U-601279, 10CFR50.59 Rept for Plant Mods,Temporary Mods,Procedures & Documents,Jan-Mar 1988
| ML20155H461 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 03/31/1988 |
| From: | ILLINOIS POWER CO. |
| To: | |
| Shared Package | |
| ML20155H459 | List: |
| References | |
| U-601279, NUDOCS 8810200219 | |
| Download: ML20155H461 (57) | |
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,,I , ATTACIDENT 2 t U-601279 !
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i CLINTON POWER STATION i f
10CFR50.59 REPORT {
l FOR l PIANT MODIFICATIONS f
TEMPORART MODIFICATIONS l
, f PROCEDURES AND DOCUMENTS
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CLINTON POWER STATION IOCFR50.5, REPORT FOR MODIFICATIONS FROM JANUARY THROUGH MARCE I,..
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t I s e e MOD 7FICATIONS 09/27/88 PAGE NO. 1
( j) 10CFR50.59 REPORT FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT 11TLt NUMBER EVALUAff0 es ooro FA Aro23 INSTALL FENCE IN RADWASTE BUILDING AND SCREENHOUSE This plant modification installs a fence in the radwaste building machino shop. This fence will function as a Radiological Control Area boundary. This modification also provides a fenced tool area in tho scroonhouse andCollapse in the radwaste building for the safo kooping of tools.
of those foncos will not affect any equipment important to safety because the fences are located in non-safoty, non-soismic areas.
AS A RESULT OF THE EVALUATION. IT WAS DETERMINED THA UNREVIEWED SAFETY QUESTION DID HOT EXIST.
e.s otoo sx Am.33 sure t ELIMINATE ALARM RELAY FEEDDACK SIGNAL IN RADI This modification supplement disconnects the alarm relay feedback signal from the microprocessor in cach of the area radiation / process radiation (AR/PR) monitors which occurs This modification also corrects r~w during the source check.the AR system firmwarethe Eliminating to prevent alarm the display o
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data during channel source checks. circuitry feedback signal during sequence is acceptable because proper functionina of AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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( ! 10CFR50.59 RdPORT FROM JANUARY THROUGH MARCH 1988 LOG DoCUMENf TITLE M.MSER EVALUAff0 a3 0009 rw At.34 MODIFY RADIATION CENTRAL CONTROL TERMINALS This plant modification changes the firmware on the area radiation / process radiation (AR/PR)will These changes system contral correct control errors that terminals (CCTs).cause the CCTs toThis alarm for FAIL and ALERT lighted alarms.
fail plant and will add a continu modification also changes the FAIL and ALERT tiles from stationary lights to lighted pushbutton alarm acknowledge switches.
This modification enhances the reliability of main control room annunciators and increases the operator's awareness of significant plant conditions.
P.S A RESULT OF TiiE EVALUATION, IT WAS DETERMINED TIIAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
es oota FA Astoo4 ADANDON ELECTRODE BOILER RECIRCULATION FLOW Differential pressure switches OPDS-AS023 and 24 by sensing differential pressure across recirculation pumps
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'~ ') OASOSPA and D. This field alteration abandons the differential pressure switches in place to oliminate unnecessary electrode boiler trips caused by the sw This will not damage the boilor, but recirculation will flow. steam output. Overall result in lowered auxiliary steam system reliability will bo improved.
IT WAS DETERMINED TilAT AN AS A RESULT OF Ti!E EVALUATION,UNREVIEWED SAFETY QUESTION D O_
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) 10CFR50.59 REPORT FROM JANUARY THROUGH HARCH 1988 too occuxtur TITtt NUMSit EVALUAfto as oos3 FA coroo', DELETE DIFFERENTIAL PRESSURE ALARMS ACROSS This field alteration climinatos the high 040, 041, differential and 042, across the pressure alarms 1PDS-CD039, Upon completion of power condensato pump suction strainors. ascension testing, the fine mo in-lino strainers were removed from all condensato pumps.
However, the high differential pressuro Clogging alarms of coarse which mesh remain scroons erroneously annunciate.
which are still in place will be identified through daily monitoring of local pressuro gaugos.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION DID 87 2654 FA Croo9 REVISE DATA SHEETS FOR TIME DELAY RELAYS This field alteration corrects discrepancies betwoon nameplato data and savon data shoots and adds a coil rating 7-x for Agastat tino delay relays located in the main contro room.
( ) part dreuing numbers, and instrument service andThe corrections to the m qualification descriptions.
numbers and purchase part drawing numbers also nood to beThes made on FSAR Tablo 3.10-2.of the diosol generator room ventila treatnent, supprossion pool makeup, cleanup, turbine generator, turbino generatorelectro-hydra and the fuel building ventilation systems.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION
09/27/88 4
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10CFR50.59 REPORT FROM JANUARY THRO 70H KARCH 1988 t i
LOG 00CUMCHT IlfLE Numsta tvAtuAfto C-0078 FA cw oo$
REVISE DRAWING TO SHOW EXPANSION JOINTS for the shows The piping and instrumentation diagram (P&ID) system (FSAR F:
circulating water (CW) ts !
components 1CWO2MA.and B as restriction devices. !
alteration revises the P&ID to correctly show the componen as expansion joints. Expansion joints 1CWO2MA and B were installed as part of the original design to reduce the effects of thermal stress from the main condenser on the watorbox drain lines which are fixed in the basement flo of the turbine building. i t
7 i AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAl l 4
UNREVIEWED SAFETY QUESTION DID NOT EXIST.
LDING 88 0023 en fr so PROVIDE A STORAGE / MAINTENANCE AREA This plant modification installs aThis welded wire mes f<snce will at' elevation 781' of the radwaste building. .
change the cable tunnel into a storage and maintenance area l
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to relieve crowded conditions in the control andUse of this farea for stor4 instrumentation (C&I) shop. i '
,~ and maintenance will not affect the structural integr ty o l
- the radwaste building or the existing ventilation system.
The added fire extinguishers provide the requircd fire protection. Also, there is no safety related cablo or permanent plant equipment in the area. I AS A RESULT OF THE EVALUATION, IT WAS DETERMINED TRA UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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nI 10CFR50.59 REPORT FROM JANUARY THROUGH MARCH 1988 P LOC 00CLMENT fifLE htsWER EVALUAf(0 .
88 0035 #A csroo3 REVISE POSITION OF GLAND SEAL SYSTEM VALVES from The gland steam system seal steam packingexhauster/ c ;
the main turbine shaft packings.
revises the piping and instrumentation diagram (FSAR Figure !
10.4-2) to show the steam packing exhauster (SPE) drain This ;
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, controls and loop seal fill valves as normally open.
- will allow operations personnel to field adjust the valves so that the SPE drain / loop sealThe cangland be maintained at theT proper level. seal '
experiencing excessive air in-leakage. system is not safety impact systems that perform a safety function. '
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT !A URREVIEWED SAFETY QUESTION DID NOT EXIST. ,
88 @M5 TA wrwr REMOVE HEATER DRAIN CHECK VALVE 1HD0025
() This field alteration removes heaterThis drain tank and replaces it with a pipe section.
drain checkcheck val valve was provided to prevent a Analysis backflow of flash turbine trip during turbine load reductions.showed Also, that r tank drainage if the check valve were removed.
unanticipated load reductions of sufficient magnitude to affect tank drainage would only be caused by equ IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTIO O
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( ,) 10CFR50.59 REPORT FROM JANUARY THROUGH HARCH 1988 log 00CLMEnf TlftE '
mmett EVALMito c)co33 #A paroo3 CHANGE MATERIAL OF HP SYSTZM PUMP TOP SHAFT This field alteration allows a part substitution for the The -
high pressure core spray (HP) system pump top shaft.
original top shaft material met the specification of l American Society for Testing and Materiale (ASTM) S '
A-276. This material substitution is acceptable ;
of ASTM A-479.
because materials, the physical properties of the replacementi.e., tens -
elongation, are equivalent or better than the original material.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
88 0037 PM Lo 22 INETALL JUMPERS TO BYPASS LEAK DETECTIO EE002, RF008 and Leak detection system handswitches RE001, RF009 in panel 1H13-P601 in the MainThe Control Room are not present O wired in accordance with the design.
area sump fill timers inoperable.
This plantconfiguration modification renders tl t
,- installs jumpers which will bypass and eliminate the need l for the handswitches and provide pov:r to the sump fil!
timers. This modification will allow d !
the remaining reset switch.the leak detection system to operato as IT WAS DETERMINED THAT AN !
AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTIO L t
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k_ 10CFR50.59 REPORT FROM JANUAkY THROUGH MARCH 19s8 LOG DOCUMENT fifLE WUMcit (VALUATCO es ooos eM M 36 INSTALL FLUSHING LINE TO FLOOR AND EQUIPMEN This plant modificationsystem installstoathe fiv~.ung lino from acid /cauntic the drain makcup condensato (MC) lines of the equipment drain (WE) system f the drain (TF) system.
This lino will allow flushing linos to provent plugging following acid / caustic atadditions.
acid-water This modification also adds lined check valvrinterfaces This t WE/TF drain lines from the WE acid / caustic system.
modification doos not affect safety related, seismic, orThe affected augmented D components.
TP systems are not used for the handling of radioactive fluids.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION D ss 0074 rA nro14 ALLOW USE OF TEMPORARY STRAINERS IN RADWAST This field alteration adds a note to piping and to
('3,) instrumentation diagrams (FSAR Figures 11.2-2 and 11.4-3) allow the use of temporary strainers in radwanto s i This will allow temporary strainers to be added, as -
necessary, to prevent resins from ontoring unwanted areas.
Failure analysis of the strainers is not required to moet ANSI B31.1, the design for this class D piping system.
Also, the strainers will not impact pump operation b .
positivo suction head difference they cause. !
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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09/27/88 8 HODIFICATIONS PAGE NO.
/,^N 10CFR50.59 REPORT FROM JANUARY THROUGH MARCl! 3 988
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l LM ox& tut TITLE NUM8tt (VALUAtto 8a 0003 en Pa 34 REMOVE DOWHSCALE & POWER FAIL TRIP FROM PR MO downscale and power fail This plant modification removes ths trip functions from 16 process radit tion (PR) monitors and adds handswitches to allow a manualin trip signal to beThe 16 the oxhaust
' initiated. in the containment fuel transfer pool vont plonum, ducts of the co fuel building ventilation system,ip Tht tr outputs of those containment purgo system.
monitors isolate the containment building vontilation system and the fuel building ventilation system, and Downscale start the and power fail standby gas treatment system.
annunciation for those monitors is provided in the mainTh control a failedroom.
channel within the tino limit specified by the .
Technical Specifications.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED TilAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
lf I L e.s oo22 fA Paroo4 REMOVE FILTERS IN LIQUID PROCESS RADIATION M F' This sevenfield alteration of f-lino removes liquid process filtors radiation from (PR) the inlots to monitors.
I l These monitors moneure the radioactivity in the plant in the liq in the fuel pool host exchanger service water,and in the component cooling servico water of fluent,The filter is not part of the vendor's standard offluent.
design and provides an unnecessary flow restriction. I Removal of the filtors will improve the oporating This characteristics and accuracy of the PR monitors. modif ,
or other systems, AS A RESULT OF Tile EVALUATION, IT WAS DERPJtINED THAT AN UNREVIEWED SAFETY QUESTION DI(J NOT EXIST.
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09/27/88 MODIFICATIONS PAGE NO. 9 10CFR50.59 REPORT FROM JANUARY THROUGH MARCH 1988 toc oot w wf ititt sweta tvattutto se. cot 3 m Ps.13 ADD SAM 1PLE LINE ISOLATION RthCK VALVE 8 block This plant modification installs sample line isolation valves to each coniensate domineral.izer sampling station.
This will allow the isolation of sampling stations forThe sample li maintenance purposes. modification are not safety related or seismically qualified. N AS A RESULT OF THE EVAINATION, IT WAS DETERMINED THAT UNREVIEWED SAFETY QUESTION DID NOT EXIST.
4 N 673 FA autoot DELETE AUTohATIC kUNBACK OF RR FLOW CONT This field alteration deletes the Automatic automatic runback of flow control valves.
reactor runbackrecirculation (RR) was initiated by a circulating water of these valves pump trip when all three This pumpsgeneration is a power were operating feature.t with Lossa low 13 condenser vacv.1m.
of condenser vacuum transients described in FSAR Chap er O do not take credit for this runback feature.
IT WAS DETERMINED THAT AN
-+ AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTIO O
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MODIFICATIONS 09/27/88 PAGE NO. 10
\ 10CFR50.59 REPORT FROM JANUARY THROUGH MARCH 1988 tm >x&ot Tlftt IA.M8(t (VALUAftD u ootr FA rnoo3 REVISE SAFETY CLASSIFICATION OF VALVES ISX095A safety classification of This sparafield alteration valvon ISX095A revisos the activo to passivo and from and D from 1E power to non-1E power. Those valvos are the shutdown system outlet valvos to the hydrogen service water (SX)ing compressor cubiclo coolers IVR09S and control IVR12S. system mixA previousAsmodification a result, removed the hydrogenthe cubicle compressor cubiclo doors.
are no longer needed and valvos 1SXO95A and B are notThese va required to operate.
degrado a 1E bus becauso double breaker protect provided.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION D M ooc 2 m vc 42 DELETE AUTO ACTUATION OF VC SYSTEM CHLORINE M This plant modification dolotos the automatic actuation of
( ') the chi)rino modo of the control room ventilation (VC)The system.
automatic motors awayactuation wheninchlorino from air intakes is stored aatcapacity containors least 100 Presently, chlorinohaving containers at of 150 pounds or loss.
Clinton Power Station are 150 pounds and are stored more than 100 motors away from the air intakes of the controlThe onlo room ventilation system.
provido a main control room alarm for high chlorinoc actuated. l IT WAS DETERMINED TNAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION D i
NODIFICATIONS 09/27/88 PAGE NO. 11
) 10CFR50.59 REPORT FROM JANUARY THROUGH MARCH 1988 Los ooomtut illLE ,
lue(R tv&LUAfto 87240 Pm vt 05 INSTALL DOP INJECTION MANIFOLD This modification installs a permanent dioctyi phthalato (DOP) injection manifold for the testing of laboratoryThis modification has exhaust filter units OVL11SA and B. The no impact on the operability of the filter units.
manifold is located in negative pressure ductwork which hasAny no leak testing criteria.
installation of this modification will not prevent the laboratory exhaust filter units from performing their design function.
AS A RISULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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CLINTON POWER STRTION 10CFR50.59 REPORT FOR TEMPORARY MODIFICATIONS. >
FROM JAkcARY THROUGM MARCE 19..
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10CFR50.59 REPORT FROM JANUARY THROUGH MARCH 1988 LOG 00CtMtNi titte in.msta tvAwArto u oo39 ft e w e u ott INSTALL STRAINERS IN SUCTION LINES OF RADWASTE PUMPS This temporary modification installs strainers in the auction linos of vasto camplo pump A and excess water pump A of the radwanto equipment drain (WE) system. The pumps are used to transfer water to the service water system and the cycled condensato system, or off-standard water back to the WE surge / collector tanks. The installation of a strainer on the auction of each pump will provent resin migration into other systems. Those pumps and their suction linesThe do not impact or interface with a safety-related system.
modification will not create the potential for Ln unexpected or uncontrolled release of radioactivity to the environment.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
u oo61 tr e Mao u ott REMOVE SMOKE DETECTORS FROM VC SYSTEM INTAKE AREA h) This temporary modification removes two ionization smoko detectors from the control room ventilation (VC) syntom
-.'~ intake area in the control building. Water from the outdoors wots those two detectors causing all 30 detectors in the zono to becomo inoperable. These two detectors are not required because they are installed in an area that contains no Also, combustible material and those detectors no provido do not ventilation any l' equipment. Their removal improves operability of automatic actuation.
the remaining detectors in this zone.
AS A Ri.SULT OF THE EVALUATION, IT WAS D5;TERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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,,e-TEMPORARY MODIVICATIONS 09/27/88 PAGE NO. 2 10CFR50.59 REPORT FROM JANUARY THROUGH MARCH 1988 toc coowat Itut spots tvuuarto es cors itw nao so otr CRO85 TIE WM SYSTEM LINE FEEDERS TO 60FTENERS This temporary modification connects the makeup
- domineralizar (WM) system line feeder This A to line softener allows line B and line feeder 8 to line softener A.
softener B Cross to remain tyinginthe service WM line while line tender feeders B is and softeners will increase system availability. This will ensure a repaired.
I continued supply of high quality water for continued plant This modification does not impact the safety l operation. design basis of theAlso, plant because failure ofthe theWM WM system systemperforms no l safety related function.
l will not impact operation of any safety related system.
This equipment is located in the makeup water pump house l
which is southwest of the plant service building.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUA^ TION,UNREVIEWED SAFETY QUESTION DID NOT E f sa oor, icw nao 88 019 INSTALL BLOWERS IN T33 TURBINE BUILDING MAIN STEAM TUNN Higher than normal tesperatures have been occurring in thetur y in the area being clogged, to minor steam leaks, and to some This tesperature sensors being located in a stagnant area.
temporary modification installs temporary portable blowers The in the steam tunnel to eliminate air stratification.
blowers are powered from a non-1E source and their failure will not impact the safety function of any safety related equipment.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST. I O
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i / h i \~ J 10CFR50.59 REPORT FROM JANUARY THROUGH MARCH 1988 LOC 00CLMENT itttt EMatt tvAtuAfto (CRD) as oost ice e asco ALTERNATE COOLING WATER SUPPLY FOR CONTROL ROD DRI the CRD pumps will bo out of During planned outage PO-2,This temporary modification providos an alternato servico.
cooling water supply to the CRDs by installing four hosensystem hose statio from the cycled condensato (CY) The l CRD supply lino high point vont/ low point drains.
portions of the CY and CRD systems which are af fected by l this modification are not safety related and the safotyFailure of all l function of the CRD system is not affected. /
four hoses will result in a loss of CRDs.
cooling Also, multiplewater check to thoHowever, c'sthough seal life will be shortened.
l valves will provent reactor coolant inventory from leaking past the seals if seal cooling water is lost and the seals degrado. The system will be restored to its original configuration at the end of PO-2.
1 AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN i
UNREVIEWED SAFETY QUESTION DID NOT EXIST.
O ss 0091 ft e moo as c21 INSTALL SPARE MOTOR OPERATOR ON RH SYSTEM VALVES the motor operators on residual During planned outage PO-2, system valvos lE12-F024A and B will be hoat removal removed and(RH) identical operators installed without electrical terminations.
This will allow the valvos to be manually operated. Those valves isolate the RH test return linos to the suppression pool. This modification will allow the RH i
system to remain operable as required by the TechnicalThis modific Specifications.
the plant in Mode 4, and thus the automatic containment isolation function of those valves is not required.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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i CLINTON POWER STRTIch 10CFR50.59 REPORT 1 FOR l 6
PROCEDURES, TESTS RND AND EEFERIMENTS, AND OTNER DOCUNRNTS I FROM FSRR RMENDMENT 38 TO >
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i RECEIPT OF TNE OPERRTING LICENSE AND FROM JRNURRY THROUGM MRRCN i 1988 f
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1 PROCEDURE 0 AND DOCUMENTS l
PAGE NO. E
( ) AND FROM JANUARY THROUGH KARCH 1 ;
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a4 024 tato.or a.o EMERGENCY BREATHING AIR FILTER LEAK TEST This new test procedure controls the testing of air t inleakage of the emergency breathing air filter unit,This pr ORA 02S.
at the inlet and outlet of the filter enclosure and subjects the filter unit to vacuum conditions which are well within its design capability. The breathing air system is not
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j safety related and the filter unit is not used during normal i plant operation * >
, AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
l 88 039 2ast.ct s.0 RUSKIN FIRE DAMPER DROP TEST l
This test procedure performs a drop test on Ruskin fire auxiliary i i
dampers in the following ventilation systems building, control room, screenhouse and makeup water pump r house, machine shop, drywell purge, turbine building, This test i radwaste building, and switchgear heat removal. !
requires that an electrothermolink be installed in place of l
"' a permanent fusible link, and that a transparent plastic viewing window beThe installed testingin will placebeofperformed a permanentso as to t
inspection door. ,
maintain' system operability as required by the TechnicalInj !
Specifications.the plastic viewing windowswill the systems willbe not impair fire protectio restored r After completion of the test,
- ' to their original configuration. ,
IT WAS DETERMINED THAT AN +
AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION[
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t 09/27/88 2 PROCEDURES AND DOCUMENTS PAGE NO. OF THE OPERATING LICENSE 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT AND FROM JANUARY THROUGH MARCH 1988 tec coctetur fliLE utteett (VALUAi!D R DEARINGS u@M ca t u 01 035 FLUSH LINE FOR SERVICE WATER for PUMP 1WS0 This condition report identifies two discrepancio.',i one for the service water (WS) pumps 1WS01PA The original
" and and C fl a radially drilled hole in the TheWS pump as-built The shaf ts. design finally connected to a 1/2" line. be configuration does not include the 3/4" reducer. l original design also required that a 1/4" radial ho flow path for the pump bearings. This condition report il drilled and countersunk to 1/4'. justifies the acceptability hole in tboir present configuration.does not adversely alter the l the flush lino from 3/4" to 16 The 1/8" radial impair hole the flow to the pump upper bearings.
allows adequate flushing water flow and does not fatigue strength of the pump shaft.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTIO
, VENT VALVE u oo67 ca 1 u 02 033 REVISE DRAWING TO REFLECT AS-DUILT CO (FSAR Figuro 9.2-2) it The piping and instrumentation diagramspresently This sh vont line 1SX127AA upstream of valvo ISXO90A.
condition report corrects the diagram to show the vont as being downstream of 1SXO90A, which is the as-builtThe v configuration.
highpoint which in the design requirement. AN AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THA UNREVIEWE0 SAFETY QUESTION DID NOT EXIST.
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09/27/88 3 FROCEDURED AND DOCUMENTS
~.s PAGE NO. NG LICENSE
- 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT O AND FROM JANUARY THROUGH KARCH 1988 toc occLetut lifLE muMsta tvALUAff0 C> M30 tua Puu at GENERAL REVISION OF THE CPS EMERGENCY PLAN The Clinton Power Station (CPS) Emergency Plan Thiswas developed program to support the Eaorgency Preparodness Program.has b omorgency situation at CPS.
changns to the Plan such as, revising position titles and responsibilitics, clarifying definitions, relocating and redefining certain facilitic; and equipment, andThese enanges comply with incorporating clerical changes.
the requirements of 10CFR50.47 and 10CFR50 Appendix E. '
AS A RESULT OF THE EVALUATION, IT WAS DETEPNINED TilAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
tJ oost EP P AP 06 a2 REVIEW OF EMERGENCY PREPAREDNESS PROGRAM ensures This Emergency Plan Implomonting Procedure (EPIP) that the Emergency Plan and its associated implomonting :
/ procedures are reviewed and that revisions are made This to
\s correct inadequacios identified during the review. revi I
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clarifies what information is required in the Emergencyadds the Nuclear Preparedness Program Annual Review Roport, and updatos Review and Audit Group (HRAG) as its recipient, personnel titles inTheaccordance parsonnelwith roment management title changes requiro reorganization. revision to the Emergency The rest of Plan, which isare the changes part of the Fi Safety Analysis Report (FSAR) .
consihtout with the Enorgency plan.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION O
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l 09/27/88 4 PROCEDURE 0 AND DOCUMENTS PAGE NO. ING LICENSE l(
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' 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT l
- AND FROM JANUARY THROUGH MARCH 1988 Loc coaxar Tlftt CJpart tvAtuAfte i C oo79 trir Ap.or as ALERT AND NOTIFICATION SYSTEM (EPIP) providos This Emergoney Plan Implomonting Proceduro guidanco for documenting the performanco of the alert and notification system (ANS) with respect to testing and l maintenanco. This revision correcta rotorences to corrects "Siren Maintenance / Repairs Reporta, Attachment 4, the location of siren (15 due toguidelines Also, relocatiori,for and cla i
to the Director - Emergency Response. 'ified to conform datormining siren operability have boon n .$ monthly I with system design, documents comprising performanco report have boon clarified, ano personnel titics have boon corrected in accordance with recent managomo reorganization.
I design of the ANS because its now location moots The position the ,
requirements for notification of the public. i l title char.ges require revision to the Emergency Plan, wh ch l is part of the FSAR.
with the Emergency Plan.
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() AS A RESULT OF E*.TiiE IT WAS DETERMINED THAT AN ALUATION,UNREVIEUED SAFETY QUESfION DID NOT E te co77 tale A7 09 t2 ElfERGENCY COMMUNICATIONS OPERABILITY onsures CHEC d
This Emergency Plan Implomonting Proceduro This (EPIP periodically for proper operation and availability.
revision adds communications tests for the emorgency response facilities, clarifios the rotontion of records, ,
modifies definitions, clarifies satisf actory instrument !
performance, clarifies the purposo section, adds call-back and verifiestion on the Emergency Notification System (ENS), ,
adds roll call on the Nuclear Accident Reporting The System (NARS).
accordance with recent management reorganization.
position title changes requiro revision to the EcorgencyThe rest of t Plan, which is part of the FSAR.
are consistent with the Energency Plan.
IT MAS DETERMINED THAT AN ,
AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUEST!O i l
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PROCEDURES AND DOCUMENTT 09/27/80 PAGE NO. 5
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10CFR50.59 REPORT FiJf AMENDMtlNT 38 TO RECEIPT OF THE .
AND FROM JANUARY THROUGH MARCH 1988 tm >xpor Tittt Klett tvAtuAft0 ALEF,T af 2669 (PIP te 04 a2 ,
This Emergency Plan Implomonting Procedure describos tho actions to be taken in response to an "Alert" omorgency This revision changes the phrano "Emergency classification.
Action Level Classification" to "Emergency Classification",
revises the text format, provides direction regarding preparation of emergency closo-out reports, and corrects t
' personnel titles in 'the accordance personnel with recant title management changes require reorganization. revision to the Emergency Plan, which is part of the FSAR.
The relt of the changes are consistent with the Emergoney Plan. '
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIE'TED SAFETY QUESTION DID NOT EXIST.
SITE ARP' EMER,*ENCY 87 2668 (Pir (t c5 et k- This Emergency PlanThis Implomonting Proceduro describes revision changes the phrano ,
-~ omorgency classification. l "Emergency Action Lovel Classification" to "Emergency l Classification", providos direction regarding the '
preparation of emergency closo-out reports, revison the text format, and corrects personnel titles in accordance with ,
recent management reorganization. The personnel titic changes require revision The to the rest of Emergency the changes Plan, are which is consistent part of the FSAd.
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with the Emergency Plan.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION DID ,
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6 PROCEDUREC AND DOCUMENTS 09/27/88 PAGE NO.
10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT Ot TdE OPERATING I.IC I AND FROM JANUARY THROUGH MARCH 1988 too coammt l' tyAtuA1(O TITLt WUh.!t I
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ar her trip tc M a2 GENERAL EMERGENCY !
! t This Emergency Plan Implementing Procedure describes the I actions to be taken in responsa to a "Genet?al Emergency" :
emergency classification. Thia tavision revises the !
definition of General Emergency, and changes the phrase i "Emergency Action Level ClassLficatien" to "Emergency Classification". In addition, thin revision provides I
direction regarding preparaticoand of waargency corrects personnel closeout titles .
r reports, revises text format, in accordance with recent management reorganization. The [
i personnel title changes require revision to the Emergency [
Plan, which is part of the FSAR. The rest of the changes i are consistent with the Emergency Plan. f r
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT FXIST. l I
i 68 0096 trte fr 01 t3 TECHNICAL SUPPORT CENTER OPERATY.ONS This Emergency Plan Implementing Procedure describes the ;
performance of activities in the Technical Support Center L (TSC).
This revision modifiec text to improve compat*bility !
with related procedures, adds a requirement to connect the !
i health physics network (HPN) telephone upon TSC activation, ;
revises the definition of contaminated, and corrects i personnel titles in accordance with recent management [
reorganizeLion. The personnel title changes require revision to the Emergency Plan, which is part of the FSAR. l 6
The rest of the changes are consistent with the Emergency Plan. l AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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09/27/88 7 PROCEDURES AND DOCUMENTS PAGE NO. NG LICENSE 10CFL50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF AND FROM JANUARY THROUGH MARCH 1988 LOG 00CLMENT TITLE NUM8ER EVALUATED 88 0097 EPIP FE*03 a2 EMERGENCY OPERATIONS FACILITY OPERATIONS This Emergency Plan Implomonting Procedure (EPIP) describes the performance of activities in the Emergency Operations Facility (EOF) . This revision modifies text to improve compatibility with related procedures, adds a requirement telephone upon EOFto connect the health physics network (HPN) and activation, revises the definition of contaminated, corrects personnel titles in accordance with recentThe personnel title management reorganization.
require revision to the Emergency Plan, which is part of the FSAR.
The rest of the changes are consistent with the Emergency Plan.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION D 83 0096 EPIP FE*04 R2 BACKUP EMERGENCY OPERATIONS FACILITY OPERATIONS provides
(~N This Emergency Plan Implementing Procedurc (EPIP)
() guidance on operations at the Backup Emergency Operations Facility (BEOF) once it is determined that the EOF is no This revision clarifies transfer of longer habitable. command authority, provides additional guidance on therevis information required during notifications, of members required to relocate to reflect only key personnel, changes the definition of activation to clarify adds a when the facility is ready, clarifies access to BEOF, checklist for activation, corrects the street address of the BEOF, and changes position titles in accordance with recentThe management reorganization.tillo changes require a revision to the Em which is part of the FSAR. The rest of the changes are consistent with the Emergency Plan.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION D O
09/27/88 8 PROCEDURES AND DOCUMENTS PAGE NO.
m/ 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF T AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT TITLE NUMBER EVA14ATED 88 0036 EPIP FE 06 R2 EMERGENCY COMMUNICATIONS EQUIPMENT provides This Emergency Plan Implementing Proceduro (EPIP) descriptions of the communications systems available and the proper techniques to be employed when conductingThis revision deletes communications in an emergency.
unnecessary definitions, simplifies information regarding omergency communications systems, updates the dial code for the Nuclear Accident Reporting System when a "Goneral "Emergency Emergency" is declared, revises Attachment 2,to improve usefulness, Radio System (s)",
personnel titles in accordance with the recent managementThe reorganization.and to the personnel titles require a revision to theThe rest of the Emergency Plan, which is part of the FSAR.
changes are consistent with the Emergency Plan.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION DID A
U S3 0040 EPIP RA 01 R3 MANUAL RADIOLOGICAL DOSE ASSESSMENT This Emergency Plan Implomonting Proceduro (EPIP) is a i
manual radiological dose assessment proceduro used as a This backup to,the computorized dono assessment method.
revision adds correction timo for factors correction factorsoffluent the accident and count rato monitors, revisos the doso conversion factors, adds channel add unfiltered vontilation releases, and corrects position titles in accordance with the recent managementThe personnel title reorganization. revision to the Emergency Plan, which is part of the FSAR.
The rest of the changos are consistent with the Emergency Plan.
AS A RESULT OF THE EVA'.'JJATION, If WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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() 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OP AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT TIfiE NUMBER EVALUATED 88 0095 EPIP RA 08 R2 RADIOLOGICAL INJURIES This Emergency Plan Implementing Procedure provides guidance when handling and transporting personnel who are or may be radiologically contaminated because of an injury uithin a Radiological Controlled Area. This revision revises the procedure format; providos information for generatingacciden j serious injury, and minor injury; replaces the term patient with victim; revises references; revises the scope of first aid for minor injurics; and corrects personnot titics inThe accordance with the recent management reorganization.
personnel title changes require revision to the Emergency Plan, which is part of the FSAR. The rest of the changes are consistent with the Emergency Plan.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
FIRE PROTECTION EVALUATION REPORT AMENDMENT Q(7 88-0207 PER AMEWo 2 (FPER) is being The Fire Protection Evaluation Reportinformation concerning amended to incorporate "as-built" This amendment fire protection features of the plant. includes revisions to the combust wall thicknesses, the fire barrior ratings, thethenumber of floor drains, the floor areas (square foot),
detection /supprossion systems, and the fire protection featuro drawings. These changes comply with the requirements of 10CFR50 Appendix R and do not increas arca, physically alter any fire barrior, affect the design drainage capability, or adversely change the detection /supprossion systems.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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09/27/88 10 PROCEDURES AND DOCUMENTS PAGE NO. OPERATING LICENSE f}
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10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF TH AND FROM JANUARY THROUGH MARCH 1988 LOG 00CUMENT flTLE NUM8ER EVALUATED G 0088 FPER FIC FP 17s DERATING OF RADWASTE BUILDING FIRE RATED WALL Figure FP-176 in the CPS Fire Protection Evaluation shows a 1.9 hourReport and Safe Shutdown Analysis (SSA)
(FPER) fire rated wall surrounding row a stairwell and alovator at in H.9, elevation 720'-6" approximately column 124.9,Penotration 1SR2126 is located ini the radwaste building. 723'-1 1/2" and does not have a f ro this wall at elevation Figure FP-178 will be revised rated damper. The portion of to show the wall surrounding the penetration as non-fire rated. Derating the fire rated wall is acceptable because the combustible load is estimated to be within acc with no safe shutdown significance, and there is another i onclosed stairwell with fire rated walls located in th s building.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION
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' es 0263 rsAR 1.8 VENTILATIOh FILTER EXCEPTIONS TO REGULAT This FSAR chango identifies paragraphs of Regulatory Guido 1.140, Rev.
comply.
O, with which Clinton Power Station does no provido guidance on the maintenanco and removal Although spacothe j requirod for ventilation filter components. by specific requirements of the regulatory guido are not mot
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l the radwaste building ventilation system and the drywel adequato maintenanco spaco and access are i purgo system, provided as a result of the specific physical configurat on of the filter units in thoso systems.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVA1JJATION,UNREVIEWED SAFETY QUESTIO t
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PROCEDURES AND DOCUMENTS 09/27/88 PAGE NO. 11 l
(, 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERA AND FROM JANUARY THROUGH MARCH 1988 LOG 00CU(NT TITLE WWe0ER EVALUATED 87 2659 isAA 13.2 TRAINING j
Section 13.2 of the FSAR describes and outlines various training programs at Clinton Power Station which are structured to comply with the applicable regulatory requirements. The changes made in Section 13.2 of the FSAR involve the Licensed Operator Requalification Program and are a result of changes to the program because of revisions Rev. 2. This FSAR made to 10CFR55 and Regulatory Guide 1.8, change will reflect that the CPS training program is in compliance with newly revised regulatory guidelines.
AS A RESULT OF THE EVALUATI ,, IT WAS DETERMINED THAT AN UNREVIEWED SAFE QUESTION DID NOT EXIST.
88 0227 FSAA 14.2.12.2 REACTOR RECIRCULATION PUMP COASTDOWN REQUIREMENT The acceptanco criteria for the reactor recirculation pump N coastdown test in FSAR section 14.2.12.2.27.4B incorrectly s
requires that the flow coastdown transient Sinco thebe equal to limiting or curves faster than the limiting curves.
defined by the Transient Safety Analysis Design Report are maximum and minimum curvos, the coastdown transient result must be betwoon the two. This FSAk chango corrects the pump coastdown critoria and ensures that the results of the pump coastdown' tost are consistent with the design analysis values.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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PROCEDURES AND DOCUMENTS 09/27/88 PAGE NO. 12 p,
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\_/ 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPE AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT TITLE NUMBER EVALUATED 88-0248 tsAn 14.2.12.2 REVISE MAIN STEAM LINE FLOW VENTURI DIFFERENTIAL PRESGUR I
This FSAR change revisos the startup test Level 2 acceptance criteria for The the value main specified steam line flowFSAR in the venturi differential is incorrect and pressure.
is being revised from 84.60 pounds per square inch to 79.71 pounds per square inch. The revised value is consistent with original design specification of the venturi. No change is being made to the function and physical configuration of the venturi.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
88 0235 rsAR 14.2.12.2 SOURCE RANGE MONITOR COUNT RATE CRITERIA This FSAR change revisos the sourco range monitor (SRM) the SRM
- count rato critoria in the following startup tests:
performance test and the control rod sequence test Lovel 1
{)s acceptanco critoriat and the fuel loading and the fullfor The requirement coro a
s, shutdown margin test proroquisites.
minimum SRM count rate of 0.7 counts /socond is being revised to stato that thoro must be neutron signal count-to-noiso count ratio of at least 20:1 on the required operablo SRMs with a minimum count rate of 0.7 counts /cocond; otherwise, there must be a noutron signal count-to-noiso count ratio of a least 2:1 with a minimum count rate of 3.0 counts /second.
This chango brings the FSAR into conformance with the more stringent requirements of the Technical Specifications.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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09/27/88 13 PROCEDURES AND DOCUMENTS PAGE NO.
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k/ 10CFR50.59 RP. PORT FROM AMENDMENT 38 TO RECEIPT AND FROM JANUARY THROUGH MARCH 1988 LM MOMENT TITLE MMBER EVALUATED u ots isAn 2.1.1.3 BOUNDARIES FOR ESTABLISHING EFFLUENT RELEASE LIMIT This FSAR change revises the name of the rostricted area to be the owner controlled area (OCA) and removec a statement 1
Also, the requiring periodic surveillances of the OCA.
description of the cyclone fence (that fence which establishes the boundary of the OCA) was revised from "preventing access" to "restricting access" to the OCA.
These changes do not affect plant radiation protection, the control of access to the Protected Area, or security systems.
There are no regulatory requirements for maintaining periodic surveillances or for preventing access to the OCA.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWEC SAFETY QUESTION DID NOT EXIST.
88 0024 tsAA 2.3.3.2 DELETE CHECK OF RECORDED AIR TEMPERATURE
(~ FSAR section 2.3.3.2 provides a description of the
(_j maintenance and calibration of meteorologicalThe FSAR requiremon
' instrumentation.
temperatures against values obtainedis on the tower w This requirement thermomotors is being deleted.
redundant since temperature sensors are calibrated semi-annually using an ico bath.
' AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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14 PROCEDURES AND DOCUMENTS 09/27/88
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ss/ 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT TITLE NUMBER EVALUATED 88 0084 FsAn 2.5.4.13 SETTLEMENT MONITORING PROGRAM FSAR section 2.5.4.13 and Figure 2.5-438 describe the plant l
settlement monitoring program and graph the settlement data, respectively. The plant settlement monitoring program was instituted to track plant settlement and monitor excessive or differential settlement. Review of settlement data shows that plant settlement hasFSAR stabilized Figurewell within 2.5-438 willthe be revised predicted design rango.
to update plant settlement graphs, and FSAR section 2.5.4.13 will be revised to discontinue the settlement monitoring program.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
4 88 0224 FSAR 3.5.1.7 INTERNALLY GENERATED MISSILES FROM PRESSURIZED COMPONENTS This FSAR change revises the description of the methodology
\
) used to analyze the effects of internally generated missiles from pressurized components. Single nut, bolt, nut and s,
bolt, and nut and stud combinations are being excluded from consideration as potential missiles since the stress lovels to which these bolts and studs are torqued result bolt in a or strain en, orgy which is too Also, low tothe permit the nut, 5 foot radius critoria stud to becomo a missile.
for thermowell impact analysis was oliminated so that all including those beyond a 5 potential impacts are analyzed,FSAR Table 3.5-9 is being revised to show the foot radius.
results of the revised thermowell impact critoria. Tho revised table shows that no potential thormowoll missilos could hit and disablo components which are casential for safo shutdown of the plant. 1 AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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15 PROCEDURES AND DOCUMENTS 09/27/88 PAGE NO.
\_) 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING AND FROM JANUARY THROUGH MARCH 1988 LM M CMENT
). ,4 NUMBER EVALUATED 88 0016 Fsat 5.4.5.4 MAIN STEAM ISOLATION VALVE TESTING FSAR section 5.4.5.4 describes the inspection and testing of the Main Steam Isolation Valves. The level of detail Rev. 3, provided is not required by Regulatory Guide 1.70,and is not discussed the Standard Review Plan (NUREG 0800),
in the Safety Evaluation Report (NUREG 0853) or its supplements. This FSAR change deletes detail which is not required to be in the FSAR.
AS A RESULT OF THE EVALUATION, IT FAS DETERMINED THAT AN UNREVIEWED SAFEfY QUESTION DID NOT EXIST.
88 0289 FSAA 6.4 REVISE CONTROL ROOM VENTILATION SYE TEM DESCRIPTION 1
This FSAR change revises the description of the control room ventilation (VC) system to include a description of the locker room exhaust fan, the locker room exhaust fan trip
' logic, and the maximum outside air purge damper trip logic.
This FSAR chango also revises the humidity control zones of
((_T) the VC system and specifics that a positive pressure is not
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maintained in the control roca wh.:n the VC system Thoso is operating in the maximum outside air purgo modo.
revisions do not affect the ability of the VC system to maintain, control room habitability during its normal and accident modes of operation.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN
' UNREVIEWED SAFETY QUESTION DID NOT EXIST.
PAGE NO. 16 PROCEDURES AND DOCUMENTS 09/27/88 m, 10CFRSO.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING LICENSE AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT EVALUATED TITLE NUM8ER 88 0286 FSAR 6.4, 9.4 DESIGN AND TESTING OF THE CONTROL ROOM VENTILATION SYSTEM i
FSAR sections 6.4 and 9.4 describe the design and testin; of the control room ventilation (VC) system. These sections are being revised to indicate that the control room is divided into seven independent environmental control zones instead of six; that the cooling capacity of the VC system was verified by a temperaturo survey instead of a heat balance; and that the positivo pressure maintained by the VC system is 1/8" water gauge instead of 1/4" water gauge.
Those changes do not affect the ability of the VC system to maintain tb- habitability of the control room.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
i 88 0229 rsAR 6.5.1 SGTS, VR SYSTEM, AND DRYWELL PENETRATION DESCRIPTIONS gT This FSAR change revisos the descriptions of the standby gas
( ,) treatment system (SGTS), the containmolit building ventilation (VR) syscom, and drywell ponotrations. The
,w calculated capacity of the SGTS equipment train standby cooling air fan in FSAR section C.5.1.1.1 is being revised from 12,300 BTU /hr to 12,700 BTU /hr. This chango is the result of.a revised calculation which demonstrates an increased margin in the fan's capacity for heat removal.
Also, the intograted dose for the onco-in-lifetimo post loss of coolant accident scenario, with respect to the control room ventilation system makeup air filter packages in FSAR section 6.5.1.6, is boing revised from 2E+08 rads to lE+05 rads to agroo with the original design specification. .
I Finally, the description of drywell ponotrations IMD-154 and 1MD-194 in FSAR Tablo 3.8-5 is being revised to denoto that the ponotrations are being used for the containment monitoring system. This will correct a discropancy betwoon the table and the piping and instrumentation diagram (FSAR Figure 7.6-23) which shows the correct configuration.
AS A RESULT OF Ti!E EVALUATIO!!, IT WAS DETERMINED TilAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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PAGE NO. 17 PROCEDURES AND DOCUMENTS 09/27/88 g,
(_,) 10CFR50.59 REPORT FROM AMENDHENT 38 TO RECEIPT OF THE OPERATING LICENSE AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT NUM8ER EVALUATED T I T'.E
'7 I C-0237 rsAt 6.7 TIMER AND PRESSURE SENSOR ADDITION TO THE MSIV-LCS This FSAR change revises section 6.7.2 and Table 6.7-1 to reflect the addition of a timer and a pressure sensor to the downstream portion of the main steam isolation valve leaktge j control system (MSIV-LCS). The timer adds a 6 minute initiation delay and, together with the pressure sensor, provides a permissive signal which allows the downstream MSIV-LCS to be transferred from the depressurization mode to the bleed off mode of operation. Thic permissive signal will ensure that the main steam lines are depressurized prior to the system being aligned to the MSIV-LCS blowers so that blower damage is avoided. The new instrumentation improves the overall ability of the MSIV-LCS to process leakago.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
88 0232 rsAt 6.7.3.5 MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL SYSTEM g . ,.
Flow limiters in the main steam isolation valvo leakago control system blood linos are used to automatically isolate the blood' lines from their associated steam line at a given flow rato.. This FSAR change updatos the range of typical flow rato actpoint values by referring to the actual sotpoints. The actual sotpoints are specified in the Technical Specifications.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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18 PROCEDURES AND DOCUMENTS 09/27/88 PAGE NO.
() 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATI AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT TITLE NUM8(R EVALUATED 88 0181 rsAn 7.2 REACTOR PROTECTION SYSTEM This FSAR change revises the description of the reactor protection (RP) system roset switch and the setpoint of the turbine stop valve and turbine control valve fast closure.
The description of the reset switch is being revised to state that manual reset is prohibited for 10 seconds after a single trip logic is tripped. This will onnure that the RP system fully responds to the trip signal prior to it being roset. The setpoint of the turbine stop valve and the turbine control valve fast closure is being revised to 40%
of rated reactor power. This setpoint is consistent with the original design of 30% turbine shell pressure.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
88 0247 rsAn 7.3.1.1.2 REVISE METHOD OF MAIN STEAM LINE AREA LEAK DETECTION This FSAR change revises section 7.3.1.1.2.4.1.3.1 to correct the description of the method used to detect a main steam lino leak in the main steam tunnel. The revised description states that the temperature difference of the water ontoring and leaving the air cooling units in the main steam tunnel will be monitored instead of the air temperatubo difference. Thoso methods of main steam line leak detection are equivalent because an increase in heat gain to the main steam tunnel can be detected by a chango in the temperature difference of the cooling water across the coolor. Monitoring the temperaturo difference of water ontoring and loaving the air cooling units is the common method of steam lino leak detection used in areas outsida the containment.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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PROCEDURES AND DOClidLNTS 09/27/88 PAGE NO. 19
(, n\ 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF TH AND FROM JANUARY THROUGH MARCH 1988 DOCUMENT LOG fifLE NUMBER EVAWATED y,
88 0266 rsa 7.4.1.4.4 INSTRUMENTATION ADDITIONS TO THE REMOTE SHUTDOWN PA This FSAR change revises the description of the remoto shutdown panel to reflect the addition of a suppression pool temperature indicator and a control switch to the panel.
The control switch operates the shutdown service water system bypass valve to residual heat removal system heatThese exchanger lA. enhance the operator's ability to bring the plant to aThe safe shutdown when thehave added components mainbeen control room is designed uninhabitable.
tospecifications.
moot the original seismic, environmental, and electrical l IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION DID 88 0290 rsAt 7.7, 9.4 DELETE CONTAINMENT PRESSURE INTERLOCK IN VR/VQ SY This FSAR change revises sections 7.7.1.16.1 and 9.4.7.2.2 to delete reference to a containment pressure interlock on O the drywoll purgo (VQ) system / containment ventilation (VR)
The FSAR stated that those valves system isolation valves.could not be opened unless the containment pressu This interlock is not necessary as those than 3 psig.valvos are 4,nterlocked with high drywoll pressuro and loss of coolant accident signals, both of which will prevent the opening of the VQ/VR system isolation valvos prior to the containment reaching 3 psig.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN !
UNREVIEWED SAFSTY QUESTION DID NOT EXIST.
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09/27/88 20 PROCEDURES AND DOCUHENTS P/4r IfD. ING LICENSE
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10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT O AND FROM JANDARY THROUGH MARCH 198C LOG DOCUMENT TifLE NUMBER EVALUATED 8s 0265 rsAa 7.7.1.9 REVISE DESCRIPTION OF RADIATION MONITORING SYS This FSAR change makes minor revisions to the description l of the radiation monitoring system monitors and the contra control terminals to clarify the oporation of the "as-built" configuration. No changes woro mado to theAlso, design orthe functions functional requironents of the system.
j of interfacing systems are not affected by those changes.
IT WAS DETERMINED TIIAT AN l
AS A RESULT OF TIIE EVALUATION,UNREVIEWED SAFETY QUESTION D ,
e3 0257 rsAn s.3.1.4.4 REVISION TO INSTRUMENT CABLE ROUTING CRITERIA This FSAR change allows for deviations from the routing Presently, critoria for instrument instrument and control cables that share racowayscables.
with control cables cannot be run parallel to the control cables unless tho raceway is equipped with internal Exceptions barriors which provide to this added electromagnetic shiolding.
()N s requirement would be allowed in individual cases when
-It justified by supporting analysis This chango which does moots the not adversely critoria of impact IEEE Standard 384.
plant safety because cach exception must be supp of the cable routing.
IT WAS DETERMINED T!!AT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION V
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PROCEDURES AND DOCUMENTS 09/27/88 PAGE NO. 21 EIPT OF THE OPERATING LICENSE
'(_ 10CFR50.59 REPORT FROM AMENDMENT 38 TO REC ;
AND FROM JANUARY THROUGH MARCH 1988 Loc oooJMENT flTLE NUMBER EVALUATED 88 0245 tsAn 9.1 DELETE FUEL CHANNEL GAUGING FIXTURE This FSAR change deletes section 9.1.4.2.3.6 and Figuro 9.1-10 which describes the fuel channel gauging fixturo.
The fixture was designed to be used in detecting The fixture is being unacceptable warpage of fuel channels.
eliminated because industry experience with fuel channels similar to the fuel channels used at Clinton Power Station has shown that warpage is unlikely and that any warpage can be detected by a friction test. This friction test has boon incorporated into proceduro 2212.01, "Fuel Channel Management".
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
88 0278 rsAn 9.1.4.2 REVISED USE OF RE) CTOR VESSRL HEAD STRONGBACK N
This FSAR change revisos the description of the reactor head
,'-) strongback to allow its use whenThe moving the drywoll combined weighthead of theto and from its storage location.
drywell head and the strongback Also, is within the rated capacity the weight of the of the containment polar crano.
drywell head is loss than the rated capacity of the strongback.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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7.x PAGE NO. 22 PROCEDURES AND DOCUMENTS 09/27/88
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JNs/ 10CFR50.59 REPOP.T FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING LICENSE AND FROM JANUARY THROUGH MARCH 1988 uM D% DENT WLMBER EVALUATED fiiLE I
88 0288 FsAa 9.4 REVISE VR SYSTEM AND VQ SYSTEM DESCRIPTIONS This F3AR change clarifies the operation of the containment buildin? ventilation (VR) system and the drywell purge (VQ) system following a loss of power or instrument air. The FSAR currently states that a single switch is provided to reopen the VR/VQ system isolation valves after a loss of power or instrument air. Since certain modes of VR/VQ system operation require that several combinations of f switches be manipulated te reopen the isolation valves, the FSAR is being revised to state that operator action is required to reopen the valves. This FSAR change also revises the description of the VQ system charcoal bed deluge system. The FSAR currently states that deluge of the i charcoal beds is automatic when high temperature is sensed.
This description is being revised to state that the deluge is not automatic, and that high and high-high alarms are annunciated in the control room and subsequent operator action is required to actuate the deluge. Automatic delugo of the charcoal filter units is not required to satisfy O regulatory requirements. Also, temperature alarms are conservatively set to provido ample timo for operator
~n response.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN
. UNREVIEWED SAFETY QUESTION DID NOT EXIST.
88 0267 71At 9.4.5.2.1 REVISION OF SWITCHGEAR ROOM TEMPERATURE 8 This FSAR chango revison the naximum allowable temperatures in tho switchgoar rooms from 84 degroon F to 95 degroos F during normal operation and from 99 degroos F to 104 degroos F during abnormal operation. The now allowable temperatures will not impact equipment cporation because they are still loss than the temperaturo to which tho equipment in the switchgoar rooms is environmontally qualified.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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PAGE NO. 23 PROCEDURES AND DOCUMENTS 09/27/88 jT 10CFRSC.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING LICENSE
(,/ AND FROM JANUARY THROUGH MARCH 1988 LOG 00CUMENT Nt*8ER (VALUATED TIILE 88 0225 rsAt 9.4.6.2.1c CONTAINMENT BUILDING VENTILATION SYSTEM DESCRIPTION This FSAR change corrects an inaccurato statement concerning i radioactive effluents released through the containment building ventilation system from the containment building refueling floor. The statement currently reads that "...no contaminated air is exhausted to the outside..." because the time to isolate the exhaust after detection of high radiation is 6 seconds and air travel time through the uucts is 9.9 seconds. Considering the sensitivity of the radiation moniors, this FSAR statement has been corrected to be more accurate. The FSAR has boon changsd to read
" ... release of contaminated air to the occside atmosphere is either precluded or is insignificant." The insignificant release does not affect any accident ovaluation or the consequences of an accident.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
88 0044 rsh'. APP 0 REPORT ON OUTAGES OF EMERGENCY CORE COOLING SYSTEMS
.,7 This change revises the response to Throo Mile Island (TMI)
Action Plan II.K.3.17 to clarify Illinois Power Company's position for reporting emergency core cooling system (ECCS) outages. Cho revised responso states that ECCS outagos will be reported via participation in the Nuclear Plant Rollability Data System (NPRDS). Participation in the NPRDS moots the intent of TMI Action Plan Itom II.K.3.17, and is acceptable to the NRC.
AS A RESULT OF T!!E EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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9 PAGE NO. 24 PROCEDURES AND DOCUMENTS 09/27/88 10CFR50.59 REPORT FROM' AMENDMENT 38 TO RECEIPT OF THE OPERATING LICENSE AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT TITLE NUM8ER EVALUATED 88-0268 rsAt Flo 5.1 3 REMOVE POWER FROM HIGII/ LOW PRESSURE INTERFACE VALVES This FSAR change adds a note to Figure 5.1-3 to indicate that valve 1B21-F001 will have its electrical power disconnected during normal operation to prevent it from spuriously opening.If theThis valvo is a normally closed reactor head vent valve. valve were to spuriously open while the reactor is operating at high pressure, the lines down stream of the valve would be subjected to higher pressures than for which they were designed. Also, valves 1E12-F052A
& B will have their power disconnected during power oporation to provent them from spuriously opening. Theso valvos are the steam supply line isolation valves to the residual heat removal system heat cxchangers. The above changos are the result of the spurious operations analysis performed as part of the CPS Fire Protection Shutdown Analysis. Administrative control of power to these valves 4
has boon implomonted in proceduros 3006.01 and 3312.01 to ensure that power is provided to the valves when they may be rocplired to operato.
AS A RESULT OF Ti!E EVALUATION, IT WAS DETERMINED THAT AN 4 UNREVIEWED SAFETY QUESTION DID NOT EXIST.
88 0231 FSAR FIG 5.4 13 RES,IDUAL HEAT REMOVAL SYSTEM LOOP B MINIMUM FLOW LINE During system vibration testing, it was datormined that the residual heat removal (RH) system lcop B minimum flow lino 8
had exconsivo vibration caused by a single-hole orifico installed in that lino. The single-hole orifice was replaced with a multi-holo orifico and subsequent tonting showed that the vibration had boon reduced to acceptable i lovols. The now multi-hole orifico moots all design requirements of tho original orifice including tho minimum flow requirement. This FSAR change revison the piping and instrumentation diagram to show the multi-hole orifico. ,
AS A RESULT OF Tile EVALUATION, IT W/.S DETERMINED TilAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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PROCEDURES AND DOCUMENTS 09/27/88 PAGE NO. 25 g
-( ) 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERA AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT TITLE NUM8ER EVALUATED a8-0175 isAm rio 6.7 3 MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL SYSTEM This FSAR change deletes Figuro 6.7-3 and references to the figure in the text. This figure is the functional leakage control diagram for the main steam isolation valve (MSIV) control system (IS). The information contained in the figure is also contained in the CPS electrical schematic diagrams. The electrical schematic diagrams for tbe IS system are identified in FSAR Table 1.7-1. In general, functional control diagrams are not included as FSAR figuros.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
88-0283 rsAt r!c 8.3 2A REVISIONS TO HPCS POWER SUPPLY INSTRUMENTATION This FSAR chango revison Figure 8.3-2a to show the potential transformer fuso in the high pressure core spray system (HPCS) power supply being 0.5 amps instead of 1 amp.
O. This corrects the fuso sizo to be the size recommended by the manufacturer and onsures that proper protection is the
provided for the transformors. This change also revisos phase that the synchroscopo is connected to from A to C.
The changa to the synchroscopo connection has no impact on its operation since it can work properly no matter which phase it is connected to.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN i
UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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09/27/88 26 PROCEDURES AND DOCUMENTJ PAGE NO.
() 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT O ,
AND FROM JANUARY THROUGH MARCH 1988 LM MGMNT fl1LE uustR EVALUATED 37 2663 isAt Flo s.3 3 RESIDUAL HEAT REMOVAL SYSTEM PUMP START TIMES The start timing sequence for residual heat removal (RH) system pumps lA and 1B is 5 seconds RHafter pumpclosure ofOthe 1C starts diesel generator circuit breaker.FSAR Figure 8.3-3, sheet 1, seconds shows a after 5 second breaker startclosure.
time delay for all three RH pumps.
The figure will be corrected to show the proper startingThis change wil delays as indicated above. ,
impact plant safety because the start time delay for RH pump 1C was conservatively changed from 5 seconds to o seconds.
Also, the generator load curve reflects the o second time delay for pump 1C.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION DID 33 0221 FsAt Flo 9.1 13 FUEL CHANNEL HANDLING BOOM
() This FSAR change revices Figuro 9.1-13 which shows the fuel channel handling boom. The mounting detail of the boom was changed from a floor sockot mount to a floor mounted base plato.
The now base plato design provides support Previous -
equivalent to the original socket design. functional and accide chango.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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() AND 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE FROM JANUARY THROUGH MARCH 1988 too occuncut TifLE NL.m8Et EVALUATED C 0251 ftAt fic 9.2 2 ADDITION OF ORIFICE 8 TO 8HUTDOWN SERVICE WATER SYSTE l
shoots 1 and 2, to This FSAR change r vises Figuro 9.2-2, show the addition of flow restricting orifices in the shutdown service wat1r system discharge pipes of the These residual heat removal system A and B heat exchangers. ;
orificos were added to reduce high flow conditions exhibited !
during testing in order to achieve the original design flow. '
The design of these orifices meets the piping design ;
critoria for this system.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST. .
88 0249 FSAA FIG 9.2*2 ADDITION OF ORIFICES TO SHUTDOWN SERVICE 9 WATER SY sheets 1 and 2, to
.This FS3R change revises Figuro 9.2-2, show the addition of flow restricting orificos in the shutdown service water system dischargo pipes of the fuel These pool cooling and cleanup heat exchangers A and B.orificos w ,
during testing in order to achiava the original design flow. j The design of the orificos moots the piping design critoria for this system.
AS A RESULT OF Ti!E EVALUATION, IT WAS DETERMINED TIIAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST. '
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28 PROCEDURES AND DOCUMENTS 09/27/88 PAGE NO.
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10CFRSO.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING LICENSE
!') AND FROM JANUARY THROUGH MARCH 1988 LOG 00cJMENT TITLE NUM8Et EVALUATED 88 0269 rsAA ria 9.2-6 ADD INTERTIE FROM WM SYSTEM TO TF SYSTEM This FSAR change revises the piping and instrumentation j diagram for the make-up water domineralizer (WM) system to show an intertie with the floor drain (TF) treatment system.
This intertie allows regenerative waste from the makeup
' demineralizers to be routed to holding tanks where it can The be neutralized prior to its release to the treatment pond.
holding tanks are located north of the radwaste building.
System failure will not impact any safety related equipment.
AS A RESULT OF THE EVALUATION, IT WAS DETERMI'iED THAT AN i
UNREVIEWED SAFETY QUESTION DID NOT EXIST.
l C3 0262 rsAt ric 9.3 2 REPIACE AIR OPERATED VALVE 8 IN THE LIQUID RADWASTE SYSTEM This FSAR change rosiscs Figures 9.3-2 and 11.2-2 to show )
l that the air operate 1 valves for the main radwaste filter drain valves OWEll8Ac B, and C have boon replaced with quick ,
oxhaust shuttle valvos. The function of the air operated i
valvos in to open the main drain valvos for backwashing. l The now valvos provido factor opening timos which are nooded to achiovo the "air bump" offect for an offectivo backwash.
Also, the now valves moot the required noismic, quality group, and Quality Assuranco critoria. Design provisionsThis for contr'olling radioactive releases are not affected.
chango doon not increano the amount or alter the flou of radioactivo fluids.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN U!! REVIEWED SAFETY QUESTION DID NOT EXIST.
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PAGE NO. 29 PROCEDURES AND DOCUMENTS 09/27/88 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING LICENSE AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUENT flTLE NUMBEa EVALUATED l 88 0271 rsAn rio 9.3 3 REVIFE MODEL OF BREATMING AIR SYSTEM MANIFOLDS 1
This FSAR change reflects a change in the model of the breathing air system manifolds. The original manifolds were replaced with a model compatible with the radiation protection respiratory equipment. This change corrects the problem of respirators being incompatible with the installed manifolds. The new breathing air manifolds perform the same function as the old manifolds.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST. ,
88 0241 tsAt Fic 9.4 11 RWCU ROOM SUPPLY AIR BACKDRAFT DAMPER EQUIPMENT NUMBER ,
' I FSAR Figure 9.4-11 incorrectly identifies the equipment number of the reactor water cleanup (RWCU) system valve room D backdraft damper as being IVR43Y. This chango revises the g dampor number to IVR145Y, and thus provides an accurato
.) description of the containment building ventilation system.
The original design intent of the dampor is not changed.
-,a AS A RESULT OF THE EVAIUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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PAGE NO. 30 PROCEDURES AND DOCUMENTS 09/27/88 hj 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING LICEN AND FROM JANUARY THROUGH MARCH 1S88 LOG COCUMENT EVALUATED
!!!LE WUM8Et 88 0291 rsAt ott 410.7 FIRE DOOR COMPLIANCE TO 10CFR50 APPENDIX R This FSAR change clarifien an exception to 10CFR50 Appendix R criteria by making a distinction between the swing-type fire doors and the rolling steel fire doors that are used in the diesel generator bays. Unlike the swing-type doors, the rolling steel doors are not self-closing, and the rolling steel door to the Division III diesel generator room is not locked. These rolling steel doors must be kept closed in order for the fire suppression systems in the diesel generator bays to function properly. To ensure that the rolling steel doors are maintained closed, the doors to the Division I and II diesel generator bays are locked closed and inspected weekly, while the door to the Division III l diesel generator bay is inspected daily. Also, in order to gain access to the Division III door, personnel must enter the Division I bay which is locked. Finally, a fire watch is posted whenover a rolling steel door is to be left open.
AS A RESULT OF Tl!E EVALUATION, IT WAS DETERMINED TilAT AN O UNREVIEWED SAFETY QUESTION DID NOT EXIST.
sa oNS rsAt TAs 11.5 4
SUMMARY
OF RADIOLOGICAL ANALYSES OF LIQUID PROCESS SAMPLES FSAR Tabl,o 11.5-4 providos a summary of radiological analysos performed on liquid process samples. This tablo is not referenced in any FSAR text and is being doloted from 1
the FSAR. The information provided in this table is not i
required in the FSAR por the Standard Review Plan (NUREG-0800) Section 11.5 or Regulatory Guido 1.70, Rev. 3.
AS A RESULT OF Ti!E EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID HOT EXIST.
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31 PROCEDURES AND DOCUMENTS 09/27/88 PAGE NO.
10C1'R50.59' REPORT FROM AMENDMENT38 TO RECEIPT OF THE OPERATINC LIC AND FROM JANUARY THROUGH MARCH 1988 Loc ocaseuf TITLE uuMeta EVALUATED l
as 0201 tsaa TAs 3.10 1 DELETION OF EQUIPMENT QUALIFICATION TABLES FSAR Tables 3.10-1, 3.10-2, 3.11-1 and 3.11-2 list balance and nuclear steam supply system (NSSS) of plant (BOP)ipment electrical equ which requires seismic and environmental qualification. Tables 3.11-3 and 3.11-4 provide qualification parameters. Table 3.11-20 lists BOP i
and NSSS mechanical equipment which requires environmental qualification. These tables are being deleted from the FSAR, and all text references to the deleted tables are being changed to reference Nuclear Station Engineering According Department (NSED) Maintenance Standard MS-02.00.
to Regulatory Guide 1.70 and sections 3.10 and 3.11 of NUREG
[ 0800, these tables are not required to be part of the safety analysis report. Deletion of the tables does not release the currently qualified equipment from being maintained in its qualified condition. Any such change would be the result of a separately approved modification and would be individually evaluated and documented. The qualifications of currently qualified equipment will be maintained by
,O Maintenance Standard MS-02.00.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
88 0255 FSAR T Ad 3.21 REiISE CLASSIFICATION OF DIESEL GENERATOR AIR START SYSTEM
', This FSAR change revises the quality group classification for the vendor suppiiod skid mounted piping and valves of the air start systems for the Division I and II diesel (these quality generators from "C with no N Stamp" to "D" This revision groups are defined in Regulatory Guido 1.26).
makes the classification of the skid mounted air start piping and valvon consistent with the classification of air start piping mounted on the diosol engino. The failure analysis of the air start system shown in FSAR Table 9.5-10 is not affected by this chango.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF T AND FPOM JANUARY THROUGH MARCH 1988 tm m ercur f!TLE m ysta EVALUAtt0 -
u.0250 isAA TAs 3.2 1 CMANGE IN CLASEIFICATION OF EO SYSTEM COMPONENTS This FSAR chango corrects throo entries in Table 3.2-1 associated with the classificat.4,on air start systemof the Division III components. The diosol generator (DG) electrical classification of the air receiver tank is being changed to "N/A" becauso electrical classification is not The reference to note (J) in the applicable to tanks."comments" column of the air receiver tank is being doloted because note (J) applion to vendor Finally, skid pipingtheand valves, "Quality and not to the air receiver tank.
Assurance Roquiremont" column for piping and piping"B". This change comporonts is being changed from "N/A" to requires that piping and piping components conform AppendixtoD,the which Quality Assuranco requirements of 10CFR50,ato consistent with AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
M 0254 isAt TAs 3.2 1 REVISE CLASSIFICATION OF RA SYSTEM COMPONENTS This FSAR change revisos the quality group classification for the control room omorgency breathing air (RA) system from "C" to "C/D" (those quality groups are defined in Regulatory Guido 1.26).
This chango was nado to allow the use of commercial grado air pressure regulators. Tho original "C" classification was not necessary to satisfy any regulatory requiremont and was specified by Illinois Power Company to provido a highor degree of procuromont The RAcontrol, system installation, and testing of the RA syston.
is not safoty related and is not required to mitigato the consequences of any analyzed accident.
AS A RESULT OF THE EVALUATION, .IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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, e' PAGE NO. 33 PROCEDURES AND DOCUMENTS 09/27/88 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING LICENSE AND FROM JANUARY THROUGH MARCH 1988 Loc DocuMENi NUMBER EVALUATED TifLE l 88 0228 FsAa fAs 3.7 10 SEISMIC LOADS OF REACTOR PRES 8URE VE8SEL AND INTERNALS FSAR Table 3.7-10 provides a comparison of calculated seismic loads and allowable loads of the reactor pressure j vessel and its internals. This FSAR change deletes Table 3.7-10 because the seismic and allowable load data was never listed. The required information is contained in Table 3.9-2 which is not being changed. t AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN l
I UNREVIEWED SAFETY QUESTION DID NOT EXIST.
88 0190 FsAt T AS 3.9 2 REVISE STRESSES TO REFLECT AS-BUILT PIPING STRESS ANALYSES l
This FSAR table presents loading combinations, analytical !
4 methods, calculated stresses, and other design values for the most critical areas in the design of ASME Code Class 1, ;
2, and 3 components, including component cupports and core t
support structures. Values in this table are being revised to incorporate the results of the as-built piping stress 1 analysos. All of the revised values are still within the ASME Code allowables, Thorofore, this FSAR change will not L_ reduce the sa'aty of the systems involved or any other :
system.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED TilAT AN
' UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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PAGE NO. 34 PROCEDURES AND DOCUMENTS 09/27/88 IT 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING LICENSE
\d AND FROM JANUARY THROUGH MARCH 1988 ,
LOG DOCUMENT WUMBER EVALUAfto TITLE i
C 0240 isaa TAs 3.9 5 RECLASSIFICATION OF VC SYSTEM DRAIN VALVE 8 This FSAR changa deletes 8 control room ventilation (VC) i system drain valves from Table 3.9-5, "Balance of Plant
! Active Valves and Pumpa," because their classification has been changed from active to possive. These drain valves open to allow fire protection water to drain from the VC l charcoal filters after actuation of the fire protection deluge valves. Failure of the drain valves to open does not create a flooding concern because a plant operator is i required to verify that the VC filters properly drain upon i i actuation of the fire protection deluge valves. If 7 necessary, the operator can manually open drain valve. !
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN i UNREVIEWED SAFETY QUESTION DID NOT EXIST.
i M 0M2 r ut TAs 5.2 6 CORRECT UNIT 8 OF MEASUREMENT FOR CONDUCTIVITY ,
t
) This FSAR change corrects the units of measurement for conductivity in FSAR Table 5.2-6 from "mho/cm-25 degrees C"
__' to "nicromho/cm-25 degrees C". This chango doos not affect any plant equipment because all applicable equipment has i bonn designed to achieve and measure in the "micro" range. -
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST. t
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_ _ . _ _ _ _ __ 4-I PAGE NO. 35 PROCEDURES AND DOCUNENTO 09/27/88
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(,, 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING LICENSE AND FROM JANUARY THROUGH MARCH 1988 LOG 000Mdf ,
spe(t EVACATED fifLE l C>0244 tsAn TAs 6.2 47 CLARIFICATION OF VR SYSTEM VALVE CLOSURE TIME REQUIREMENTS
' This FSAR change adds a reference to note 29 of Table 6.2-47 for valves IVR007A and B and IVR006A and B. These valves are in the continuous containment purge (VR) system. The addition of this reference provides clarification that the source of the valve closure times and the requirments for the periodic surveillances are the ISI Program and the Technical Specifications, respectively.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
48 0115 FSAA TAs 6.2 47 POST ACCIDENT SAMPLING SYSTEM VALVE SIEE CHANGE This FSAR change revises the sizes of post accident sampling system valves in Table 6.2-47.and Figure 9.3-3 because of design changes that were made to allow the system to meet flow and leak rate test requirements. The new valves are O seismically and environmentally qualified to the same requirements as the original valves.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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- PAGE NO. 36 PROCEDURES AND DOCUMENTS 09/27/88 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING LICENSE
- t. AND FROM JANUARY THROUGH MARCH 1988 LOC DOCUMENT NLeeta EVALUATED TITLE as 0243 rsAa TAs 6.t 47 DELETE CLOSURE TIME OF YALVE 1C11-F083 I This FSAR change revises the closure time for remote manual motor operated valva 1C11-F083 in the control rod drive system from "STD" to "N/A". This change makes the closure i time for this valve consistent with the closure time of other remote manual motor operated valves. By design, valva 1C11-F083 is a remote manual operated valve, i.e., no automatic actuation. Closure time is not required to be specified because operator action is needed to close the valve.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
44 0262 tsaa TAs 6.2 47 RELOCATE AND ADD VALVES TO INSTPUNENT AIR SYSTEM This FSAR change reflects the relocation of two relief valves (1IA128A & B) from the piping hatwaen the inboard and outboard conteinment isolation valves to a vendor supplied Os panel at the autcmatic depressurization system air supply
~~
bottles. The change also reflects the addition of a new relief valve (1IA128C) to the piping that supplies air from the instrument air system air amplifiers. The relocated valves wi%1 be removed from FSAR Table 6.2-47 because they are no longer containment isolation valves. Also, since they are not located within the containment boundary, they are being downgraded from ASME Section II class 2 to ASME Section VIII. The relocation of the relief valves improves the containment boundary since there are now two fewer valves whose failure could af fect containment integrity.
Also, the valves remain classified "active" in the ISI program.
AS A RESULT OF THE EVAIUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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) 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING LICENSE AND FROM JANUARY THROUGH MARCH 1988 LOC 00CLMENT Ntmett EVALUATED TITLE i as 034 FSAR TAS 6.$*3 VENTILATION SYSTEM COMPLIANCE TO REGULATORY GUIDE 1.52 This FSAR change revises Table 6.5-3 to expand the discussion of ventilation system compliance with the system, component, and environmental design criteria, the qualification testing, and the maintenance requirements of Regulatory Guide 1.52, Rev. 2. Although exceptions have been taken to specific requirements of the regulatory guida, the design and performance testing of the air filtration and absorption units which are part of engineered safety feature atmosphere cleanup systems (the control room ventilation system, the drywell purge system, and the standby gas treatment system) is adequate to ensure that they perform j
- their design function.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN 4
UNREVIEWED SAFETY QUESTION DID NOT EXIST.
i 88 0042 FSAR TA8 9.3 3 PROCESS SAMPLING TABULATION FSAR Table 9.3-3 is a tabulation of samplos taken by the process sampling (PS) system. This change deletes alarm setpoints listed in the table because there is no requirement in the Standard Review Plan or Regulatory Guido 1.70 for these sotpoints to be listed in the FSAR. FSAR l 9.3-4 is a' iso being revised to show that silica analyzers have been disconnected. The silica analyzers do not perform
, any safety function and do not interface with equipment important to safety. Silica monitoring will be performed via grab samples and laboratory analysis.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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PAGE NO. 38 PROCEDURES AND DOCUHENTS 09/27/88 m
(_j) 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECFIPT OF THE OPERATING LICENSE AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT EVALUAlt0 fiftt WUM8ta a7 2658 ut0 2.13 a2 NTD LICENSED OPERATOR REQUALIFICATION PROGRAM This Nuclear Training Department (NTD) proc) dure implomonto licensed operator roqualification training (1 described in section 13.2.2.1 of the FSAR. This procedut< revision incorporatos changes made to 10CFR55 and inc.udes a method for the development, control, and modification of study notes. These changes support the applicable regulatory requirements.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
88 0223 ota 640.13 FIELD TEST REQUIREMEFTS FOR DOOR SEALS This FSAR change revisos the field test requirements for water tight door seals from pressurized air tests to chalk / grease fit-up tests. The door seal assemblion woro
(~N leak tested by the manufacturer prior to installation at
(~_,) Clinton Power Station. After installation, a verification of propor surface contact betwoon the door seal and the door frame will ensure that the door seal functions properly.
For this reason, only the chalk / grease fit-up test is required. The chalk /groaso test does not irpact the operation,or function of the door uoals.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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PAGE NO. 39 PROCEDURES AND DOCUMENTS 09/27/88 10CFR50.59 REPORT FROM AMF ' MENT 38 TO RECEIPT OF THE OPERATING LICENSE AND FROM JANUARY THROUGH ) ' tCH 1988 ux Nxwat RM8tt EVALUATED f!fLE 88 0206 ssA Antuo 2 SAFE SHUTDOWN ANALYSIS AMENDMENT The Safe Shutdown Analysis (SSA) is being amended to incorporate "as-built" information concerning fire protection features of the plant. This amendment includes revisions to the Spurious Operations Analysis Table, the equipment lists, the combustible loadings, the minimum wall thicknesses, the fire barrier ratings, the number of floor drains, the fire protection feature drawings, and the fire protectio,1 deviation drawings. These changes comply with 10CFR50 /.ppendix R and do not increase firaloadings above the rat.',ngs of fire walls for any fire area, physically alter sny fire barrier, affect the design drainage capability, decrease cable separation distances below Appendix R Section III.G or III.L criteria, or adversely change the detection / suppression systems.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
Oe30069 sSA APP A SAFE SHUTDOWN ANALYSIS, APPENDIX A Appendix A of the Safe Shutdown Analysis (SSA) provides an analysis of Cps which shows that for any spurious electrically powered valve operation, safe shutdown capabilitp is maintained. Appendix A of the SSA is being revised to include the analysis of bypass lines with motor operated valves installed around check valves. This concern was identified in NRC Inspection and Enforcement Notice 87-50. The results of this analysis concluded that this configuration does not affect the safety of the plant.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTIOM DID NOT EXIST.
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