQUENCY RELAYS - UNIT 1 REV ho. 001 This revision added SI-230.1 in the reference, added a statement in the This revision ensures that the 0*s are fulfilled. The probability of an scope that SI-250.1 is needed to complete the SR, and added information to accident was not increased, and the possibility for an accident or clarify and to erhance the procedure. malfunction of a different type was not created. The margin of safety, as defined in the basis of the T.S., was not reduced.
** SI-218.2 PERIODIC CALIBRATION OF RCP (JNDERFREQUENCY REL AYS - UNIT 2 CEV No. 001 This revision added 53-230.2 in the reference, added a statement in the This revision ensures that the SRs are fulfilled. The probability of an scope that SI-230.2 is needed to complete the se, and added information to accident was not ineseased, and the possibility for an accident or
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clarify and to enhance the procedure. malfunction of a different type was not created. The margin of safety, as defined in the T.S., was not reduced.
** SI-220.1 AUTOMATIC LOAD SEQUENCE TIMER FUNCTIONS TEST - UNIT 1 CEV No. 004 This revision brought the procedure into compliance with SI-1, Appendia F, The general methodology of the test was not changed. The protability of an added a statement concerning the M&fE required specifications, acMed SRO occurrence or the consequences of an accident or malfmetion were rot approvat, and added UO notification as applicable for connon equipment. increased. The possibility for an accident or malfunction of a type different than that previously evaluated was not created. The margin of safety, as defined in the basis of any T.S., was not redaced. ** SI-220.2 AUTOMATIC LOAD SEQUENCE TIMER FUNCTIONAL TEST - UNIT 2 REV NO. 004 This revision corrected deficiencies identified try SI-1, Appendia F. This Analysis of CSP increated time delay demonstrated no increase in revision also included arpticable modes, METE specifications, operations probability of an accident or malfunction. The changes in this revision _
notification and approval, and more concise direction regarding M&iE did not change test intent or methodology. Other changes served to ensure connections / disconnections and contingency for unset "As Found" data. It cug,liance with T.S. requirements. The margin of safety was not reduced. also included a change to CSP time dcLay f rom 30 secorvh to 180 seconds (ECN L6715).
** St-228.2 PERIODIC FUNCTIONAL Test OF RCP UNDERVOLIAGE REL AYS - UNIT 2 REV NO. 000 This instruction was written to replace SI-228 for unit 2. SI-228.2 has $1-2:3.2 accomplished the same function as SI-228. The added steps in steps which are not in SI-228 and which will verif y the tsujervoltage relays $! 228.2 improved the functional test. No new accident possibilities wre -
actuate afprominately at their setpoints. created. 51-228.2 verified that in the required mode, the required three . of the four undervoltage channets will be in service at att times during the test.
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- 58-230.1 PERIG)lc FUNCil0NAL TEST OF RCP UNDERFREQUENCY RELAYS - UNIT 1 CEV No. 001 This revision added signoffs for removing the undervoltage relay connection The probability of an occurrence or the consequences of an accident were blocks, deleted the referenced relay setting sheet numbers, and referenced not increased, because the change erhances the procedure by documenting the LER 1-86-015. removal of equipment. At refueling, LER 1-86-015 prevents the removat of information rewired by the LER in the original procedure. The margin of safety was not reduced, because the revision verifies the relays are tested according to T.S. requirements.
- S1-230.2 PERIODIC FUNCTIONAL TEST OF REP UNDER FREQUENCY RELAYS - UNIT 2 REV No. 001 This revision added signof fs for removing the undervoltage relay connection The probability of an acc! dent was not increased, because the changes block, deleted the referenced relay setting sheets, and referenced erdiance the procedures by documenting the removat of equipment and by LER-86-015. referencing LER-1-86-015 which will prevent the removat of information required by the LER in the original procedure. Deleting the relay setting sheets will not affect this procedure, because setpoints are taken from T.S. There are no new possibilities of creating an accident or malftmetion of a dif ferent type, because the revision did not change the method of testing or the precautions required during testing. The margin of safety was not reduced, because the revision verifies that the relays are tested according to the T.S.
- SI 233.1 VISUAL INSFECTIONS 0F PELffRATION FIRE BARRIERS - MECHANICAL SYSTEM 302 (PENETRATIONS) - UNITS 1 AND 2 REV co. 002 This revision changed the scope to include references to other sis required These changes did not alter the intent or testing of this instruction.
to conplete SR 4.7.12.a. and included the requirement to visually inspect They did not increase the pessibility of an accident and did not reduce the att mechanical piping and conduit penetrations in the f tre tone boundary margin of safety, because no it.S. was af fected by the changes.
.- . - _ ~ . .
Page Co. 54 02/22/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY SUMMART , surf aces instead of a specific russber of penetrations.
- St-233.4 VISUAL INSPECTION OF THFRMAL FIRE BARRIERS '
REV kO. 004 This revision was made to i g tement the necessary sketched drawings into Att the fire barrier penetrations meet the required fire rating, and the 51-233.4 R3 as a replacement and addition to entsting interaction rumbers. conduits impacted are seismicatty qualified. Att fire barrier penetrations are in accordance with 10 CFR 50.49, Appendix R. The fire barrier penetrations and cable penetration barriers were restored to their original status following cable replacement and/or rerouting. The probability of an-accident was not increased, and the possibility of an accident of a different type was not created. The margin of safety remains unaltered.
- S!-234.3 TECHNICAL SPECIFICATION FIRE DETECTORS - UNITS 0, 1 AND 2 REV No. C11 This revision was made to comply with the National Fire Protection The instruction scope has been increased to incorporate testing of fire Association standards and to incorporate vendor checks. It was c;so s@ pression flow control vatsas currently performed in'SI-177 series to revised in accordance with $1-1, Appendix F, and incorporated CATS 86-275. eliminate redandancy and improve efficiency. The basic test requirements remain unchanged, and att T.S. requirements are futfitted. The margin of safety, as defined in the basis of any T.S., was not redaced.
- SI-234.4 TECHNICAL SPECIFICATION FIRE DETECTORS - UNITS 0,1, AND 2 REV No. 014 This revision was made to comply with the National Fire Protection the instruction scope has been increased to incorporate testing of fire Association standards and to incorporate vendor checks. It was also suppression flow control valves currently performed in SI-177 series to revised in accordance with SI-I, Appendix F, and incorporated CATS 86-275. eliminate redundancy and to improve efficiency. The basic test requirements remain unchanged, and att T.S. requirements are futfitted.
The margin of safety, as defined in the basis of any T.S., was not reduced.
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a O* SI-234.5 TECHNICAL SPECIFICATION FIRE DETECTORS REACTOR SUILDING - UNITS 0,1, AND 2 REV NO. 011 This revision was made to comply with the Nationel Fire Protection The instruction scope has been increased to incorporate testing of fire - Association standards and to incorporate vendor recommended checks. It was suppression flow control valves currently performed in $1-177 series to also revised in accordance with SI-1, Appendix F, and incorporated eliminate redmdancy and to improve ef ficiency. The basic test requiremer.ts of CATS 86-275. requirements remain mchanged, and att ifs. requirements are fultitled. The margin of r,afety, as defined in the basis of any T.S., was not reduced.. SI-234.7 TECNNICAL SPECIFICATION FIRE DETECTORS - UNITS 1 AND 2 REV No. 007 This revision was made to comply with the Nationat Fire Protection The instrtttion scope has been increased to incorporate testing of fire Association standards and to incorporate vendor checks. It was also s@pression flow control valves currently perfonned in SI-177 series to revised in accordance with SI-1, Appendix F, and incorporated CATS 86-275. eliminate redundancy and to improve ef ficiency. The basic test requirements remain unchanged, and att T.S. requirements are fulfitted. The margin of safety, as defined in the basis of any T.S., was not redaced. m $1-237.1 POWER NOUSE CO2 FIRE PROTECTION SYSTEM TEST - UNITS 0, 1, AND 2 REV NO. 009 This revision added performance modes and METE ranges and incorporated The basic testing method remains the same but is more detailed and complete recommended vendor cardox checks. It also incorporated requirements of to ensure compliance with the T.S. No possibility for an accident or CATS 86-497 and PRO-1-87-174. malfunction of a different type than any evaluated previously in the SAR was created. 'The margin of safety was not redJced. . O* SI-237.2 DIESEL GENERATOR BUILDING CO2 FIRE PROTECTION SYSTEM TEST - tmITS 1 AND 2
~ ~
REV NO. 007 This revision added performance modes and M&TE ranges and incorporated This revision tests equipment as designed and does'not alter configuration. vendor cardon checks. It also incorporated requirements of CATS 86 497. No margin of safety was red;ced.
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)
W $1-238.2 DIESEL GENERATOR BATTERY CAPACITY TEST - UNIT 0
#EO NO. 008 This revision was made to increase the service test current levet from 5 The probability of the occurrence of a loss of offsite power or any anps for 29 minutes to 47 anps for 30 minutes. The remainder of the accident that would respire the use of the dieset generators for the safe revision addressed clarification of proced.rrat steps and increased shutdown of the facility was not increased by the additionat discharging information in scope, prerequisites, and test equipment, time added to the service test. The consegances of the complete loss of one dieset generator train, for any reason, are analyzed in FSAR 8.3.1.2.1.
ce sg.338.3 AmuuAL D:;$EL GENERATOR BATTERY SYSTEM INSPECTION - UNIf 0 PEV No. 000 This instruction was written to fulfit t SR 4.8.1.1.3.C.1, SR 4.8.1.1.3.c.2 This procedure is an inspe: tion that does not take the equipment out of and part of SR 4.8.1.2. These requirements were formerly fulfilled by service and does not disassemble anything. ' The probability of the
$1-238.2. occurrence of an accident was not increased, and the possibility of'an accident or malfunction of a different type was not created. No margin of safety was reduced.
SI 240 FUNCTIONAL TEST OF CONTROL ROOM AIR INTAKE CHLORINE DETECTION SYSTFM (WEEKLY) - UNIT 0 REV NO. 012 The revision clerified instruction steps, added detalt to the T.S. The test methods remained the same except for actuation of the CRI. reference, and changed authorization to commence testing to unit 1 and unit Actuation of the CRI places the plant in a more conservative condition. 2 SRos. The probability of an occurrence or the consequences of an accident were not increased, and the possibility for an accident of a different type was not created. This test ensures the operability of channels required by the T.S. 4
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3
** SI-2$2 FUNCTIONAL TEST OF THE WASTE GAS DISPOSAL SYSTEM OXYGEN AND HYDROGEN ANALYZERS CEV NO. 005 This revision cancetted 51-242. The functions in $1-242 have been incorporated in SI-243. No testing methods have been changed. ** SI-253 CEANNEL CALIBRATION OF THE WASTE GAS DISPOSAL SYSTEM OKYGEN AhD HYDROGEN ANALYZER QUARTERLY - UNIT 0 REV en. 006 This revision incorporated the functional testing previously performed by The procedure changes were made to include testing performed in another $1 S1-242 and resolved discrepancies identified by SI-1, Appendix F. without changing the general methods used. The probability of an occurrence or the consequences of an accident were not increased, and the -
possibility for an accident of a different type was not created. The margin of safety was not decreased, because this revision obtains the same results as St-242 R4 and $1-243 R7.
** SI 205 FUNCTIONAL TEST OF SEISMIC MONITORING SYSTEM - UNIT 0 REV NO. 004 This revision added performance modes, listed test equipment, and The functional testing of the response spectrum recorder (0-XR-52-86) is incorporated generat format considerations from present guidelines. This not required by the Y.S. Att the other changes were for clarity and revision also removed the response spectrue recorder (0-NR-52-86) from the documentation. .The test methods remained the same. The probability of an-test. occurrence or the consequences of an accident or metfunction were not increased. The possibility for an accident or metfunction of a different type was not created, and the margin of safety, as defined in tre basis of any T.S., was not reduced.
, ** St-255 SURVElLLANCE PROGRAM f0R REACTOR IRRADIATION SPECIMEN - UNITS 1 AND 2 REV NO. 004 This revision added the requirement to meet 10 CFR 50.61,'"fracture Including the requirements of 10 Cf R 50.61 was in addition to the required Toughness Requirements for Protection Against Pressurized Thermal Shock T.S. and enhanced the procedure. ~ The mergin of safety was not recluced. 5 l
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g Events," to 51 255, this revision also corrected titles to other references.
" SI 256 PERIODIC CALIBRATION OF OVERCURRENT AND GROUND FAULT RELAYS ON RCPs AND BACKUP DEVICES ON 6.9kV UNIT BOARDS (REFUELING CYCLE) - UNITS 1 AND 2 REV No. 008 This revision separated the signof fs for A-phase and C-gAase overcurrent All breakers will be signed off individuelty rather than several at one relays on RCS breaker, normal feeder breaker, and atternate feeder breaker. tiae. RCP circuit breaker numbers will be included in the identification This revision also identified breaker ruber in step 6.2.2 of att data of circuit breakers in step 6.2.2. Civine more positive identification and packages and arved data sheets f rom the end of the package to behind the data sheet arrangement attows adequete recording of data. The changes section for each breaker, stated did not af fect or reduce the margin of safety as defined in any T.S.
REV No. 009 This instruction was revised to correct RCP breaker tuber, to change The SR ruber remains in the scope of this instruction. The probability of system rubers, and to remove T.S. SR number f rom the acceptance criteria. an accident was not increased, and no new possibilities of an accident were created. The margin of safety was not redaced. t
" 51-257 PERIODIC FUNCTIONAL OF RCP PROTECTIVE DEVICES (18 MONTNS) - UNITS 1 AND 2 4 REV No. 010 This revision combined $1-257.1 and SI-257, because the i.$. addresses The probability of en accident was not increased, and the possibility for these procedures in $1-257.1. an accident of a different type was not created. The mergin of safety, as defined in the basis of any T.S., was not reduced.
** SI-258 TESTIeG OF w1DED CASE AND Lol4R VOLTAGE CONTAINMENT PENEIRATION CIRCULI SREAKERS - UnitTS 0 AND 1 REV No. 009 This revision added the celta (D) sign to the breaker common to both unit ! This revision did not create any malftsiction of any type, because this
$1s and adjed vendor curve list. It also added a statenent that was revision tgstated only the procedsrc method without af fect6 ras any inadvertently omitted that allows the breaker test sequence to be at the safety-related equipment. This change did not af fect T.S. requirements.'
discretion of the cognirant engireer and deleted rtwirement for dq)titute the sargin of safety remained unchanged. conf iguration contret dwumentat ton.
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g C* SI-258.2 TESTING OF MotDED CASE AND E0WER VOLTAGE CONTAINMENT PENETRATION CIRCUIT BREAKER $ - UNITS O AND 2 REV NO. 011 This revision incorporated instantaneous testing of breakers and corrected This revision upgrades breaker integrity through testing and ensures - instructions to be in accordance with the SI-1, Appendin F. It superseded breaker rettability, because T.S. requirements are enforced. No ICF-86-1279, CATS 86182 and 86183, MATS 8623, and NCO 860177006 and was safety-related function or feature is reduced by this revision, because the corrective action for DR-87-063R. Integrity of the breaker is mainteir.at during the test. The test is in conformity with att T.S.; therefore, no safety margin was reduced, and there was no increase in the probability of an accident or estfunction of plant equipment. C 51-359.1 TESTING OF ACTUATION OF AUXILIARY TEEDWATER BY TRIP OF MAIN FEED PUMPS - UNIT 1 REV a0. 002 This revision cancetted SI 259.1 R2. SR 4.3.2.1.1.c.6.f of 53-259.1 R2 is Testing methodology and acceptance criteria of 51 118 R15 and $1-118.1 R15 satisfied by 51-118 R15 and 5I 118.1 R15. were not affected and match those required for 51-259.1 R2.
- c. sg.259.2 TEST OF ACTUATION OF AuklLIARY FEEDWATER SY TRIP OF THE MAIN etED PUMPS
- UNIT 2 REV no. 002 This revision cancetted 11-259.2. SR 4.3.2.1.1.C.6F of 51-259.2 R2 is Testing methodology and acceptance criteria of sI-118 R15 and st-118.1 R15 satisfied by 51-118 R15 and 51-110.1 R15. were not affected and match those required for st-25,9.2 R2.
C SI-260 SIS / BIT /RNR INJECTION FLOW SALANCE, PUMP PERFORMANCE, AND CHECK VALVE TEST - UNITS 1 AND 2 REV No. 013 This procedure lists the instructions in the SI-260 series. The revision The probability of an accident or malfunction was not Increased by this added two (2) new procederes to the list $1-260.2.1 and 51-260.3.1 revision. The margin of safety was not reduced, because this is an . administrative procedure intended as a cover for other sis in the 53-260 Series.
+6 -
+- A-Lm -- &,. --6 a s-- + -, ~---.-.L ^ ,,A- - + w,, - - - -al., %+u-L L -
Page No. 60 02/26/88 SCOUoVAN NUCLEAR PLANT to CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRI8ED IN THE SAR DESCRIPil0N SAFETT StJMMART
** St-263 MoutioRING COMPONENT CYCLIC OR TRANSIENT LIMil - LJNITS 1 AND 2 REO No. 008 This revision added new guidelines for tracking cyclic limits and added the Ensuring the correct treckfr5 and monitoring of cyctic timitations and transient one-half safe shutdown earthquake as required in the FSAR. cr=ptying i ith the FSAR did not increeze the probability of an accident or create the possibility for an accident of a dif ferent type. The margin of safety, as defined in the basis of any T.S., was twt reouced.
** SI-264 Egis ANNULUS VACUUMDRAW DOWN TEST - UNITS 1 AND 2 REV No. 007 151s revision changed at towable leakage at -5.0 inches water colaan The annutus intestage was changed to the latest f SAR value of 500 CFM at pressure and changed the method t,y which the system is realigned. This -0.5 inch WC. New of f-site dose calcutations have shown that inteakage cf -
revision also made other small changes to comply with the SI-1, Appendia f. 500 CFM at -0.5 frch WC is acceptable. Removed the 500 CFat at -5.0 irth WC inteakage specification, because the intenkage criteria only apply to 0.5 inch WC. As tong as the 500 CfM at -0.5 inch WC criteria are met, the of f site dose timits will be met regardless of teskages at -5.0 inch WC.
** $1,-205.2 SAFETY INJECTION NYDROSTATIC PRESSURE TEST - UN!!S 1 AND 2 REV NO. 003 This revision cancetted the entire instruction. It did not comply with This $1 takes the place of $t-265.2 and fulfitts att requirements of ASME, Section MI,1977 edition through sunener 1978 requirements, and SI-265.2. The probability of an occurrence or the ccsisequences of an instruction nudwr should be changed to correspond with the system nuntjer accident or matfunction were not increased, and one of a different type was SI-265.2 is being changed to SI 265.63.1. not created. 51-265.63.1 wilt futfitt the requirements of ASME, Section XI, for the piping inspected as recpired by tit 4.0.5. The margin of safety was not affected.
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Page No. 61 02/23/88 SEQUOYAN NUCLEAR PLANT 10 C7R 50.59 1987 NRC ANNUAL octRAIING REPORT I CHANGES TO PROCEDURES AS DESCRIBED Ils THE Salt Ot5CNIPIION SAftTY $UMK*tf g SI-266.1.1 60 M TN INSPECTION OF I. T. E. 7.5Hr-500 6900v BREAutes - UNIT 1 AND COMMON REV NO. 000 This is a rew instruction for separating $1266 Into irafivicbat Sis, one This change ensures that t:reaker reliability is continued through for each type of breaker (6.9kV, low voltage 05-type and molded case). inspection of each containment penetration brea6er listed in this St. This instruction also complies with SI-1, Appendin F. This 53 is for Breakers are removed f rom service for performance of this instruction in vendor malr.tenance to 6.9kV breakers, comtience with any LCO. There was no increce in the probability of an accident or malfunction, and the creation of a different type of accident did not occur. The margin of safety, as defined, was not reduced.
*) SI-266.1.2 18-MONTH CIRCUIT SatAKER INSPECTION (WESTINGNOUSE TYPE DS 480V) - tmIT 1 AND COMMON Rett NO 000 This instruction Lists att vendur recommended inspections. The inspections Implementation of this instruction ensures that the margin of safety wilt are performed on an 18-month f requency iAich exceeds the minimus 60-month be maintained.
St.
** $3-266.1.3 60-MONTH INSPECTION OF MOLDED CASE CIRCUlf DREAKERS - UNIT 1 AND COMMON REV No. 000 This instruction has been created to inspect 480V and tower voltage molded This instruction serves to increase the integrity of safety-related case circuit breakers. 58-266 is being separated into sin sis to inspect equipment by inspecting for degradations. The probability of an occurrence different types of breakers for each unit. This instruction inspects tnit was not increased, because the SI performed in modes 5 or 6 or under an LCO 2 molded case breakers, adds a breaker meggering test, and incorporates in other modes. Any breaker needing to be spared out for safety reasons vendor recommendations, will be spared ont in the instruction. The probability of an occurrence or the consequences of an accident or metfunction were not created. Att precautions to protect equipment and personnet have been listed in the instruction, The SI ensures the margin of safety was maintained as defined by T.S. 3.8.3.1 and T.S. 3.8.3.3.
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I Dage No. 62 02/26/88 StuuoTAN NUCLEAR PLANT to CTR 50.59 1987 WRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN TNE SAR DE50RIPflON SAFETY SuphARY g
** SI 666.2.1 60-MOM;M IN5PECTION OF l. T, E. 7.5HK-500 6900V SR[ AKERS - UNII 2 AND COMPON REW Wr. 000 This is a new instruction for separating 58-266 into individ;al sis, one This chsnge ensures that breaker reliability was continut<2 through for each type of breaker (6.9kV, lo.e voltage DS-type end molded case). inspection of each contalrument penetration bree6er listed in this St.
Th6s imtruction else cwp!8es with $1-1, Annmdim f'. Yhts 58 is for areakers are removed f rom service for performance of this instruction in j vendor maintenance to 6.9kV breakers. comtlance with any LCO, There was no increase in the prthsbility of an
-accident or metfunction. and the possiaitity for an accident different l from those previously . atueted was'not created. The mergin of safety, es defined, was not redaced.
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** 58-266.2.2 18 MONin circuli sREAKER INSPECil0N (WEsilNGNOUSE iTPE DS 480W) - UNIT 2 AND COMMON l REW m0. 000 This instruction was issued for the separation of 51s (one for each type These inspections are performed on an 18-month fregaency which emceeds the breaker) and to list att vendor recomumended inspections, minisam 60-month SR. The probability of an occurrence or the consegaences of an accident were not increased. The possibility for en accident of a type different from that previously evaluated was not created, and implementation of this instruction ensures the margin of safety was , , maintained.
i 58-266.2.3 60-MONTN INS'TCil0N OF MOLDED CASE CIRCUIT BREAKERS - UNIT 2 AND COMMON REV NO. 000 This instruction has been created to inspect 480 volt and tower voltage The instruction serves to increase the integrity of safety-related l molded case circuit breakers. 51-266 ts being separated into sim sis to equignment by inspecting for degradations. The probebility of an occurrence l inspect different types of breakers for each unit. This instrtaction is not increased, because the SI is performed in modes 5 or 6 or Leider an inspects mit 2 molded case breakers, adds a breaker me;gering test, and LCO in other modes. Any breaker needing to be spared out for safety incorporates vendor recomumendations. reasons will be spared out in the instruction. The possibility for an N accident dif ferent f rom those previously evaluated was not created All precautions to protect ewipment and personnel have tem listed in the s l - _ _ _ _ _ . _ _ _ _ _ _ - _ _ _ _ _ . _ . _ _ . _. _. .. _. _ . _ . - . _ - . . , _ - - _._. _ .
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SUMMARY
instruction. The 51 emures the mergin of safety was maintained as defined ty T.S. 3.8.3.1 and T.S. 3.8.3.3. 58-767.3.2 IN-51kVICE 8'kE55URE TE5IING Of A4Mit I AkT f t"DWAt[N $YSILM MOTON Da!VtM $1JMP5 - UNII$ 1 AND 2 REV #0. 002 This revision clerified the procedure arid deleted the ASME class 2 piping the procedare'is u.ed to perfwm an in service pressure test on a portion f rom the test, because it is not imiuired by ASME code,1977 edition of the AfW. The deletion of class 2 piping from inspection is attomed by through sunsaer 1978. the oppt icatAe ALME code. Conchacting the test escrety ret tects norsmet operation and does not create or increeee the possibility of an accident or malf met ion. The procedure setlefles A$sE, Secthvi MI, and a portion of T.s. 4.0.5. The deletion of class 2 piping does not affect normat system operation. The T.S. margin of safety esos not redaced. 51-267.3.4 f tistCTIONAL PRES 5URE TEST OF THE ERCW $UPPtf TO THE AUNitIARf f EE0 WATER SYSTEM - UNITS 1 AND 2 REW NO. 002 This revision incorporated 51-1, Appendix F, and incorporated instructions This procedure performs a functionet pressure test en the ERCW st@ ply to into data sheet. the AFW system. During the test, AfW can be used and the probabilit/ of an accident or malftriction uilt not be increased. The awrgin of safety, as defined in the basis of any T.S., esos not' reduced. 53-268 VERIFICATION OF P-4 INTERLOCK INPUT TO $5PS
- UNITS 1 AND 2 REV ho. 006 This revision deleted the reference to the T.S. and included a reference to The same equipment is tested in the same menner as before this'revicion.
mRC mEs 79 4 araf mRC NES 79-5 which requires P-4 contact verification af ter The probability of an accident esas not increased, and the possibility for actuation /c4;eration of the reactor trip t,reaker, an accident of a dif ferent type esas not created. This instruction is not used to satisfy any T.S. $R.
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SUMMARY
*O 58-268.3 PERIODIC VERIFICATION Of P-4 INTERLOCK IUNCTION FROM REACTOR TRIP SREAKERS - UNIIS 1 AND 2 EEV NO. 000 This instruction was written to verif y P-4 interlock as result of reactor Testing continuity through breaker auxiliary contacts does not increase the trip breaker actuation. pedmbility of an accident or malfunction. The possibility of an accident er nuit function of a dif ferent type was ret created. The awgin of safety was not reduced. ** $1-270 INSPECTION OF MOLE,ED CASE AND LOWER VOLTAGE CIRCUIT BREAsER SACKUP FUSES CEV NO. 006 This revision cancelled the entire instruction. This instruction has been $1-270.1 ensures that all fuses per unit will be inspected property since replaced by SI 270.T. T.S. rewirements wilt be enforced. Because the instruction compties with T.5., the mergin of safety was not redaced, and the cancettation will not increase the probability of an accident or create an accident or malfunction. ** SI-270.2 FU5ES FOR CONTAINMENT PEhETRATION CONOUCTOR OVERCURRENT PROTECTION - UNITS 1 AND 2 REV No. 005 This revision compties with T.S. requirements by including att fuses by This revision ensures that att fuses will be inspected property, because EQIs identification and reference sampling method. f.5. requirements are enforced. The inspections are visuet, and no maintenance is performed by this instruction. Replacements are made as required. The inspection of the fuses does not increase the probability of an accident or metfunction and does not create one of a different type. !
The instruction is in Compliance with the T.S.; therefore, the margin of safety is not redxed.
Oage me. 65 02/22/88 SEQUOYAN NUCLEAR PLAuf 10 CFR 50.59 1967 mRC AmuuAt OPERATING REPORT CMANGES TO PROCEDURES AS DESCRitED IN TWE SAR DESCRIPTION SAFETY SIDMARY g REO m0. C36 This revision ensured titeret compliance with the T.S. The instruction The visual inspection has no impact on safety. The "wiggle" test may provides for a visuet inspection of fuses and a "wiggle" test for result in ds-energizing safety-related equipment and entering a LC0; tightness. however, it will not cause an equipment malfunction. Cautions have been aMed to the instruction to ensure rededent train operability prior to nerforming the inspectico. The potential loss of one train of safety-related equipment has been previously evetuated, and no new situation was created. The mergin of safety, as defined in the basis of the T.S., was not reduced.
- SI-275.1 TESTING OF WON CLASS 1E Lono CIPCUIT BREAKERS FED f ROM CLASS 1E susSE$ - UNITS 0 AND 1 REV NO. 006 This revision added the detta (D) sign to breakers common to both imit 1 This revision did not create any notfunction of any type, because this sis and added vendor curve test. It also added a statement that was revision updated only the procedure method without af fecting any inadvertently omitted that allows the breaker test sequence to be at the safety-related equipment. This change did not affect T.S. regJirements;-
discretion of the cognirent engineer and deleted the requirement for therefore, the mergin of safety remained urchanged. dupticate configuration control documentation.
- St-275.2 f tSTimG Of woM CLASS 1E LOAD CIRCUIT BRE AKERS f ED FROM CLASS 1E sus 5ES - UNITS 0 Amo 2 REV NO. 011 This revision complies with T.S. requirements and incorporates att DNE This revision upgraded breaker integrity through testing and ensured breaker lists. breaker reliability, because Y.S. requirements were enforced, so safety-related function or feature has been degraded by this change, because the integrity of the breaker is meintained during the event.
Because the test is in compliance with att T.S. requirementis, there was no ' reduction to the margin of safety. _90_
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Page No. 66 02/26/88 SEQUOTAN NUCLEAR PLANT 10 CTR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRISED IN TWE SAR DESCRIPTION SAFETY
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*O 51-276 AUMILIARY fEEDWATER AUTOMATIC CCNTROL VALVES OPERAtiLITY - UNITS 1 AND 2 REW No. 015 This revision corrected the Data Package Cover Sheet in accordance with This revision to the procedure added signoffs to verify the proper SI 1, and added signof fs to verify the motor-driven AFW ptsup as not rmning conditiona before and during the performance of this test and deleted prior to initiating the test. The revision broke to sutti-acticn steps, redundant signoffs. The margin of safety was not affected by this deleted Data Sheet 4, and clarified which steps to perform dependent upon revision, because the changes were for clarity.
steam generator pressure. i
$1-295 DIESEL FUEL RECEIPT REV NO. 005 This revision added a provision to hold the fuel in an alternate container This was a procedJre change and did not increase the probability of an pending results of the analysis. 50A-188, Attachment 1, coversheet was occurrence or the consequences of an accident or malfunction. The added to doctanent OES endorsement for PMP T.S. 04.06.07.14.03. possibility for an accident or malfunction of a differ.nt type was not created. The margin of safety, as defined in the basis of any T.S., w w not reduced.
SI-296 PRESSURE TEST OF DIESEL FUEL OIL SYSTEM - UNITS 1 AND 2 REW NO. 001 This revision added applicable modes 5 and 6 and referenced st 4.8.1.2. These changes ensured the instruction awt att applicable f.s. requirements. The revision also made the instruction applicable to units 1 and 2. The probability of an accident was no' increased, arvj the poss'bility for an accident of a different type was not created.
** $1-297 PRE 55URIZER NEATER CAPACITY - UNITS 1 AND 2 REW NC. 003 This revision changed the organizational name from QA to QE&C, adjed a. Ihis revision did not increase the probability of an accident or place for a signature of the individual determining whether or not malfunction of. safety equipamt and did not increase the possibility of a acceptance criteria is satisfied, renumbered steps of the data deet to different type of'cccurrence. The serpe and intent were mchanged, and the match the body of the instruction, deleted superfluous signoffs from data T.S. was unchanged. The margin of safety remains unaffected by this
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SUMMARY
g sheet, and added brackets to the equation for E to indicate what in the revision. e @ation goes together. St-302.2 VACLAM SWITCN AND CONTROLLER PERFORMANCE CHECK FOR RADIATION MONITORING GAS SAMPLE FLOWS (MOCTMLY) - UNIT 2 REV NO. 003 This revision was made to respecify tlie acceptance criteria to include The addition of channel cat (bration requirements and fitter fall alarm analysis of "At Found" and *As Left" data for switch action in automatic testing is consistent with FSAR, Section 11.4.4. The acceptance criteria controtters and loss of flow alarms. Format changes were made so that for controtter switches added are based on trending of previous. testing and detailed instructions with documentation of performance could be presented established such that the re wirements for saapting described in 10 CFR 30 to the performer in a manner that ensures consistent and ef fective removal and FSAR, Section 11.6.2.2.4, are provided far consistency. The changes do from service, surveillance test and data analysis, adjustment when not implement changes to the configuration of a permanent nature. The necessary, and return of af fected equipment to service. Also incorporated changes do not affect the way the e wipment operates, such that any new in this instruction are the channel calibration requirements for the accidents or metfunctions could affect the design objectives wf these monitors addressed and filter fait alarm testing. monitors. Changes to the controtter testing have a conservative effect on the margin of safety by effectively increasing the particulate filter concentrations for a given sample concentration.
" SI 303 SPARE 480V VITAL BATTERY CHARGER PERFORMANCE TEST - tm!T 0 REY WO. 002 This revision ircorporated the provisions of the 51 review program aruf This instruction is performed on the spare vital battery chargers only iAen added detailed instructions on the use of the Alber Discharge Load System. they are not connected to a vital battery board. Therefore, this procedJre cannot reduce the designed safety margin of the plant.
C SI-305.2 NYDR0cEN MITICAf t04 SYSTEM OPERA 81LITT - AMIT 2 REV NO. 007 This revision ensured comnt lance with AI-12, WCI-M2, EMSL-A36, and SI-1, This revision incorporated steps to ensure T.S. compliance and to clarify Appendia F. procedere. There was no modification to the entsting system or l s'afety-related equipment; and by complying with T.S. rewirements, the
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SUMMARY
g margin of safety was not reduced. SI-307.1 DEGRADED VOLTAr.E RELAY RESPONSE TIME TEST AND T19EER CALISRATION - UNIT 1 REV #0. 002 This revision added requiremer*ts to lif t additional leads from relays mder This revision did not change the generat test methodology or sequence. The test. probability of an occurrence or the consequences of an accident or motfmction were not increased. The change did act affect the *As left* condition of equipment, and the posaltritity for an accident of a dif ferent type was not created. The change ensured that the gathered data esos indicative of the required time #tay meeeurement. The margin of safety, as defined in the basis of any T.S., esas not, redaced.
** ST-307.2 DEGRADED VOLTAGE RELAY RESPONSE TIME TEST Ase TIfER CALISRATION - tmIT 2 REV NO. 001 This revision added performance modes, added range and accuracy of pe&tf, The changes made to the instruction try this revision were adelnistrative in and added the cousuon mode criteria requirements. nature. The testiry method and the intent of this instruction were not altered in any way. Because the testing remains the same as in the previous revision, at t T.S. requiraments are the same, and the mergin of safety was not reduced. ** $1-d@1 STEAM GEssERATOR SL0bOOuN COiditeeUOUS RELEASE - (MITS 1 AND 2 aEy no. 014 This revision was made to add the location of flow recorders and the the revisions were mostly for clarification to ensure T.S. compliance with reesirements for using each one. A caution was added that if the outside no changes in mettxxsology or acceptance criteria that would increase the teaYerature is less than or equot to 32 degrees Fahrerdielt, 0-15-27-225 probability of an occurrence or the consequences of an accident or will be declared inoperable. Also, if the outside temperature is less Ihan malfunctiore of equipment described. The possibility of a new type accident er equat to 32 degvees Fahrenheit, and there is a low levet in the dif fuser was riot created. No changes were made to the procedJre eAich would pond, teth 0-ts-27-225 and 0-it-27-175 wilt te declared incperat>te, and the compromise the T.s. compliance or cause the margin of safesy to be redated.
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y release will be discontinued. This revision etso clartfled the instruction and added a ref erence to LCO 3.11.1.1. l SI-603 MONTMLv RADIOCHEMICAL ANALYSIS LIQUID EFFLU[NTS - UNIT 0 l REV No. 0(Nr* This revision reflects the deletion of P-32 T.S. requirement due to a only chemistry tab activity is ef fected by the deletion of P-32 evaluation. January 14, T986, revision to the T.S. The detetton of P 32 was eweluoted in the T.S. revisf d Organfrationet name changes have no " N e on plant safety.
** SI-407.1 RADI0 ACTIVE CASEOUS WASTE Ef FLUENT-PARTICULATE AND IODINE RELEASE RATES FROM SNIELD Aan) AUXILIARY su!LDING VENTS (MONTMLY) - UNITS 0,1 Am 2 REV No. 005 This revision cancetted SI-407.1. At t the requirements of SI-407.1 are runs satisfied in SI 407.2. l l
SI-407.2 RA0104CTIVE GASEOUS CASTE EFFLUENT PARTICULATE AND IODINE RELEASE RATES FROM S4! ELD AND AUNILIART SUILDING BENTS MEKLY/ CONDITIONAL) - UNITS 0,1, AND 2 REV NO. 007 This revision corrected T.S. references and added a provision for SE/SRO The probability of an occurrence or the consegaences of an accident or authorization for work n radiation monitors and second anetyst metfunction of equipment leportant to safety were not increased by the verification (in accordance with AI-4 and AI-37). changes made to the procedure. The probability was decreased due to the )
^
more stringent controts on SE/SRO authorization and independent i verification for operstors on equipment. The mergin of safety esos not reduced in any seerew; because of the more adegante provisions for SE/SRO j f authorizations and ~.e iffratlys of operations on radiation monitors. f.
** SI-410.1 CONTAINMENT (LOWER COMPARTPENT) YENT TO AUXILI ART eUILDING ERMAUST - UNITS 1 AND 2 RED #0. 009 This revision incorporated revisie n tc T.S. (chance number 34 and 42). This revision only of fected the number of samples obtained within a 24-hour '
period. This does not affect the operation of epalpment or the type of work performed. ' The probability of an occurrence or the consequences of an
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g accident or malf unction were not irbased. The possibility for en
^
accident or malfianction of a dif ferent type was not created, and the margin of safety, as defined in the basis of any T.S., was not reduced. , f
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** 51-410.2 CONTAINMENT (UPPER, LOWER) PURGE - UNITS 1 AND 2 _
g , J
. REV NO. 009 This revisien included new sanple meth,ad numbers, chan2ed lef tium sampting Listing the reference and sawportig instrCMions, reo7ganizingid ts spts '
requirements, required sanpting and analysis in *ps 5 and 6, deleted a s and steps of instruction, and other changes TCr' clarification ard reference to SR 4.3.3.10 per Compliance Tracking aprt 86398, and added a enhancement purposes did not increase new title page. . did not create a dif ferent type ofrence. or%gTheprobabl*lty clerical andof an accident an
4 clarification changes did not affect the T.S. The margin of safety, as defined, was not reduced.
** SI-413 HYDROGEN AND OXYGEN CONCENTRATIONS IN THE WASTE CAS DECAY TANC - UNIT 0 REV No. 007 This revision added steps to Section 3.0, step 3.1, to ensure adequate This revision was made to format for adequa'te flush times and'to correct flush time of gas line and corrected Data Sheet 1.0 procedure step ntabers Data Sheet l ' frocedure step numbers. It also stated that the $1 to match precedure steps in instructions. m satisfies T.:.. requirements. This did not increase the probability of an
%. accident or malfunction, and the margin of safety was not reduced.
s
'T ** SI-415 CASEOUS EFFLUENT REQUIREMENTS (CROSS ALPHA, h08tE CAS, AND TRITIUM),- UNITS 0, 1, AND 2 -
t REV NO. 018 This revision replaced T.S. reporting I'mits with 10 CFR 50 reporting This procedure deals only with chemistry laboratory activities and does not limits which are more restrictive. affect equipment relating to operating the plant safety. These changes only help to ensure equipment is operable when needed, and the T.S. , reporting timits changed to 10 CFR 50 requirements did not decrease the margin of safety or increase or create the possibility of an accident not previously evaluated. s 1 l } Page No. 71 _ 02/22/85 _ . .
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s, Q- 4 StQUOTAN NUCLEAR PLANf
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1987 NRC ANWUAL OPERATING 4EPORT CHANGES TO PROCEDtEEC AS DESCRIBED IN THE SAR js DESCRIPTION SAFETY
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3
** SI-416 WASTE GAS DECAY TANK GASEOUS ACTIVITY - (JNIT 0 REV NO. 009 This revision was to clarify and to ensure that coriptience instrumentation This revistion was a procedere change to ensure representative sanpling is is used to verify WGDT pressure and that a representative sanple is being done and compliance instrumentation is being used. Because the obtained (50-OR-86-229R). ' change ensures adequate ftush time, the margin of safety was not red.ced, and there was no increase in the probability of an accident or malfunction.
** SI-417- RADI ATION MONITOR SETPOINT EVALUATION NOBLE GASES - GASEOUS EFFLtiENTS - UNITE 0,1, AND 2 REV NO. 005 This revision made correction to title changes within the chmoistry grotp The charp made were organi; F- nal changes and have no consequences in and revised the instruction in accordance with SI-1, Appendix F. regard to an accident or equ., .it malfunction. The margin of safety, as Adctitional revisions removed references to initial setpoint. adjustment, de.'ined in the basis of any T.S., was not reduced.
included setpoint timits, and provided separate treatment of RM-90-119 and RM-90-99.
** SI-418 GASEOUS RADWASTE TREATMENT - OPERA 81LITY VERif! CATION - (JNITS 1 AND 2 REV NO. C05 This revision cancetted the entire instruction. The T.S. require ants (SR This revision did not affect the piant equipment in any way, boy.atre it 4.11.2.4.2) of units 1 and 2 for demonstrating operability / verification of deals with only the operability requirements of the gaseous rcJwaste gaseous radwaste treatment systcms have been eliminated. This revision was treatment system which have been eliminated in'the T.S. This change did required to resolve CATS item 86-524. not decrease the margin of safety and did r.ot increase the probability of an accident or metfunction of equipment.
s
** SI-421 TURBINE BUILDING SUMP O!SCHARGE RADICACTIVITY DETERMINATION - t% ' O CEV NO. 008 This revision corrected the T.S. ref erence and added the metbd to this revision did not increase the probability of an acrident and did not determine turbine buitding e.p flow. The NPC timit was lowe .d to a more create the possibility of an accident or malfunction of a different type.
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g conservative value. Lowering the MPC Limit from 1.0 to .75 is more conservative, and t.;e margin of safety was not reduced. SI-422.2 00ARTERLY 10 CFR 50 APPEN0lx I IASE CALCUI ATIONS LIQUID EFFLUENTS - UNIT 0 REV NO. 002 This revision clarified the St arst made the format consistent with SI-1, this revision affected only the monthly tiquid effluent report format and Appendix F. It also deleted P-32 results because of a T.S. revision, and did not increase the probability of an accident. The acceptance criteria closed Discrepancy Report 86-205'., CATS item 86-732, QA Audit was'not altered by the changes. The margin of safety was not reduced. QSS-A 0023-D08, and CATS item 8/,-698. 't+ h REV No. 003 This revision corr vted calculations on pages 9-12 by adding a The revision did not increase the possibility for an accident or multiplication f actor of 1000 to correct the units. matfunction. The revision corrected the equation by the addition of a dilution mutt ptication factor to provide correct data units. .The change . 8 did not reduce the margin of safety, as defined in the T.S., because the T.S. remained unaltered. SI-431 COOLING TOWER BLoL00WN FLOWRATE DETERMINATION - (MITS 1 AND 2 REV NO. 005 This revision was made to delete steps for operating 0-RCV-77-43. This valve is now operated in accordav e with a Category A SOI. The probability of an accident was not af~ected, and the possibility of.an. acrident or malfunction of_a different type was not created. Directing the performer to the correct instruction and deleting the wrong instructions - increased the margin of safety. N 08-470.4 SNIELD BUILDING 10 DIKE SAMPLER FLOW ESTIMATION - UNITS 1 OR 2 Rett NO. 004 This revision reinstated SI-470.4, which was incorrectly deleted by This revision implemented SI-470.4, which was incorrectly deleted by revision 3. It also included minor organizational changes and revision 3. There was no increase in the prcbability of an accident, and
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DESCRIPTION SAFETY
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I - . clarifications. the margin of safety was not seduced, because this Si more accurately determines the flow through the iodine sampter. .
**: $1-476 CLEANING AND OPERATIONAL CHECK OF LIQUID RADIATION MONITOR FLOW SWITCHES (Cf*DITIONAL) - UNITS 0, 1, AND 2 REW NO. 008 This revision cancelled SI-476. The LEM sensor flow switch had been replaced by a'universat-type flow '
se'trh, and this instruction was no longer applicable. '
' ** 'SI-483 PROCEDL1tES FOR REMOVING A REACTOR PROTECTION C#tANNEL FROM SERVICE - UNITS 1 AND 2 -REV NO. 003 This revision updated T.S. time timits to correspond to T.S. changes and This revision did not change the method of removing a protection channet was' revised in acccrrlance with SI-1, Appendix F. from service or returning it to service. The probability of an accident or.
malfunction uas not increased. The possibility for an accident or mattunction of a different type was not created, and the margin of safety.
. was not reduced.
** 51-487 SENTRY POST ACCIDENT SAMPLING SYSTEM OPERASILITY VERIFICATION AND CALIBRATION - UNITS l'AND 2'
' REV NO. 002 ' Tiits revision added the precedure for calibration of the post accident This revision echanced the post accident saapting L/ stem capability to ; j sampting system gas chroaatography for contairnent air analysis for perform conta'irment air hydw analysis. It ensures the accuracy of. hydrogen determination in the instruction.' . hydrogen determination in the containment air, thus leproving the
~
reliability and minimizing any accident already evaluated in the FSA). 's -; This revision did not alter any T.S.T thus, the margin 6f safety was not li reduced. s t A ,f,. .
** SI-4C8 RCS RTD SENSOR ' VERIFICATION OF CALIBRATION f ' UNITS 1 AND 2
. LEV N'J. 000 This'new instruction schedules and performs TI-60. This instruction performs TI-60 end reviews the results. The margin of v, 1,
.~ , l '
s .a): , J t M F 'D D' ef
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Page No. 74 02/26/88 SEoOOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
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I safety, as defined in the basis of any T.S., was not reduced.
- SI-532.5 0FFICE OF ENGINEERING, REPROGRAPHICS, AND TRAINING BUILDING FIRE DETO: TORS REV NO. 000 This revision deleted testing of one-shot heat detectors from the SI and
~
The testing instruction and method have not changed in the procedure. included detector XS-13-119fC as shown on drawing. Also, detectors These detectors have no bearing on nuclear safety. This procedure does not XS-13-87RA and -89RA are no longer instatted, because the location of change out equipment or alter circuitry. Because this Si is a non-T.S. SI, detectors over printing machinery caused spurious alarms. the margin of safety was not reduced and there was no increase in the probability of an accident or matfunction occurring. " SI-532.6 CRVI SMOKE DETECTOR TEST - UNIT 0 REV No. 000 This instruction was written to perform the annual functional test for This instruction implemented FSAR, Section 9.4.1.4, thsch' requires that smoke detectors XS-31A-004A and MS-31A-0038 which initiate a CRVI. thermostats and smoke detectors be tested periodicatty. This annual functional test is for non-T.S. smoke detectors.
- SI-545 CONDENSER PERFORMANCE TEST REV NO. 003 This revision cancetted $1-545. This procedure was not safety related; therefore, the margin of safety was not reduced.
- SI-557 FEEDWATER HEATERS PERFORMANCE TEST - UNITS 1 AND 2 REV NO. 003 This revision cancetted SI-557. This procedure was not safety related; ther fore, the margin of safety was not reduced.
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) ** S1-566 ERCW FLOW VERIFICATION TEST - UNITS 1 AND 2 LEV No. 016 This revision was made for the fottowing reasons: (1) Curves depicting mininue flow versus tenperature requirements are used (1) Added mininua flow versus tenperature curves to be used to evaluate to evaluate operability of any safety-related ERCW conponent that is operability of any ERCW conponent that receives insuf ficient flow. receiving insufficient flow. This insufficient flow rate may correspond to an ERCW inlet temperature that is test than 33 degrees Fahrenheit as (2) Revised flow acceptance criteria to reflect more detailed instrument required by T.S. 3/4.7.5. However, the component will remain operable as '
inaccuracies. Long as the reduced temperature requirement is greater than the actual intet tenperature. Insufficient "As-Found" flow rates are evaluated, and (3) Revised to throttle auxiliary control air compressor with the upstream an attempt is made to reestablish the flow rate that corresponds to 83 isolation valve instead of the downstrears throttle valve. This was done to degrees Fahrenheit. If the flow rate that corresponds to 83 degrees decrease. pressure of the ERCW side of the conpressor. Fahrenheit cannot be obtained, the operability of that component is administratively limited to the temperature that corresponds to the reduced (4) Revised to perform flow verification with the ERCW ptmp discharge "As-Left" flow rate. This will be accomplished by revising the SI-3 valves throttled to provide margin for ERCW pump degradation. ultimate heat sink tesperature acceptance criteria for that component, and 51-566 will require verification that the required SI-3 revision is the latest revision. (2) Flow acceptance criteria were revised to reflect instrument inaccuracies. (3) The ERCW flow to the auxiliary control air compressor was throttled
'with the upstream isolation valve instead of the downstream throttle valve.
This action helped to ensure that the ERCW water pressure remained below the design pressure of the auxiliary control air compressors. Any valve cavitation that occurrco during testing was documented and dispositioned in this procedure. The acceptable ftow rate had a maximum limit to minimize the effects of pressure and cavitation.
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(4) The performance of SI-566 established a baseline for ERCW punp degradation by throttling the ERCW pump discharge valves. This bt.4eline is in the form of a flow rate differential pressure, somewhere between 0 and 5 psid, depending on capability to meet the required ERCW flow rates. Af ter the performance of SI-566, the procedure was revised to reflect this besetine different?at pressure. While under balancing conditions, throttling the dischs.rge valves to a differential pressure of 5 psid resulted in en appro<imate 6-percent reduction of the total ERCW flow. .To ensere that plant se;fety was not adversely affected by this pre-baseline throttling, the ERC'J train was not tested if an ERCW component on the opposite train was not operable. Also, heat loads that could not be handled by the train under testing were transferred to the opposite train. These revisions did not increase the probability of an accident or malfunction, and the possibility for an accident of a different t p was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
- SI-632.0 AUXILIARY BUILDING COMBINED $YSTEMS EXTERNAL LEAKAGE REV NO. 004 This revision made minor changes to organization names, added T.S. Changing the nomenclature did not have any detrimental effect on the margin 6.8.5ati) (adninistrative requirements for teak reduction program), deleted of safety as defined in any T.S. Leakage trending can only enhance the a one-time only requirement to report the finding to the NRC, and added the plant's performance abitity. The NRC report was a one-time only NRC requirement to have a trending program for systems and valve leakage on requirement, and i'ts deletion had no effect. The addition of T.S.
tinn that cover rad water. 6'8.$a(l)
. ensures that this requirement will not be accidently lost.
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l SI-632.2,"AUXILIARY BUILDING SAFETY INJECTION SYSTEM EXTERNAL LEAKAGE - UNITS 1 AND 2 REV NO. 009 This revision deleted the annual report to NRC requirement, added T.S. Addition of procedural performance steps, component description, and the 6.8.5.a to the reference section, added a detailed cor.ponent description, compliance with T.S. 6.8.5.a increased the margin of safety. and added procedurat performance steps in compliance with SI-1, Appendix F. SI-632.5 AUXILIARY BUILDING REACTOR COOLANT SAMPLE SYSTEM EXTERNAL LEAKAGE - UNITS 1 AND 2 REV NO. 004 This revision added information to indicate that the information gathered This revision did not introduce any new plant configuration, operation, or would enter the Leak reduction trending program and added drawing methodology in the test performance. This revision only. inspects 47W610-43-6 to the reference section. components in piping lines and does not alter any' tinetps f rom those in the previous revision. These changes did not alter T.S. The margin of safety was not reduced. The probability of an accident or malfunction was not increased. 4
** SI-654 FIRE HEADER VALVE SEALS INSPECTION - UNITS 0, 1, AND 2 REV 10. 011 This revision detered at t T.S. valves which were incorporated into SI-167 Incorporating att T.S. valves in SI-654 into $1-167 and incorporating att and incorporated ali non-T.S. valves from SI-167 into SI-654. Valves non-T.S. valves in SI-167 into SI-654 had no effect on the margin of 0-26-725 and 0 26-328A were removed from the valve checklist. safety. Valves 0-26-725 and 0-26-328A were removed under ECN 5198 and did not affect the margin of safety. The probability of an occurrence or the consequcoces of an accident or malfunction were not increased. The'
- possibitity for an accident or sulfunction of a dif ferent type was not '
created. REttNO. 012 This revision was made to change the required position of fire heack r valve The probability of an accident or malfunction of equipment previously 0-26-643 (oit dispensing roon header isolation valve) to the CLOSED evaluated in the SAR was not created. The possibility of an accident or
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l position. The open spray nozzles will spray down the oil Jispensing room malfunction of a differert type was not created, and the margin of safety if the valve is in the required OPEN position. was not reduced by this change.
** SI471 CONTROL ROD DRIVE MOTOR CENERATOR OVERCUE ,NT AND UNDERVOLTAGE RELAY CAllBRATION TESTS - UNITS 1 AND 2 REV NO. 004 This revision cancetted the instruction. This SI was cancelled, because the control rod drive relays are not CSSC or T.S. The functional test of the relays has been transferred to PM 1829-085, unit 1, and PM 1830-085, unit 2. There are no T.S. requirements, so the PM program will be sufficient to maintain operability. There was no increase in the probability of an accident or malfunction, and the margin of safety was not reduced.
** $1-681 CONTROL ROD DRIVE MOTOR CENERATOR RELAY FUNCTIONAL TEST REV No. 003 This revision cancelled the instruction. This SI was cancelled, because the control rod drive relays are not CSSC or T.S. requirements. The functional test of the relays has been transferred to PM 1829-085 and PM 1830-085. - There are no T.S. requirements, so the PM program will be sufficient to maintain operability. There was no increase in the probability of an accident or malfmetton, and the margin of safety was not reduced.
" SI-688.2 FUNCTIONAL TEST FOR ACCIDENT RADIATION MONITORING STSTEM, MONTNLY - UNIT 2 REV NO. 003 This revision added reference sis which show whece the high voltage The additional sources to obtain the high voltage calibration values were calibration values for radiation monitors are performed and added a added for clarification. The method and frequency of performing the statement that voltage values are maintained in the instrunent shop on functional test were not altered by the revision due to RM-90-280 being cards. This resision also changed the setpoints on RM-90-273. -274, and inoperable because of a detector and radiation analyzer mismatch. An FCR
-280 to be in agreemer t with the instrument tabs. A statement was added to will be submitted to clear this discrepancy. RM-90-280 is the area monitor
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Page No. 79 02/22/88 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 WRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBE 0 IN THE SAR DESCRIPTION SAFETY QMMARY g inform the UO that alarms on 2-M-30 would be actuated during calibration. for the post accident sampling facility and is non-CSSC. This revision did not delete any functional test requirements. The probability of an occurrence or the consequences of an accident were not increased. The possibility for a dif ferent type accident or met function of equipment not previously anatyred by the SAR was not created, because RM-90-273, -274, - and -280 are non-T.S. monitors. The margin of safety was not affected.
** SI-689 AUXILIARY CONTROL AIR OPERABILITY TESTS - UNIT 0 REV No. 005 This revision changed the acceptance criteria of the compressor operability The minimum required pressure range is 70 psig. This is in line with test tests. The range was changed from a range of 75 to 102 psig to a range of equipment accuracies and remains conservative. There was no margin of 73 to 102 psig. Also added SRO signoffs from each unit rather than UO safety defined for this system in the T.S.
signoffs from each unit.
** SI-192 ERCW CHLORINATION - UNITS 0, 1, AND 2 EEV NO. 002 This revision incorporated the pmchlist dated November 10, 1986, deleted a this revision did not affect plant safety. The removat of redundant reference d ich is redundant, clarified passage regarding purpose, stated references, correcting nomenclature, and clarifying the purpose of the that St is non-T.S., and identified consnon equipment. It corrected drawing 'ostruction did not affect the intent / performance of the St. The revision deficiencies identified in th SON 1986 walkdowns. The drawings are being at60 identified equipnent and required obtairiing per1 mission f rom the unit 1 chmged to match the in-field tags through FCR 4961. This SI requires and unit 2 SR0s to run the test. The changes did not increase the permission from the units 1 and 2 SRos to run the test. probability of an accident or matfunction and did not create a different type of accident. Because the SI is non-T.S., the margin of safety remains unchanged.
** SI-693 RCW AND RSW CHLORINATION - UNITS 1 AND 2 REV NO. 002 This revision inco porated the punchlist, added pieces of equipment Clarification of the procedure, correction of typographical errors, and
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previously omitted, clarified and enchanced the procedure, and specified addition of equipment which is normally operated did not increase the that the procedure is rion-T.S. prot;obitity of an accident. Because the procedure is specifled as non-T.S., the u rgin of safety was not affected.
** S1-702 FUNCTIONAL TEST OF REACTOR COOLANT RfD BYPASS FLOW SWITCHES (CONDITIONALLY) - UNiiS 1 AND 2 REV NO. 003 This revisicn cancetted the entire instruction. The calibrations that were previously performed in SI-702 are now performed in IMI-68, Appendix B and Appendix C. ** SI-714 ExiRACTION STEAM PIPE WALL DECRADATION MONITORING PROGRAM - L18iS 1 AND 2 REV No. 000 This instruction was initiated to address potential watt thinning as a insulation was temporarity removed for ulti , sonic testing of pipe watt result of erosion corrosion in suspect areas of extraction steam piping. thickness. Pipe which had degradated to less than allowable well thickness was replaced. The extraction steam system is not addressed in the T.S. No margin of safety was reduced. ** SI-720 CALIBU.9 dm 0F AUXILIARY FEEDWATER TERRY TUR8]NE CONTROLS REFUELING OUTAGE - UNIT 2 REV No. 000 This revision provided a more detailed description of the tocation of this revision corrected typographical errors and was administrative in '
XS-46-57 and changed the range on voltage. Location of SM-46-56 is L-326A, nature. The addition of the location of the panet did not affect safety, not 2-3268. and the changes ensure that the instruction will be run correctly.~ secause this ch wige did not af f ect the T.S., the ausgin of saf ety was not redixed.
** SI-722 CMDS CROSS REFERENCE - UNITS 0, 1, AND 2 REV NO. 000 This instruction was written to provide a cross-reference of OMDS values The providing of dMDS cross-reference has no effect on the probability or which fulfitt the OMDS requirement, the frequency the instruction is gossibility of an accident. The, margin of safety was not affected by the performed, and the EQ frequency requirement.' development of a new instruction which is used as a reference.
1
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g
** S t - 722.4 CMOS VALVE STROKING (9 MONTH FREQUENCY) - UNITS 1 AND 2 REV NO. 000 This instruction was written to satisfy EQ stroke requirements on RCS The stroking of these valves was previously done in another SI. This SI watves. has a different frequency, but the stroking procedure is the same as the previous St. The frequency change did not reduce the margin of safety.
S1- 726 INTERNAL INSPECTION OF MFW/AFW/RHR CHECK VALVES DURING REFUELING OUTAGES - UNITS 1 AND 2 REV No. 000 This St was written to inspect the internals of selected MFW, ATW, and RNR The additional valve inspection requirements resulted in increased system' check valves during refueting outages. rettability. This added assurance that these valves will function and perform as designed in the system they are a part of. This instruction did not reduce the safety margin in any way. S 4
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l . O' O O S MMARY OF O O PROCE3JRE O ! O CHANGES O O S P ECI A; O ! O ES- O O O N S' R L C ONSo O O I
Oage No. 1 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION GAFETY
SUMMARY
j 00 STI-C35 DECRADEO VOLTAGE TEST FOR MFIV'S BRAKE SOLENOIDS REV NO. 000 This special test was written for degraded voltage testing of the MFIV's This test will prove or disprove the operability of the brakes during an brake solenoids. accident or undervoltage situation. The test will be performed in a mode where feedwater isolation is not required for any FSAR analyzed accident. Att the system components af fected by this procedure will be certified operable before re-entry into an applicable mode., This test will not inc.' ease the probability of an occurrence or the consequences of an accident or malfunction. It will not create the possibility of an accident, and the margin of safety will not be reduced.
*o STI-007 WESTINGHOUSE DEMONSTRATION OF ICE CONDENSER SERVICING TOOLS - UNIT 1 REV NO Col This revision concetted the instruction. This procedure for demonstration of Ice condenser servicing tools was <
obsolete.
~!
00 STI-015 QUALIFICATION TESTING OF WEDGE SOLT ANCHORS REV NO. 000 This special test was written to perform qualification testing of wedge The probability of an accident will not be increased, and the possibility bott anchors in the LLRW storage buildings. of an accident or malfunction of a different type will not be created. The margin of safety for the testing of wedge bolts is not defined in the basis of any T.S.
** ST1-017 OC HIGH VOLTAGE TEST FOR SELECTED UNIT 2 1E CABLES IN VERTICAL DROP CONFIGURATION >
CEV NO. 000 This dc high voltage test witL be performed on selected 1E cables to This test will be perfornu:d on one safety train at a time, white ensuring alleviate concerns regarding cable damage. the redundant train is operable to support mode 5 operation. The involved systems and equipment will be isola.ed and protected.' After testing, the f 1
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6 plant design configuration witt be restored and documented. The plant operating parameters and system setpoints will not be altered. Functional tests and required sis will be performed at the conclusion of cable testing to ensure T.S. compliance. REV CD 001 This revision excluded conan connector wires from tie scope of the test and This test cetts for testing of cable insulaticn at high de voltage. It is, added visual inspection and cleaning of the conductos insulation which is therefore, required to isolate the conax connectors f rom the cable accessible. Athe corrected typographical error. c.onductors at the Raychem sleeves. The cones r.onrwctors will be reconnected to the cables at the conclusion of the test. This STI will be performed in accordance with STI-17 RO and other applicable procedures to ensure no other system or component is af fected and the margin of safety is not reduced. S78-018 DC EMERGENCY LIGNTS INRUSH CURRENT - UNITS 1 AND 2 REV NO. 001 This revision was made to incorporate ICF 87-482 and ICF 87-474. ICF sy ensuring that electrical connection botts are not over torqued, the 37-482 changed torquing value range to agree with bolt size installed in margin of safety will be increased. Testing with a saatt number of lights the field. ICF 87-474 added note to steps 6.2.1, 6.3.1, 6.4.1, and 6.5.1 nonoperational will provide DNE a basis on whica calculations of inrush to indicate acceptability of lights being nonoperational. This attowed current can be determined. No margin of safety, as defined in the basis of running of the test if a small nunter of lights were not working, any T.S., will be reduced.
** ST1-019 DC HIGH VOLTAGE TEST FOR SELECTFD 1E CABLES WITH POTENTIAL FOR CA8tE JAMMING - UNITS 1 AND 2 REV NO. 000 This instruction was written to perform a de high voltage test on selected Th6s test will be performed on one safety train at a time while ensuring 1E cables to atteviate concerns regarding cable damage. the re&ndant train is operable to support mode 5 operation. In addition, all the involved s'ystems and componants'will be isolated and protected.
The test will not permanently affect the plant configuration. Plant design configuration will be restored, and ti,e plant operating parameters or
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l system setpoints will not be attered. The probability of an occurrence or the consequences of an accident or malfunction are not increased. The possibility of an accident of a different type wilt not be created, and the margin of safety will not be reduced.
** STI-021 DC HIGH VOLTAGE TEST FOR SELECTED 1E CABLES WliN POTENTIAL FOR CABLE PULLSf DAMAGE CONDUli MC 17348 - UNITS 1 AND 2 REV to. 000 This dc high voltage test is performed on selected 1E cables to atteviate The performance of STI-21 RO does not increase the probability or concerns regarding possible damage due to cable puttby in conduit. consequences of an accident previously evaluated in the FSAR and does not increase the possibility or consequences of a malftsiction of equipment inportant to safety, because the test is performed on safety train B for specific components, and train A is operable to stoport att equipment ti.at -
is necessary to function during mode 5 operation. STZ-27 RO ensures that att test cables and conciactors disconnected, tested, :md restored do not affect equipment or components whose failure or actua; ion may increase the probability or consequences of an accident or metfunction of equipment important to safety. Plant design and construction ensure adequate isolation between the test cables erwl other cables. The margin of safety, as defined in the basis t,f the T.S., is not reduced. The plant operating parameters or system setpoints are not affected or altered.
** STI-023 DC NIGN VOLTAGE TEST FOR SELECitD 1E CABLES WITN POTENTIAL TOR CABLE PULLBY DAMAGE CONDUIT MC17484 - UNilS 1 AND 2 KEV C). 000 This special test is performed on selected 1E cables to atteviate concerns This test will be performed on saf ety trt.in A copr* meets. Train B will be regarding possible d.mge due to cable puttby in corduit. operable to support att equipment that is necessary to function dering mode 5 operation. It will ensure that the test cable, and conductors that are disconnected, tested, and restored (as well as other cables and conductors disconnected and restored) do not af f ect equipment or cone;rwnts
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I whose f ailure or actuation s:sy increase the probability or consequences of an accident or malfunction of @ipment inportant to safety. Plant design and construction ensure adequatt isolation between tt;e test cables and other cables. This test will n$t affect any equipment necessary for mode 5 operation. The margin of safety, as defined in the Lasis of the T.S., is not reduced. C sit-024 DC MIGH VOLTAGE TEST FOR SELECTED 1E CABLES WITN POTENTIAL FOR CABLE PULLBY DAMAGE CONOUIT MC1750A - UNITS 1 AND 2 REV NO. 000 This STI was written to perform a de high voltage test on selected 1E This test will be performed on one safety train at a time, d ile ensuring cables to atteviate concerns regarding damage due to cabte pultby in the redundant train is operable to steport mode 5 operation. Att the conduit. involved systems and conponents will be isolated and orotected. The plant design configuration will be restored and documented. The plant operating - parameters and system setpoints will not be affected or altered. The probability of an occurrence or the consequences of en accident or matfunction are not increased. The margin of safety is not reduced. Civ No. 001 This revision changed the test method from testing groups of cable in This change better supports the validity of the test results, and the conduit MC1750A to testing each individual conductor in conduit MC1750A. margin of safety is increased. There is no USo involved. CD STI-025 DC HIGH VOLTAGE TEST FOR SELECTED 1E CABLE PutL8Y DAMAGE CONDuti MC 1754 A - UNITS 1 AND 2-REV NO. 000 This de high voltage test will be performed on selected 1E cables to The performance of STI-25 RO wilt not increase the pr*bability or alleviate concerns regarding possible damage due to cable pu!!by in consequences of an accident previously evaluated in nt'e FSAR. It will not conduit. Increase the probability o* consequences of a malfunction of equipment important to safety, because the test will be parfors:-d on safety train A for specific components, and train 8 will be operable to stoport all
<>quipment that is necessary to functfon during mode 5 operatlon. STI-25 RO
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Pcce No. 5 02/26/83 SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
ensures that all test cables and conductors that are discynected, tested, and restored do not affect equipment or componente W se failure or actuation may increase the probability or consequences of an accident or matfunction of equipment important to safety. Plant design and construction ensure adequate isotation between the test cables and other cables, The margin of safety, as defined in the basis of the T.S., is not reduced. Plant operating parameters or system setpoi.Es will not be affected or altered. i W STI-027 DC HIGN VOLTAGE TEST FOR SELECTED 1E CA8tES WITH POTENTIAL FOR CABLE PULLBY DAMAGE CONDUlf MC 1751A - UNIT 1 AND 2 REV No. 000 This dc high voltage test witt be performed on selected 1E cables to The performance of STI-27 RO will not increase the probability or alleviate concerns regarding possible damage due to cable pullby in consequences of an accident previously evaluated in the FSAR. It will not concksit. increase the probability or consequences of a malftmetion of equipment inportant to safety, because the test will be performed on safety train A for specific components, and trair 8 will be operable to support all equipment that is necessary to function during mode 5 operation. STI-27 RO ensures that att test cables and conductors that are disconnected, tested, and restored will not affect equipment or components whose failure or actuation may increase the probability or consequences of an accident or malfunction of equipment important to safety. Plant design and construction ensure adequate isolation between the test cables and other cables. The margin of safety, as defined in the basis of the T.S., is not reduced. .The plant operating parameters or system setpoints will not be affected or attered.
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Page No. 6 02R6/88 SEQUOYAH NUCl[AR PLANI 10 CfR 50.59 1987 NRC ANNUAL OPERATING REPOkT CHANs.ES TO PROCEDURES As DESCRIBED IN THE SAR DESCRIPTIO4 SAFETY
SUMMARY
l STI-028 DC HIGH VOLTAGE TEST FOR SELECTED 1E CABLES WITH POTENTIAL FOR CABLE PULL 8Y DAMAGE - UNITS 1 AND 2 REV NO. 000 The test will be performed on selected 1E cables to alleviate concerns The test will be performed on safety train A for specific components.tisted regarding possible damage due to cable puttby in conduit MC1605A. In attachment 2 of 571-28 R0. Train B will be operable to support att equipment that is necessary to function to support mode 5 operation. The test will be performed in accordance with STI-28 R0 and other applicable procedures to ensure that the test cables and corductors that are disconnected, tested, and restored (as welt as other cables and conductors disconnected and restored) will not af fect egalpment or components whose f ailure or actuation may increase the probability or consequences of an a:cident or matfunction of equipment important to safety. The plant design and construction ensure adequate isolation between the test cables and other cables. The margin of safety, as dafined in the basis of the T.S., wilt not be reduced.
- STI-029 DC MICH VOLTAGE TEST FOR SELECTED 1E CA8tES WITH POTENTIAL FOR CABLE PULLBY DAMAGE CONOUIT MC 1606A - UNITS 1 AND 2 REV CD. 000 This de high voltage test will be performed on selected 1E cables to The performance of STI-29 RO will not 39eresse the probability or '
atteviate concerns regarding possible damage due to ceble puttby in consequences of an accident previously evaluated in the fSAR. It wilt not conduit. increase the possibility or consequences of a malfunction of equipnent inportant to safety, because the test will be performed on safety train A - for specific components, and train B will be operable to stoport att equipment that is necessary to function during mode 5 operation. STI-29 ensures that att test cables and corductors disconnected, tested, and restored will not af fect ecuipnent or components whose f ailure or actuation may increase the probability or consequences of an accident or malfunction of equipment important to safety. Plant design and ccnstruction ensure adequate isolation between the test cables and other cables. The margin of
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r Page No. 7 ~ 02/26/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
I safety, as defined in the basis of the T.S., will not be reduced. The plant operating parameters or system setpoints will not be affected or altered.
** Sil-032 OC HICM VOLTAGE TEST FOR SELECTED 1E CABLES WITH POTENTI AL FOR CABLE PULL 8Y DAMAGE CONDUIT MC17319 - UNITS 1 AND 2 REV NO. 000 This test will be performed on selected 1E cables to atteviate concerns This test will be performed on safety train B. Train A will be operable to regarding possible damage &e to cable pullby in conduit. support all equipment that is necessary to function daring mode 5 '
operation. This instruction ensures that the test cables and conductors disconnected, tested, and restored will not af fect equipment or components whose failure or actuation may increase the probability or consequences of an accident or metfunction of equipment important to safety. Plant des'gn and construction ensure adequate isolation between the test cables and other cables.
** STI-033 DC MIGN VOLTAGE TEST FOR SELECTED 1E CABLES WITN POTENTIAL FOR CABLE PULLBY DAMAGE CONDUIT MC14938 - UNITS 1 AND 2 EEV NO. 000 T5is test will be performed on selected 1E cables to alleviate concerns This test will be performed on safety train B. Train A will be operable to regarding possible damage due to cable pullby in conduit, support att equipment that is necessary to function during mode 5 operation. This instruction ensures that the test cabtes and conductors disconnected, tested,'and restored will not af fect equipment or comporwnts whose failure or actuation may increase the probability or consequences of an accident or malfuntion of equipment important to safety. Plant design and construction ensure adequate isolation betwetn the test cables ano other cables.
s
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k: , Page No. 8 02/26/33 SEOUOYAH NUCLEAR PLANT 10 CFR 50.59 1787 NRC ANNUAL OPERATING REPORT CHANLES TO PROCLDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
** STI-034 DC HIGN VOLTAGE TEST FOR SELECTED 1E CABLES WITH POTENTIAL FOR CABLE PULLBY DAMAGE CONDUIT MC14978 - UNITS 1 AND 2 REV h0. 000 This test will be performed on selected 1E cables to atteviate concerns This test will be performed on safety train B. Train A will be operable to regarding possible damage due to cable puttby in condait. support all equipnent that is necessary to function during mode 5 '
operation. This instruction ensured that the test cables and conductors disconnected, tested, and restored will not af fect equipment or corrponents whose f aliure or *ctuation may increase the probability or cc%egaences of an accident or malfunction of equipment important to safety. Plant design and construction ensure adequate isolation between the test cables and other cables.
** 77I-037 CABLE TRACING TEST ON POWER AND CONTROL CABLES FOR SELECTED 1E EQUIPMENT ERCW PUHP N-B - UNIT 1 REV NO. 000 This STI was written to perform cable tracing to verify that power and STI-37 RO will be performed within the safety evaluation provided in FSAR, controt caote routing to the ERCW puup N-8 is consistent with applicable Section 9.2.2.3.2, and within the T.S. basis described in 3/4.7.4. Cable ,
plant drawings. routing verification witt introduce a low-voltage, low-amperage trace signal to the power and control cables of ERCW pump N-8. These cables will not be exposed to voltages and currents in excess of their design.
** STI-038 CABLE TRACING TEST ON POWER AND CONTROL CABLES FOR SELECTED 1E EOUIPMENT ERCW PUMP R-A - UNIT 2 REV NO. 000 This STI was written to perform cable tracing to verify that power and STI-38 RO wilt be performed within the safety evaluation provided in FSAR, control cable routing to the ERCW ptmp R-A is consiktent with applicable Section 9.2.2.3.2, and within the T.S. basis described in 3/4.7.4. Cable plant drawings. routing vernfication will introduce a low-voltage, low-aaperage trace signal to the power and control cables of ERCW pump R-A. These cables will not be exposed to voltages and currents in excess of their design.
I
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E Page No. 9 02/26/88 SEQUOTAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING RF. PORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFEIT
SUMMARY
4
- STI-040 CABLE TRACING TEST ON POWER AND CONTROL CABLES FOR SELECTES 1E EQUIPMENT 2-FCV-67-138 REV NO. 000 This STI was written to perform cable tracing to verify that power and The test will be performed within the safety evaluation provided in FSAR, controt cable routing to containment vent cooter valve 2-FCV-67-138 is Section 6.2.4.1, and T.S. basis 3/4.6.3. Valve 2-FCV-67-138 will be consistent with applicable plant drawings.- tenporarity taken out of service for the test during cold shutdown.'
Section 6.2.4.1 of the FSAR states that contairmw:nt isolation is not required during cold shutdown. The cables witt not te esposed to vottages and currents in excess of their design.
" STI-042 DC HIGN VOLTAGE TEST FOR SELECTED UNIT 2 1E CABLES (SILICONE RUBBER CABLES) - UNIT 2 - TRAIN A REV NO. 000 This instruction will perform a dc high-voltage test on selected unit 2 1E This test will not increase the probability or consecuences of an accident cables to atteviate concerns regarding cable damage. previously evaluated in the FSAR. The test will be performed on safety-train A with safety train 8 operable to support all equipment that is necessary to function & ring mode 5 operation. The test will be performed in accordt.nce with STI-42 RO which ensures that the test cables and conductors disconnected, tested, and restored (as well as other cables and conductors disconnected and restored) do not af fect equipment or components -
whose foiture or actuation may increase the probability c*r consequences of - an accident or metfunction of equipment important to safety. The plant design and construction ensure adequate isolation between the test cables - and other cables. The margin of safety, as defined in the basis of the T.S., is not reduced.
** STI-043 OC HIGH VOLTAGE TEST FOR SELECTED UNIT 21E CASLES (SILICONE RUBBER CABLES) - UNIT 2 - TRAIN B CEV NO. 000 This instruction w,itt perform a dc high voltage test on selected unit 2 1E This test does will not increase the probability or conseqtumces of an cables to atteviate concerns regarding cable damage. accident previously evaluated in the FSAR. The test will be perforned on
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Page No. 10
'02/26/88 SEOLPYAN NUCLEAR PLANT 10 CTR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
)
safety train B with safety train A operable to sLpport all equipment that is necessary to function during mode 5 operation. The test will be performed in accordance with STI-43 RO 6Alch ensures that the test cables and conductors disconnected, tested, and restored (as well as other cables and conductors disconnected and restored) do not af fect equipment or components whose f ailure or actuation may increase the probability or consequences of an accident or malfunction or equipment important to safety. The plant design and construction ensure adequate isolation between the test c.bles and other cables. The margin of safety, as defined in the basis of the T.S., is not reduced.
" STI-052 DC HIGH VOLTAGE TEST FOR CLASS 1E 10 Cf R 50.49 SILICONE RUBBER INSULATED CABLES REV NO. 000 This test was written to test class 1E 10 CFR 50.49 silic<>ne rubber Cable testing will be performed <>n cables in both safety trains for insulated cables to atteviate concerns regarding possible cable damage. specific components while the plant is in mode 5. The specific components affected by the test are not required to be functional during mode 5 operation. The test cables and conductors disconnected, tested, and restored (as well as other cables and conductors disconnected and restored) will not affect equipment or components whose failure or actuation may increase the probability or consequences of an accident er malftmetion of equipment important to safety. The plant design and construction ensure adequ'a te isolation between the tast cables and other cables. - The margin of safety, as defined in the basis of the T.S., will act be reckJced.
** STI-053 DC HIGH VOLTACE TEST FOR CLASS 1E 10 CFR 50.49 $1LICONE RUBBER INSULATED CABLES REV N0. 000 This test was written to test class 1E 10 CFR 50.49 silicone ruta >cr Cable testing will be performed on cables in both safety trains for insulated cables to at teviate concerns regarding possible cable damage. specific components white the plant is in mode 5. The specific conponents
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Page Ko. 11 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
l affected by the test are not required to be functional during mode 5 operations. The test cables and conductors discomected, tested, and restored (as well as other cables and conductors disc;,nnected and restored) will not af fect equipment or components whose f alture or actuation may increase the probability or consequences of an accident or malfunction of equipment inportant to safety. The plant design and construction ensure adequate isolation between the test cables and other cables. The margin of safety, as defined in the basis of the T.S., will not reduced. STI-(54 CABLE TRACING ON SELECTED CONTR01. CA8LES REV HO. 000 This test will be performed within the safety evaluation provided in FSAR, Cable routing verification introduces a low-voltage, low-asperage trace Section 9.5.1, and T.S. basis 3/4.3.3.8. Att the requirements of PHYSI-13, signal to the relay contacts of controt cables of fire detection zones 127, Appendix C, are to be met. 128, 130, and 133. These cables will not be subjected to voltages and currents in en.ss of their design. After tracing is complete, the fire detection zone relay contact cables will be restored and proven operable per fmctional testing. The probability of an occurrence or consequences of an accident will not be increased. The possibility for an accident or notfunction of equipment of a dif ferent type than previously evaluated ulti not be created. The margin of safety, as defined in the basis of any T.S., will not be reduced.
- STI-061 ERCu/ AUXILIARY CONTROL AIR COMPRESSOR TEST - UNITS 1 AND 2 REV NO. 000 This STI performs testing on various ERCW equipment to verify the heat toad At no tim during the test will the ERCW flow be allowed to decrease below removing capability and record the maximum flow available. It also the minimum allowable limit documented in $1-566 (ERCW flow balance). Att establishes a new throttle valve and its position for both auxiliary auxiliary controt-air conpressor testing will be performed af ter the control air compressors based on a min / man flow. Relocation of the conpress)r is placed in an inoperable status in conpliance with applicable
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m . - Page No. 12 02/22/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRl8ED IN THE SAR DESCRIPTION SAFETY
SUMMARY
throttle valve will prevent over pressurization of the conpressor which has T.S. No new accident or malfunction witL be Created by performing this a tower design pressure rating than the ERCW system. test white in modes 5 or 6. There will be no re&ction in the margin of safety. STI-062 HOT THERMAL EXPANSION VERIFICATION REV NO. 000 This instruction verifies adequate clearance for piping thermat expansion visual examination for thermal expansion is described in FSAR, Chapter 14, as follows: Section W-1.7 and 23 A & B. Only two data points will be taken instead of at each 100 degrees Fahrenheit heatup. This will not af fect safety. A. Visually examines and measures expansion clearance of piping identified Mirror insulation will be removed from four RHR hangers, but the subject per SMI-2-317-42 during plant heatup. pipe is isolated above 200 degrees Fahrerheit, and the heat loss to the containment is minimal. Strain gauges will be attached to four RHR pipe
- 5. Visuotty examines piping and hangers for potential restraints to hangers using capacitive discharge welding process. This process is thermat expansion. provided for in the NQAM and does not degrade the strength or serviceability of the component. Less than 70 pounds of burnable plastic
~
C. Measures the strain on four hangers in the RHR system, requiring h!ll be added to the transient fire toad by the strain gauge cables in removat of thermat insulation and attaching strain gauges on the hangers. conpliance with PNTSI-13. The protebility of an accident previously evaluated is not increased, and the possibility for an accident or The systems involved are RNR, SI, RCS, CC, CS, CVC, AFW, FW, and MS piping malfunction different from that previously evaluated will not be created. and pipe hangers. The margin of safety, as defined in the basis of any T.S., will not be reduced.
- STI-064 RESPONSE CF THE EGTS CONTROLLERS AND EXHAUST DAMPER TO A SIMULATED ACCIDENT CONDITION - UNITS 1 AND 2 EEV NO. 000 This test is divided into two parts. The first part consists of irputting Because this test will be performed in modes 5 or 6 when the EGTS system is a step change of the mittianp control signal to the 1/P danper positioner not required t's be operable, there will be no ef fect on the safety of the and measuring the start of opening and the conptetion of opening times for plant. The system will not be operated outside its limits. This ensures the EGTS exhaust danper. The second part of this test consists of that the probaultity or consequences of an accident or malfunction of
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Page No. 13 C6/33/88 SEQUOYAH NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION StFETY
SUMMARY
g inputting a sienalated accident signal into the damper controtter and equipment important to safety will not increase. This also ensures the-recording the controtter output along with measuring the start of opening possibitity br an accident of a type dif ferent f rom that previously and the completion of opening times for the exhaust damper. evaluated will not increase. C* STI-065 CONTAINMENT SPRAY PUMP PERFORMANCE - UNIT 2 REV NO. 000 This instruction was written to test and documer.t the CSP performance data. This test will not involve a change in the facility or plant operating characteristics. The test will be contiJcted without a change to T.S. 3.6.2.1. O* Sit-066 POST MODIFICATION TEST OF BACKDRAFT DAMPERS REV No. 000 This instructiort provides a functional test for the safety-related This instruction verifies cooling and ventitation to ESF equipment and backdraft dampers replaced by WP 9256 and WP 9341, ensures operability which reduces the probability or consequences of an accident. These backdraft dampers and associated air h W ling equipment have a reaundant (100 percent capacity) unit with controts to start on low flow by the other unit or high tesperature in the associated area (space cooters only). Therefore, the starting or stopping of equipment will not af fect its safety fmetion. The collection of data for calculating air - flow will not effect system operability. STI-072 D/G 1A-A RESTART TEST - UNIT 1 aEV NO. 000 This instruction was written to verify items of the functional analysis This test was implemented without a change to the T.S. The test did not report for system 82. involve new proce W res or instructions, or revisions to instructions or procedures, that are different from the procedures as described in the FSAR or plant T.S. No margin of safety has been reduced.
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Page No. 14 02/22/88 SEQUOYAH NUCLEAR PLANT to CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
g
$!1-074 D/G 2A-A RESTART TEST - tmIT 2 REV ho. 000 This instruction was written to verif y items of the functional analysis This test was implemented without a change to the T.S. The test did not report for systems 82 and 70. involve new procedures or instructions, or revisions to instructions or procedures, that are different from the procedures as described in the FSAR or plant T.S. The performance of this test will not re&ce the margin of safety.
STI-081 N2 ANALYZER VALVES 2A AND 28 FAIL-SAFE POSITION TEST - UNIT 2 REW NO. 000 This instruction was written to verify that the hydrogen analyzer This instruction wilt not involve proce&res which are dif ferent from the contairment isolation valves 2-FCV-43-201A, -202A, -207B, and -2088 f ait procedures as described in the FSAR. This test does not involve T.S. open on the toss of controt air and f ait closed on the loss of electrical requirements for mode 5 operation. power. O* SVI-033 CCNTROL BUILDING EMERGENCY PRESSURIZATION / VENTILATION TEST - UNITS . AND 2 REV NO. 000 This instruction was written to obtain data white temporarity altering the The data obtained will attow ONE to determine which flow path and alignment normal configuration of the control building ventitation system during a changes are necessary to resolve control room emergency ventitation
' controt room isolation signal. inleakage and pressurization problems. The probability of an accident will not be increased, and the possibility for an accident of a different type will not be created. The margin of safety, as defined in the basis of any T.S., will not be red;ced.
*o $13-105 ERCu CONTAINMENT ISOLATION CHECK VALVE TEST ret 7 No. C30 This instruction will instatt and test replacements for the ERCW The plant will be in mode 5 during testing. None of the equipment affected
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Page No. 15
.02/23/68 -
SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT CHANGES TO PROCEDURES AS DESCRIBED IN THE SAR DESCRIPTION SAFETY
SUMMARY
g contairunent isolation vatves 67-562A, -5628, -562C, and -562D. Atwood by this test is needed to perform a safety function, and it is not required Morritt soft-seat check valves will be instatted and tested per $1-158.1. operable in maie 5. The probability or consequences of a previously The current Anchor Darling swing check valves have repeatedly falted local anatyred accident or equipment malfunction will not be increased, and no leak rate testing. unanalyzed accident will be created. The margin of safety, as defined in the T.S., will not be reduced.
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_ . ~ - Page No. 1 .02/26/85 SEQUDYAN N9 CLEAR PLANT 10 CFR 50.59 1987 hRC ANNUAL OPERATING REPORT , SPECIAL TESTS PERFORMED IN 1987 DESCRIFTION SAFETY ANALYSIS
} ** Sil-10 CCS INLEAKAGE SPECIAL TEST CEV 000 This test was performed to locate and document any inteakage of radioactive This test did not increase 'ne rate of equipment failure. No aligrunent water into the CCS. ustd was abnormat to the f fstem des'3n. ' The probability of an occurrencw or the consequences of ar' accident or malfunction were not increased. The possibility for an accid sit of a oif ferent type than previously evaluated was not created. The margin of safety, as described in the basis of any T.S., was not reduced. ** STI-11 PLANT COMPUTE % ROCM VENTILATION TEST REV 000 This test was performed to resolve SPDS availability problems. This test cottected the data required to make modifications to the plant computer room ventitation system. This increased SPOS avaliability. The probability of an occurrence or tLe conr,equences of an ccident or malfunction were not increased. The possibility for an accident or malfunction of a different type than any previously evaluated was not created. The margin of safety, as defined in the basis of any T.S., was -
not reduced.
** STI-12 MAIN STEAM ISOLATION VALVE SPRINGS PROOF TEST REV 000 This test performed a compression test on the MStV springs to ensure The "Valve Stress Review
- rnd "Fracture Mechanics Analysis co Springs"
(.ontinued reliability of the MSIV springs for at least 960 additional ensure continued reliehility of the MSIV springs for at least 960 cycles. additional cycles. This test did not impair the function of the MSIV or create a possibility for an accident or selfmction of a different type than previously evaluated. The test was perforced daring cold shutdown mode and did not degrade any mergin of safety.
** STI 14 NONDESTRutitVE TESTIMG OF IN PLACE CONCRETE PER ASTM STANDARDS C803 AND'C805 - UNITS 0,1, and 2 sLV 000 This test was Atformed to determine the penetration resistance of hardened The test methods did not otgrade the integrity of the structures. The concrete and rebared ruber of hardened concrete at various locations protadure ensawed no embedded conduit, component, or piping was jeopardized throughout the plant, by 1.ils test. ASTM-approved nondestructive tests were performed by
> rectified techniciarr.. ' No areas were tested nAere the 90-day compressive 3
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r Page ho. 2 02/26/88 SEQUOTAM NUCLEAR PLANT 10 Cf R 50.59 1987 NRC ANNUAL OPERAf guG REPORT ' SPECIAL TESTS PERFORMED IN 1937 DESCRIPi!ON SAfEIT ANALTSIS strength is less than 2000 psi. The prot.wisitity of an occurrence or the consequences of an accident or metfunction were not increased. The possibility for an accident or metfunction of a different type than previously evaluated was not created. The T.S.' does not address testing of concrete structures. The margin of safety was unaffected by this test.
** Sil-17 DC NIGN VOLTAGE TEST FOR SELECTED UNIT 21E CABLES IN VERilCAL DROP CONFIGURATION REV 000 This special test was performed to demonstrate the adequacy of the conchait This test was performed on one safety train at a time. The re&ndant train and cable instattation at SON and to verify the performance capabilities of was ensured to be operable to support mode 5 operation. The plant design the conduit and cable system. configuration was restored and documented.. Plant operating parameters and system setpoints were not altered. Functional tests were performed at the conclusion of catie testing to ensure T.S. compliance. The probability of
.en occurrence or the consequences of an accident or metfunction of equipment were not increased. The possibility for an accident or matfunction of a different type than previously evaluated was not created.
The margin of safety, as defined in the basis of.any T.S.. was not reduced.
** STI 18 DC EMERGENCY LIGNTS INRUSN CURRENT - UNITS 1 and 2 ~ 4EV 000 This test was perforaed to measure and record the inrush current created by . This test only affected circuits related to de emergency lighting, and the the dc emergency tighting on the vital batteries during loss of offsite ac lighting system was not placed in abnormat aligrusents. Only one board was '
or att ac. tested at a time, and att testing w n performed with both units in modes 5 or 6. The probability of an occurrence or the consequences of an accident t oe metfunction of equipment were not increased.. The possibility for an accident or matfunction of a different type than previously evaluated was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
- cD S11 19 DC NIGN VOLTAGE TEST FOR SELECTED 1E CABLES WITH POTENil AL 70R CABLE JANMING - UNii$ 1 and 2 MEW 000 This spectat test performed a de high voltage test on selected IE cables to The test was performed on one safety train at a time. ,it ensured that the at teriate concerns regarding d.wnage due to cable jauning in cwdJit. redundant train was operable to swport er;de 5 operation. Att the involved systuns arx1 couements, were isolated and protected. The test did not
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Page CJo. 3 02/22/88 SEOUOYAM NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERA 11NG REPORT SPECIAL TESTS PERTORMED IN 1987 DE Sta lPilOes SAPLIY ANALYSIS I systems ard events were isolated ard protected. The test did not af f cct the Want configuration perneruntty. The plant design configuraticn was restored ard docunented. The plant operating parameters or system setpoints were not attered. The protxebitity of an occurrence or the corr.cquences of an accident or swifurction were not ircr eased. The possibility for an accident or malfunction of a different type than previously evaluated was set created. The surgin of safety, as defined in the tusis of any T.S., was not reduced.
- o Sil-20 COhiAINMENT ISOL ATION VAtVES WILL REMAIN CLOSED AFTER RESET OF THE CONTAINMENT ISOLATION SIGNAL - UNIT 2 REV 000 This test was per
- caed to verif y conteirunes t isolation valves listed in This test is described in Section 6.2.4 of the FSAR. The test did not accordance rith T.s. tab'e 3.6-2, pie valves 2FSV-30-134 and -135, sainus involve a change in the f acility or plant operating characteristics f rom th6 containment ventitation isolation valves, remained closed af ter reset that oescribed in tne FSAR. The test did not involve new procedures or of a contairunent isolation signal (phase A or 8), instructions that are different from the procedures described in the FSAR or plant T.S. The test was performed without a change to plant T.S.
Sil 21 DC NICH VOLTAGE TEST FOR SELECTED 1E CABLES llTH POTENilAL TOR CABLE PULL 8Y OAMAGE MC17348 - UNITS 1 and 2 REV 000 This test was performed oa selected 1E cables to alleviate concerns This test was performed on safety train 8 for specific conponents. Train A regarding postible damage due to cable put(bys in conduit MC17348. was operable to support att equipment that is necessary to function during mode 5 operations. STI 21 and applicable procedures ensured that the test cables and conductors disconnected, tested, and restored (as well as other cables and conductors disconnected and restored) did not offect equipment or components whose f ailure or actuation may increase the probability or consequences of an accident or malfunction of erpipment important to safety. Plant design and construction imured adequate isolation between the test cables arri ot her cables. The prm ibility for an accident of a different type than previously evalu.ated was not cr eated. The margin of t afety, as def ined in the basis of any I.S., was rwat reduced.
- 3 311 23 DC HIGM VOLTAGE IEST #0R SELECTED 1E CABLE WliH POTENil AL FOR CABLE FULL 8Y DAMAGE CONDUlf MC17288 - UNITS 1 and 2 8EV C30 This test was perfernaed on selected IE cables to alleviate coricerns This test was performed on safety train 8 f or specific corponents. Train A
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Page No. 4 , 02/26/88 SEQUDYAN NUCLEAR PLANT 10 CFR 50.59 1987 hRC ANNUAL OPERATING REPORT SPECIAL TESTS PERFORMED IN 1987 DESCRIPTION SAILIY ANALYSIS i ande 5 operation. The test was performed in accordance with STI-22 and - applicable procedsres which er.sured that the test cables and conductors , discomected, tested, and restored (as well as other cables and conductors disconnected and restored) did not af fect equipment or components whose failure or actuation may increase the probability or consequences of an accident or matfunction of equipment important to safety. The possibility for an accident or malfunction of a different type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
** STI-23 DC NIGN VOLTAGE TEST FOR SELECTED JE CABLES WITN POTENTIAL FOR CABLE PULLOY DAMAGE CONDUIT MC17284 - UNITS 1 and 2 REV 000 This tes: has performed on selected IE cables to atteviate concerns This test was performed on safety train A for specific components. Train 8 regarding possible damage due to cable put tbys in conduit MC1723A. was operable to steport att equipment tt.at is necessary to function during mode 5 operation. STI-23 and applicable procedores ensured that the test i cables and conductors discomected, tested, and .estored (as well as other cables and conductors disconnected and restored) did not offeet equipment or components whose falture or actuation ma, increase the probamity or consegJences of an accident or metfunction of equipment importan, to safety. Plant design and construction s w ed adequate isolation between the test cables and other cables. The possibility for an accident of a dif ferent type than previously evaluated was not created. The margin of safety, as defined in the basis of any T.S.g was not reduce <f.
9, ' CD -,T I-24 DC NIGN VOLTAGE TEST FOR SELECTED 1E CABLES WITN POTENil AL f 0R CABLE PULL 8f DAMAGE CON 001T MC1750A
- UNIIS 1 and 2 00 000 This test was performed on selected 1E cables to atteviate concerns This test was performed on safety train A for specific components. Train 8 "
regarding possible d.smage dse to cable put(bys in conduit MC17504. was operable to support att egalpment that is necessary to function during - mode 5 operation. 511-24 and oppticable svocedures ensured that the test , , cables and conductors disconnected, tested, and restored (as wett as other cables and conductors' disconnected and restored) did not af fect cgaipment k or components whose failure or actuation soy increase the probability or .
- consequences of an accident or malfunction of equipment isportant to safety. Plant design and constrt4; tion ensured adequate isolation between-the test cables and other cables. The possibility for an accident of a
.r
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Page No. 5 02:26/88 SEulAEAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT SPECIAL TESTS PERFORMED IN 1987 DESCRIPTION SAILIT ANALYSIS i different type than previously evaluated was not created. The margin of safety, as defined in the basis of any T.S., was not redxed. STI " DC NIGN VOLTAGE TEST FOR SELECTED 1E CABLES WITH POTENTI AL CA8tE PULL 8f DAMAGE CONDUli MC 17544 - UNITS 1 ard 2 REV OC1 This test was performed on seiected 1E cables to alleviate concerns This test was performed on safety train A for specific components. Train B regarding possible damage due to cable putibys in conduit MC1754A. was operable to support att equipment that is necessary to function daring mode 5 operation. STI-25 and applicable procedares ensured that the test cables and conductors disconnec'ed, tested, and restored (as well as other cables and conductors disconnected and restored) did not af fect equipment or conponents whose failure or actuation say increase the probability or consequences of an accident or matfunction of egalpacot isportant to safety. Plant design and construction ensured adequate isolation between the test cables and other cables. The possibility for an accident of a different type than previously evaluated was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
- O ST!-26 DC NIGN VOLTAGE TEST FOR SELECTED 1E CABLES WITN POTENTI AL FOR CABLE PULLBf DAMAGE MC17308 - LMITS 1 and 2 REV 000 This test was performed on selected 1E cables to alleviate concerre This test was performed on safety train B for specific conponents. Train A regarding possible damage due to cable pulltys in conduit MC17308. was operable to support ati equipment that is necessary to foriction during sode 5 operation. Sit-26 and applicable procedures ensured that the test cables and conductors disconnected, tested, and restored (as well as cther cables and conikctors disconnected and restored) did not af fect equipnent or cornpmtets whose failure or actuation say increase the probability or eonsequenees of an ac .Ident or matfunction of equipment isportant to safety. Ptant design and construction ensured adequate isolation between the test cables and other cables. The possibility for an accident of a different type than previously evaluated was not created. The margin of safety, as defined in the basis of any T.S ,, was not reduced.
- Sig-27 DC NICH VOLTAGE TEST FOR SELECTED 1E CABLES WITN POTENTI AL FOR CABLE PULLBY DAMAGE - CONDUIT MC1751 A - UNITS 1 and 2 SEV 000 This test was performed on selected 1E cables to atteviate concerns This test was performed on safety train A for specific components. Train B
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_ _ ~ _ . . - - - - - . ..- _.-~ .. - -_ - ~ _ . _ _ . _ . . - - . . -- . ~ - -- l rage No. '6 2 02/22/86 . l SEQUOYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT l SPECIAL TESTS PERf0RMED IN 1987 DESCRIPTION SAIETT ANALYSIS
) **- STI-27 DC NIGN VOLTAGE TEST FOR SELECTED 1E CA8tES WITH POTENTIAL FOR CABLE PULLST DAMAGE - CONDUIT MC1751A - UNITS 1 and 2 REV 000 This test was perforwed on selected IE cables to at teviate concerns This test was performed on safety train A for specific components. Train S regarding possible damage due to cable pullbys in conduit MC1751A. was operable to stpport all equipment that is necessary to function during mode 5 operation. The test was performed in accordance with STI-27 and applicable procedures which ensured that the test cables and conductors disconnected, tested, and restored (as well as other cables and conductors disconnected and restored) did not af fect equipment or cesponents whose f ailure or actuation'may increase the prot: ability or consequences of an accident or matftsiction of equipment important. to safety. Plant design and construction ensured ade @ ate isolation between the test cables and other cables. The possibility for an accident or malfunction of equipment of a different type was not created. The mergin of safety, as defined in the bests of any T.S., was not reduced. ** STI-31 DC NIGN VOLTAGE TEST FOR SELECTED 1E CABLES WITN POTENTIAL FOR CASLE PULL 5Y DAMAGE - CON 00lT 1732s - UNITS 1 and 2 ety 000 This test a.as performed on selected IE cables to alleviate concerns The test was performed on safety train 8 for specific components. Train A regarding pessible dwmege due to cable puttbys in conduit MC17328. was operable to stpport att equipment that is necessary to function during mode 5 operation. STI-31 and appticable procedure : ensured that the test cables and conductors disconnectrd, tested, and restored (as well as other cables and conductors disconnected and restored) did not af fect equipment '
or components iAose failure or actuation may increase the probability or consequences of an accident or malfunction of equipment important to safety.' Plant design and construction ensurni ade<pate isolation between the test cables and bther cables. The possibility for en accident of.a da f ferent type than previou".ly evaluatt<f war, not crcated. The margin C,f saf et y, as def ined in the tw.is of any T.S., um trot re**,ri. i ** $11-32 OC NIGN VOLTAGE TEST 70R SFLECILO 1E.Ci Stts MITH 8ti(NTI AL IOR CABLE FULL 8V DAMAGE - CON 00!T MC17318 ?- UNIIS 1 and 2 eEv 000 . This test was see rfors=4 on selected 1E cables to attevue conc >rns this test was performed on safety train 8 for specific components. Train A regarding possible damage due to cable putibys in conduit MC17318. was operable to support att equipment that is necessary to function during mode 5 operation. The test a.as performed in accordance with STI 32 and
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Page ko. 7 02/22/88 SEQUOYAM WUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERATING REPORT SPECI AL TESTS PERFORMED IN 1987 DESCRIPTION SAFETY ANALYSIS applicable procedures which ensured that the test cables and conductors disconnected, tested, and restored (as well as other cables and condactors disconnected and restored) did not af fect equipment or corrponents whose failure or as.tuation may increase the probability or consequences of an accident or malfunction of equipment irportant to safety. Plant design and construction ensured adequate isolation between the test cables and other cables. The possibility for an accident or malfunction of a different type was not created. The margin of safety, as defined in the basis c.f any T.S., was not reduced. " STI-33 DC MIGH VOLT AE TEST FOR SELECTED 1E CASLES WITN POTENilAL FOR CABLE PULLBY DAMAGE CONDUIT MC14938 - UNITS 1 and 2 REV 000 This test was performed on selected 1E cables to alleviate concerns This test was performed on safety train 8 for specific components. Train A regarding possible damage due to cable put tbys in conduit MC14938. was operable to support att equipnent that is necessary to ftsiction during mode 5 operation. STI-33 and arpticable procedares ensured that the test cables and conductors disconnected, tested, and restored (as wett u other cebtes and conductors disconnected and restored) did not af fect equipment or components whose f ailure or actuation may increase the probability or consequences of an accident or matf tsiction of egalpment important to safety. Plant design and construction ensured adequate isolation between the test cables and other cables. The possibility for an accident or matfunction of a d'fferent type was not created. The margin of safety, as defined in the basis of any T.S., was not reduced.
- o 571-34 DC HIGN VOLTAGE TEST FOR SELECTED 1E CABLES WITH PoiENTI AL #0R CABLE PuttBY DAMAGE CONDUIT MC1497B - UNITS 1 and 2 REV 000 This test was performed on selected 1E cables to alleviate concerns this test was performed on safety train B for specific corrponents. Train A regarding possible damage due to cable put tbys in conduit MC14978. was operable to support att equipment that is necessary to function during mode 5 operation. STI-34 and applicable procedures ensured that the test cables and conductors disconnected, tested, and restored (as well as other cables and conductors disconnected and restored) did not af f ect equipnent or corrponents whose f ailure or actuation cuy increase the probability or consequences of an accident or matfunction of equipment isportant to safety. Flant design and construction ensured adegaate isolation between
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Page No. 8 02/22/88 SEQUOYAN NUCLEAR PLANT to CFR 50.59 1987 NRC ANNUAL OPERATING REPORT SPECIAL TESTS P' M ORC D IN 1987 DEStalPflON SAILTY ANALYSl5 , the test cables and other cables. The possibility for an accident or malfunction of a dif ferent type than previously evaluated was not created. The margin of safety, as defined in the basis of any T.S., was not re & ced.
- Sit-37 CA8LE TRACING TEST ON POWER AND CONTROL CABLES FOR SELECTED 1E EQUIPMENT ERCW PUMP N UNITS 1 and 2 REV 000 This test perf ormed cable tracing of power and control cable routing to The performance of this test was within the safety evaluation provided in ERCW pump N-B to verify consistency with applicable plant drawings. FSAR, Section 9.2.2.3.2, and within the T.S. basis described in 3/4.7.4.
rsbte routing verification introduced a low-vottage, low-amperage trace a t put to the power and control cables of ERCW ptmp N-B. These cables were not exposed to voltages and currents in excess of their design. After cable tracing, ERCW ptmp N-B was proven completely operational.
- STS-38 CAsLE TRACING TEST ON POWER AND CONTROL CABLES FOR SELECTED 1E EQUIPMENT ERCW PUMP R-A - UNITS 1 and 2 REO 000 This test performed cable tracing of power and control cable routing to The performance of this test was within the safety evetuation provided in ERCW pump A-A to verify consistency with applicable plant drawings. FSAR, Section 9.2.2.3.2, and within the T.S. basis described in 3/4.7.4.
Cable routing verification intro &ced a low-voltage, tow-amperage trace signet to the power and controt cables of ERCW pump R-A. These cables were not exposed to voltages and currents in excess of their design. After cable tracing, ERCW pts:p R-A was proven coupletely operational. . o* ST1 40 CABLE TRACING TEST ON POWER A11D CONTROL CABLES FOR SELECTED 1E LOUIPMENT FCV-67-138 RED 0 0 This test performed cable tracing of power and controt cable routing to This test was within the safety evaluation provided in the FSAR, Section containment vent cooter valve 2-FCV-67-138 to verify consista ry with 6.2.4.1, and T.S. 3/4.6.3. Valve 2-FCV-67-138 was temporarity taken out of applicable plant drawings. service for this test during cold shutdown. Section 6.2.4.1 of the f$AR states that con'ainment isolation is not required during cold shutdowr i tow-voltage, low-acperage trace signal was introduced to the powar and control cables of vatve 2-f CV-67-138. These cables were not esposed to voltages and currents in excess of . their design. Af ter cable tracing was completed, valve 2-FCv-67-138 was proven completely operational. The cables were restored to their original configuration, and the valve was functional 4y tested and docunented.
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-4 i
f Page No. 9 l 02/22/83 SEQUDYAN NUCLEAR PLANT 10 CFR 50.59 1987 NRC ANNUAL OPERAflWG REDORT SPECIAL TESTS PERFORf4ED IN 1987 l DESCRIF.104 $AILIT ANALYSIS . 4
** ST3-42 DC NIGN VOLTAGE TEST TOR SELECTED UNIT 21E CABLES (SILICONE RUSSER CA8tES)
! REV 000 This 581 applied a dc high potential to selected silicone rubber cables The test was performed on safety train A for specific components. Train 8 inside unit 2 containment. These are control and power cables, type SROAJ, was operable to support all equipment that is necessary to function during. manuf actu ed ty the AlW Corporation, Rockbestos, and Anaconda. The test mode 5 operation. It was ensured that the test cabtes and conductors was performed to atteviate concerns of possible cable damage. disconnected, tested, and restored (as well as other cables and condJctors disconnected and restored) did not of fect equipment or components whose failure or actuation may increase the probability or consegaences of an accident or anlftsiction of egalprent important to safety. Plant design and construction ensured adequate isolation between the test cables and other cables. The possibility for an accident or malfunction of equipment of a different type than previously evaluated was not created. The plant operating parameters or system sstpoints were not affected or altered. The margin of safety, as defined in the basis of T.S. 3/4.6.3, was not reduced.
** 518-43 DC NIGN VOLTAGE TEST FOR SELECTED UNIT 215 CA8tES (SILICONE RUC8tR CABLES)
#EV 000 This $f t applied a de high potential to selected silicone takter cables The test was performed on safety train 5 for specific components. Train A inside unit 2 contelrunent. These are SROAJ type control cables was operable to"support att equipment th t is necessary to function during nienuf actured ty the AIW Cesporation. The test was performed to atteviate mode 5 operation. It was ensured that the test cables and conductors concerns of possible cable damage, disconnected, tested, and restored (as well as other cables and conductors disconnected and restored) did not ef f ect equipment or components whose
' f ailure or actuation may increase the prouebility or consequences of an accident or metfunction of equipment important to safety. . Plant design and construction ensured adequate isolation between the test cables and other l
cables. The possibility for an accident or malfunction of equipment of a different type than previously evaluated was not created. The plant operating parameters or system setpoints were not affected or altered. The surgin of safety, as defined in the basis of T.S. 3/4.6.3, was not reduced. i l l l
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Page No. 10 D2/22/88 SEQUDYAN NUCLEAR PLAbi 10 CFR 50.59 1987 NRC ANNUAL CPERATING REPORT SPECI AL TESTS FERFORMED IN 1987 DESCRIPTION $ATETY ANALYSIS , t O Si t -46 DC NIGN VOLTAGE TEST 70R SELECTED UNIT 2, 1E CASLES (SILICONE RUBBER CASLES)
- REV 000 This test was performed on selected 1E cables to atteviate concerns This test was performed on safety train A for specific Components. Train S regarding possible damage to the cabtes, was operable to support at t equipment that is necessary to function during mode 5 operation. STI-46 and applicable procedures ensured that the test cables and conductors discomected, tested, and restored (as wett as other cables and conductors disconnected and restored) did not af fect equipment '
or components whose failure or actuation may increase the probability or consegaences of an accident or motfunction of equfpment important to safety. Plant design and construction ansured adegante isolation between the test cables and other cables. The possibility for en accident of a different type than previously evaluated was not created. The mergin of safety, as defined in the bash of any T.S., was not redaced. co STI-67 DC NIGN VOLTAGE TEST 70't SELECTED UNIT 21E CABLES ($1LICONE RUBBER CABLES) - REO 000 This test was performed on selected 1E cables to atteviate concerns The test was performed on sv ety train 5 for s p cific components. Train A regarding possible damage to the cables. was operable to stpport all equipment that was necessary to function during - mode 5 operation. Sil-47 and applicable procedures ensured that the test cables and conductors disconnected, tested, and restored (ss weit as other cables and conductors t'Nconnected and restored) did not af fect equipment or components whose failvee or actuation may increase tha probability or consequences of an accident ar malfunction of equipment important to safety. Plant design and construction ensured adequate isolation betweca the test cablea and other cables. The possibility for an accident of a ' different type than previously evaluated was not created. The margin of saf ety, as defined in the basis of any T.S., was not redaced.
- o $18-52 DC NIGN VOLTAGE TEST FOR CLASS 1E 10 CFR 50.49 SILICONE RUSSER INSUL ATLD CABLES CEO 04 This Sil applied a oc high voltage potent sat to class 1E 10 Cf R 50.49 This test was performed on cables in both safety train A and 8 for *,pecific siticone rtboer insulated cables inside containment. These are SROAJ type ccaponents. One saf ety train was always operable to support att equipnent controI and poiser cables manuIactured by AIW, Roc 6 bestos, and Anaconda, that is netessary to f unction daring made 5 operation. S11-52 and The test was perf ormed to alicuate concerns regarding possible d.snuge. opplicable procedures ensured that the test cables and conductors
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1 Page No. 11 02/22/88
$EOLX) TAN NUCLEAR PLANT 10 CFR 50.59 1987 WRC ANNUAL OPERATING REP ST SPECIAL TESTS PERFORMED IN 1987 DESCRIPTION SAFETT ANALY$1S disconnected, tested, and restored (as weit as other cables and conductors disconnected and restored) d8-f not af fect equipment or components whose f ailure or actuation may increase the probability or consegJences of an accident or malfunction of egJipment important to safety. Plant design and construction ensured adequate isolation between the test cables and other cables. The possibility for an accident of a different type than previously evaluated was not created. The margin of safety, as defined in the basis of any T.S., was not reducent.
** STI-54 CABLE TRAClac TEST 04 SELECTED CONTROL CABLES REV 000 This test was performed to verify the routing of specific cables installed This test was performed within the safety evaluation provided in Section in the race:.ays. 9.5.1 of the FSAR and within the.T.S. basis described in 3/4.3.3.8. Att the requirements of PNYst-13, Appendix C, were met. Cable routing
. verification introduced a low-voltage, *ow-asperage trace signal to the controt cables of the fire detection zones 127,128, and 133 relay contacts. These cables were not sd>Jected to voltages and currents in escess of their design. When cable tracing was completed, t'e fire-detection zone relay contact cables i.ere restored end proven pa a. '
accordance with itectional tests. The probability of an occurrence or consequences of n accident were not increased. The possibility for an accident or out ftec.4on of egairoient of a dif ferent type than previously evaluated was not created. The mergin of safety, as definco in the basis' of any T. ., was not resbced.
** $11-61 ERCW/ AUX CONTROL AIR COMPRESSOR TEST
- REW 000 This test was performed on various ERCW equipment to verif y the heat load The relocation of the throttle valve prevented over-pressurization of the removing capability and record the maximum flow available. This also conpressor which has a lower design pressure rating than the ERCW system, established a new throttle valve and its position for both ACA air At no time durir=g the test was ERCW flow allowed to decrease below the conpressors based on a min / man flow. mirvaan at towable timit. Att ACA compressor testing was perforud af ter
. the conpressor had been placect in an inoperable status. Since only a maniaan flow rate was added to the existing minisua flow rate, there was no reduction in the er,rgin of safety for the ACA compressor. .The flow data
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Page No. 12 02/22/88 SEQUOTAN NUCIEAR PLANI 10 CTR 50.59 1987 NRC ANNUAL OPERATING REPORT SPECIAL TESTS PERFORMED IN 1987 DESCRIPTION SAFETY ANALTSIS t taken f or other equipnent was above the minisua flow repaired, and the system was returned to normat af ter conotetion of the test. STI-03 0/G 18-8 LOAD SEQUENCE TEST - UNIT 1 REV 000 This test was performed to collect data for DNF to evaluate dieset This test is described in the TSAR, Section 8.3, R.G. 1.19 and 1.108. The generator 18-5 worst-case toeding sequence. test did not involve a change in the pl*nt facility or plant operating characteristics from that described in the FSAR. The test did not ir.volve new procedures or instructions that are dif ferent from the procedures as described in the FSAR or plant T.S. The test was performed without a change to the plant T.S. STI-64 RESPONSE Of THE EGTS CONTROLLERS AND ExNAUST DAMPER TO A $1MULATED ACCIDENT CONDITION - UNITS 1 and 2 R G 000 This test is divided into two parts. The first part consists cf inputting this test had no effect on the safety of the plant because the test was a step change of the alltiano control signal to the ;/P danper positioner performed in modes 5 or 6 when the EGIS system was not required to be and measuring the start of opening and the completion of opening times for operable. A siriutated annutus pressure transient as shown in FSAR, figure the EGTS exhaust danper. The second part of this test consists of 6.2.3.7, was used to test the danper control system, and the system was not irputting a sinuatated accident signal into the danper controtter and operated outside its design limits. This ensured the probability or recording the controt ter output along with measuring the start of ornmng consensences ci a mattunction of egalgarnt ingsar t ant to safety were trit eruf the conpletion of opening times for the exhaust deper. increased. This also ensured the possibility for en accident or met function of equipment of a dif f erent tyge was rust created. The margin of saf et y, a . dcf f red on t he Imsis of any T .S., u.n erst s u1ms. o 513.t5 LonifAlhMINT SPeAV ICMP PIRf0RMAlnC[ - UNII 2 prEW 000 t h s s t est was ger f or aux 3 to t est arei oxteerit the psmp gerf orm.vu e data and This test is descriteed in tatile 14.1-1, sheet V5, of the (SAR. The test other related inf ormation. did not involve a change in the f acility or plant operating characteristics f rue that descrit>cd in the ISAR. The test did rwat involve rew proccdsres or instructions that are dif f erent f rom the procedures as dcscribed in the (SAR or plant T.S. T he t es t was per f or m ed w i t hout a ch nge t o 1.$. 3.6.2.1.
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. -. - .= -. - - . . ~ - - - - . . . , .~ _ -- ..
- .-- . . . - . . - - - ~ .- . .
Page No. 13 02/22/88 SEQUOYAN NUCLEAR PLANT 10 Cf a 50.59 1967 NRC AmuuAL OPERATIWG REPORT
$PECIAL TESTS PERFORMED IN 1987 DESCRIPTICM SAFETY ANALYSIS g
t O* 5ff-72 D/G 1A-A RESTART TEST - U411 1 REV 000 This test was perforsied to verify the foltowing: This test is described in Section 8.3 and Section 14,1 of the ISAR. The test did not involve a change in the facility or plant operating (1) The dieset wili trip on NJWI, low LOP, and high CP. chetacter est 6cs f rein that descritsed in the FSAR. Ihe test did not involve new procedires or instructions that are dif f erent fr*.)e the procedures (2) The diesel wili not trip on a MJWT, low LOP, and high CP trip with an describcd in the fSAR or plant i.5. The test was performed without a m ergency start signet present. change to T.S. 3.4.1.2, T.s. 3.7.3, i.5. 3.7.4, or T.S. 3.7.1.2. (3) Overspeed trip is not blocked when en emergwy start signal is present. (4) feanual control of the dieset is blocked when an emergency start signal is present. (5) The pw@ time of the air Compressors is verified. ' (6) The dieset will acceterate to rate ** speed rind flash the fletd from en idle condition followirw; en emergency start. (7.t The resetting of the ' otackout sequence timer by the SI reset timer is verified f or the fottowing pusips: AFW pulp 1A- A, ERCW pump J- A, and CCW pg 1 A A. O* Sil-73 D/G 18-8 RESTART TEST - UNIT * ' REW 000 This test was performed to verify the tottowing: This test is described in section 8.3 and section 14.1 of the f$AR. The test did not involve a change in the f acility or plant operating. (1) The dieset will trip on a NJWT, tone LOP, and high CP. characteristics from that described in the FSAR. The test did ret involve
. new procedares or instructions that are dif ferent f rom the procedures (2) The dieset will not trip on a MJWT, low (OP, and high CP trip with an descritied in the ISAR or plant 1.5. The test was performed without a emergency start signal present. change to 1.5. 3.8.1.2 and T.S. 3.7.1.2.
(3) OverW trip is not blocked when an energency start signal is
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. . . . - _ _ _ _ _ _ _ _ _ . _ _ . _ _ . .._. ,_ _ . _ . . _ . _ . - _ - _ _ _ _ _ .... . _ _ _ . _ . _ . . . - - .- _ n . ._
_ . _ _ . _.___._m _ . . . _ _ _m -- _ _ _ _ _m.m ..___.m- m. _ . . _ ..-.._mm _ _ _ _ _ . . . _m.m_ _ -. . m _
+
Page No. 14 02/22/88 SEQUOYAN NUCLEAt PtANT 10 CFR 50.59 1987 WRC ANNUAL OPERATING ROtlRT SPECIAL TEST $ PERFORMED IN 1987 e DESCRIPTION SAtLIY ANALV$15 , t present. (4) manual control of the diesel is blocked when e. emergency start signet is present.
- (5) The pump w time of the air compressors is verified.
l l l (6) The dieset ullt accelerate to rated speed and flash the field from an idle condition following an einergency start. (7) The resetting of the blackout segsence timer by the SI reset timer is verified for the AFW pump 1g-g. 1 1 ' ** STI-74 0/G 2A-A RESTART TEST - tmli 2 lAE'd000 This test esas performed to verify the following: This test is described in Section 8.3 and Section 14.1 of the f5AR. The test did not involve a change in the facility or. plant operating (1) The dieset wilt trip on a HJWT, low LOP, and high CP. characteristics from that described in the FSAR. The test did not involve new procedures or_ instructions that are different from the procedures (2) The dieset will not trip on a NJWT, low LOP, and high CP with an described in the F5AR or plant T.S. The testing was performed without a emergency start signal present. change to T.S. 3.8.1.2, T.S. 3.7.3, or T.s. 3.7.4.
~ '
(3) Overspeed trip is not blocked when an emergency start signal is. present. l (4) The pump-w time of the air compressors is verified. l 1 ($) The dieset wist accelerate to rated speed and flash the field from an idle condition following an emergency start.
' (6) The 51 reset timers for ERCW punps K- A and E-A and CCW pump 2A A reset the blackout sequence tiener on an $1 signal.
(7) Nrual control of the dieset is blocned when an escrgency start signat
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mi ,
Pese to. 15 02/22/88 SEQUOTAN NUCLEAe PLAuf to CfR 50.59 1967 NRC ANNUAL OPERAilNG REF3ti SPECIAL TEsis PERFORMED IN 1967 DESCRIPi!ON SAFEft ANALYSIS , is present. (8) The CCW gump 2A-A will not start on tow header pressure for 20 seconds fottowing a blackout.
' *
- STI-75 0/G 2s s RESTART TEST - UNIT 2 REV 000 This test was performed to wrify the fotlowing: This test is described in Section 8.3 and Section 14.1 of the FSAR. The test did not inwotwe a change in the facility or plant operating (1) The dieset will trip on a uJWT, low LOP and on high CP. characteristics from that described in the FSAR. The test did not involve new procedares or instructions that are different from the procedares (2) The dieset ulti not trip on a NJWT, low LOP, and high CP with an described in the FSAR or plant T.S. The test was performed without a emergency start signet present. change to T.S. 3.8.1.2, T.S. 3.7.3 and T.S. 3.7.4.
(3) Overspeed trip is not blocked when an emergency start signal is present. l (4) Manual controt of the dieset is blocked when an emergency start signal is present. (5) The gamp-w time of the air compressors is verified. I J (6) The dieset will accelerate to rated speed and flash the field from an l idle condition following an emergency. (7) The 51 reset timers for ERCW gamp P 8 and M-B and CCW pump 25-5 reset
- the blackout sequence timer on an SI signet. -
i (8) The CCW gamp 28 8 witI not start on low header f tow for 20 seconds l following a blackout. ' ** ST 3 - 76 CD41ROL SUILDING 84Ti[RY ENHAUST fA4 C-8 ISOLATION DAMPER If$1 - UE!IS 1 and 2 etV 000 This test was performed to verif y the control building battesy room emhaust This test is described in Chapter 14 of the 75AR. The test did not i*wolve
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Page No. 16 02/26/88 - SEQUOYAN NUCLEAR PLANT 10 CfR 50.59 1987 NRC ANNUAL OPERATING REPORT SPECI AL TESTS PERFORMED IN 1987 i DESCRIPTION SAIETT ANALYSIS i ( _ (SAR or plant T.S. The test was performed without a Change to T.S. 3/4.7.7
** ST1-77 D/G 2A-A LOAD SEOL:ENCE TEST REW 000 This test was performed to collect data for DME to evaluate dieset This test is described in the FSAR, Section 8.3, R.G. 1.9 and 1.128 The generator 2A-A worst-case toeding sequence. test did not involve a change in the plant facility or plant operating characteristics from that described in the FSAS. The test did not involve. ,
new procedures or instructions that are different from the prece &res as described in the FSAR or plant T.S. The test was performed without a change to the plant T.S. I 1
" STI-78 D/G 28-5 LOAO SEQUENCE TEST REO 000 this test was perf ormed to cottect data for omE to evaluate generator 2s-s this test is described in the FSARJ Section 8.3, R.G.1.19 and 1.108.' The. .!
worst-case toeding seguence. test did not Involve a change in the plant facility or plant w erating. characteristics f rom that deuritet in the ISAR. - The test did not involve
- new procedures or instructions that are different from the proce & res as. f described in the FSAR or plant T.S. The test wes performed without o' '
change to the plant T.S.
" STI 79 Pt ANT CONTROL SYSTEM INTERLOCK $ - R(B STOPS REO 000 This Sil functionally validated proper operation of each plant control Rod stops were provided to prevent abnormat power conditions ;Alch could ' ,
system interlock defined in the test instruction as it pertained to result from excessive control rod withdrawat initiated by either'a control blockage of automatic manual control rod withdrawal. system malfunction or operator action. The test is described in Section 7.7 of the FSAR. The test did not involve a change to the f acility or plant operating characterls'ics from that described in the FSAR. The test did not involve new procectres or instructions that are dif ferent f rom the proce & res as described in the fSAR or plant T.S. The test was performed without a change to T.S. 3.3.1. t w
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_ . ._ .~ - - - - - _ . _ - . . _ _ . __ _ - _ . _ _ _ m _ . = - _ - _ . . m - -. m ( rage No. IT 02/22/88 SEQUOYAN NUCLEAR PLANT 10 Cf R 50.59 1987 NRC ANNUAL OPERATING REPORT SPECIAL TESTS PERFORMED IN 1987 DESCRIPTION SAFETT ANALYSIS . 4
** STI-80 NONDESTRUCTIVE TESTING CT IN-PLACE CONCRETE PER ASTM STANDARD C803 sY NRC l REV 000 This test wa: performed on in-place concrete at various locations This test was performed by hRC personnel or NRC contractors. Att l throughout the ERCW pumping station and the crane well to determine the applicable radiological ard safety procedures were adered to during the I compressive strength of the concrete. perforehance of the test. the tase of captosive cartridges was in compliance with NCI-M21. The test was performed in accordance with ASTM Standard C803 1 , and NRC NDE-16. The probe depth did not enceed 1.6 inches, and there was
- no ef fect on embedM conkit or pipe. The T.S. does not address testins I of concrete structures; thus, the margin of safety, as defined in the basis
! of the T.S., was unaffected. ' ** STI-81 N2 ANALYZER VALVES 2A AND 2s FAIL-SAFE POSITION TEST - UNIT 2 l REV 000 This test verified that the hydrogen anatyrer contalrument isolation valves This test is described in table 14.1-1 1 of the FSAR. ' The test did not 2-fCV-43-201-A, -202-A, -207-s, and -208-s fait OPEN on the toss of control involve a change in the facility or plant operating characteristics from air and f all CLOSED on the loss of electricsl power. that described in the FSAR. The test did not involve new procedures or - instructions that are dif ferent from the proce&res as & scribed in the FSAR or plant T.S. This test did not involve a T.S. Item required for , mode 5. I ! ** $TI-82 MANUAL OPERATION AND $IROKE TIMING OF CCS VALVES AND AUTOMATIC OPERATFON OF THE UNIT 2 THERMAL SARRIER 800 STER PUMPS - tmITs 1 a:4 2 i REW 000 This test verified the eunual operation of four CCS valves, the strole time This test is descrited in the f sAR, Chapter 14, table 14.1-1, pages 92 and l of four CCS valves, and the automatic operation of the unit 2 theremet 93. The test did not involve a charne in the f acility or plant operating barrier booster pumps, characteristics from that described in the f5AR. 'The test did not involve new procedures or instructions that are dif ferent f rom the procedures as described in the f 5AR or plant T.S. The test was performed without a ( change to !.S. 3/4.7.3. l l
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O O O O O O O OCCUP A ION AL O EXPOSURE O D A A O I O O 4 O O O O
l NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION i SEQUOYAff NUCLEAR PLANT 1987 l GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL EMPIDYEES EMPLOYEES & OTIIERS PERSONS EMPIDYEES EMPLOYEES & OTHERS M-REMS
- MAINTENANCE PERSONNEL 2022. 20 13 2055 216.745 0.819 1.116 218.680 OPERATING PERSONNEL 118 11 6 135 11.286 0.251 2.861 14.398 '
l HEALTl! PIIYSICS PERSONNEL 235 47 0 282 40.730 3.662 0.000 44.392 SUPERVISORY PERSONNEL 37 1 3 41 1 2.536 0.220 0.565 3.321 ENGINEERING PERSONNEL 261 75 415 751 16.471 11.559 91.802 119.832 2673 154 437 3264 287.768 16.511 96.344 400.623 NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION SEQUOYAH NUCLEAR PLANT 1987 TOTAL NUM3ER OF INDIVIDUALS GROUP STATION UTILITY CONTRACT TOTAL EMPIDYEES EMPIDYEES AND OTHERS PERSONS MAINTENANCE PERSONNEL 706 9 5 720 OPERATING PERSONNEL 8 1 6 15 HEALTil PIIYSICS PERSONNEL 52 5 0 57 SUPERVISORY PERSONNEL 7 1 2 10 ENGINEERING PERSONNEL 65 13 194 272 TOTAL 838 29 207 1074
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, . . . . . ...m.____..._.._m_ _ _ _ _ _ _ _ . _ _ _ _ _ - ._m.-. _ _ _ _ . .. _ _ . ._- .__ _ . _ . . _ . - _ m l
SEQUOYAH NUCLEAR PLANT NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION 1987 M0= REACTOR OPS SURVEILLANCE NUMBER OF PERSONNEL (>100 M-REM) TOTAL MAN-REM GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL EMPLOYEES EMPLOYEES & OTHERS PERSONS EMPMYEES EMPMYEES & OTHERS M-REMS MAINTENANCE PERSONNEL 583 5 4 592 19.386 0.063 0.045 19.494 OPERATING PERSONNEL 55 9 0 64 8 5.644 0.243 0.000 5.887 HEALTli PHYSICS PERSONNEL 57 15 0 72 13.023 2.933 0.000 15.956 SUPERVISORY PERSONNEL 12 0 0 12 1.102 0.000 0.000 1.102 ENGINEERING-PERSONNEL 87 16 110 213 3.128 0.642 5.000 9.570 MO 794 45 114 953 42.283 3.881 5.845 52.009 l
~
M0= ROUTINE MAINTENANCE GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL-EMPMYEES EMPIDYEES & OTHERS PERSONS EMPIDYEES EMPIDYEES & OTHERS M-REMS MAINTENANCE PERSONNEL 637 7 3 647 69.521 0.321 0.230 70.072 OPERATING PERSONNEL 33 1 0 34 0.386 0.002 0.000 0.388 HEALTH PHYSICS PERSONNEL 61 15 0 76 4.294 0.555 0.000 4.849 SUPERVISORY PERSONNEL 11 0 1 12 0.189 0.000 0.000 0.189 l l ENGINEERING PERSONNEL 77 21 85 183 2.222 0.199 1.687 4.108 MO 819 44 89 952 76.612 1.077 1.917 79.606 i ( SOURCE DOCUMENT: RIMS S58 880129 876 i
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_ ..._ _ _ . _ . . - _ _ _ _ _ _ _ . _. _~.___ _ _ _ .. _ . - . _ , _._. _ .. _ _ - .-._., _ ._. _ ., _ -... . _ . _ -. _ ._ _ .-- ,.
M0=IN-SERVICE INSPECTION GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL EMPLOYEES EMPLOYEES & OTIIERS PERSONS EMPLOYEES EMPIDYEES & OTHERS M-REMS MAINTENANCE PERSONNEL 94 0 1 95 23.833 0.000 0.072 23.905 OPERATING PERSONNEL 2 0 0 2 0.072 0.000 0.000 0.072 IIEALTli PIIYSICS PERSONNEL 38 8 0 46 19.691 0.061 0.000 19.752 SUPERVISORY PERSONNEL 6 1 2 9 1.003 0.220 0.5GS 1.788 ENGINEERING PERSONNEL 19 11 57 87 1.614 8.661 48.604 58.879 MO 159 20 60 239 46.213 8.942 49.241 104.396 M0=SPECI AL MAINTENANCE GROUP STATION UTILITY CONTRACT TOTAL STATION UTILITY CONTRACT TOTAL EMPLOYEES EMPIDYEES & OTIIERS PERSONS EMPLOYEES EMPLOYEES & OTHERS M-REMS MAINTENANCE PERSONNEL 596 8 5 609 101.780 0.435 0.769 102.984 OPERATING PERSONNEL 23 1 0 24 0.136 0.006 0.000 0.142 HEALTil PilYSICS PERSONNEL 49 8 0 57 2.606 0.109 0.000 2.715 SUPERVISORY PERSONNEL 4 0 0 4 0.031 0.000 0.000 0.031 ENGINEERING PERSONNEL 75 27 162 264 9.507 2.057 35.711 47.275 MO 747 44 167 958 114.060 , 2.607 36.480 153.147 M0= WASTE PROCESSING GROUP STATION UTILITY CONTRACT & TOTAL STATION UTILITY CONTRACT & TOTAL EMPLOYEES EMPLOYEES OTIIERS PERSONS EMPLOYEES EMPLOYEES OTIIERS M-REMS MAINTENANCE PERSONNEL 112 0 , 0 112 , 2.225 0.000 0.000 2.225 OPERATING PERSONNEL 5 0 6 11 5 048 0.000 2.861 7.909 IIEALTli PIIYSICS PERSONNEL 30 1 0 31 1.116 0.004 0.000 1.120 SUPERVISORY PERSONNEL 4 0 0 4 0.211 0.000 0.000 0.211 ENGINEERING PERSONNEL 3 0 1 4 0.000 0.000 0.000 0.000 MO 154 1j 7 162 8.600 0.004 2.861 11.465
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y
. TENNESSEE VALLEY: AUTH ORITY - ,
5N 157B Lookout' Place-MAR 011988 10 CrR 30'3, 4 v
;U.S. Nuclear Regulatory Commission ,
" ATTN: -: Document Control Desk "
Washington, D.C. 20555 , Gentlement ' ' In the Matter of ) Docket Nos. 50-327,' Te:inessee Valley Authority ) 50-328' 1 SEQUOYAH NUCLEAR PLANT (SQN) - 1987 ANNUAL OPERATING REPORT
- Enclosed is the 1987 Annual Operating Report for SQN. It contains a
summary of the following items: emergency core cooling system. outages, a primary system safety or relief valve actuations, facility changes, .! procedure changes, and occupational exposure data. This report is being ' submitted to satisfy the requirements of 10 CFR Part 50.59 and technical i specifications 6.9.1.4. 6.9.1.5, and 6.15.1. . l If you have any questions, please telephone M. J. Burzynski at i (615) 870-6172. ! t Very truly yours, i TENNESSEE ALLEY AUTHORITY j f)h A W, L 32 R. Gridley, Di ctor Nuclear Licensing and Regulatory Affairs Enclosure ces see page 2 l I
- l l
I l 1 56hh ; An Equal Oppor* unity Employer ilh I
) U.S. Nuclear Regulatory Connission MAR 011988 cc (Enclosure): Mr. K. P. Barr, Acting Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. G. G. Zech, Assistant Director for Projects IVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 1 l}}