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) | |
Text
,
- ~ -.
I
,,I ATTACIDENT 2 t
U-601279 O
l I
e f
i i
i i
CLINTON POWER STATION i
f 10CFR50.59 REPORT
{
l FOR l
f PIANT MODIFICATIONS TEMPORART MODIFICATIONS l
f
\\.
PROCEDURES AND DOCUMENTS s
O i
l l
i I
l l
)
O S310200219 881006 PDR ADOCK 05000461 K
I' t
t I
,e' e
i CLINTON POWER STATION IOCFR50.5, REPORT FOR MODIFICATIONS FROM JANUARY THROUGH MARCE I,..
4 i
t I
e e
s MOD 7FICATIONS 09/27/88 PAGE NO.
1
( j) 10CFR50.59 REPORT FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT 11TLt NUMBER EVALUAff0 INSTALL FENCE IN RADWASTE BUILDING AND SCREENHOUSE es ooro FA Aro23 This plant modification installs a fence in the radwaste This fence will function as a building machino shop.
This modification also Radiological Control Area boundary.
provides a fenced tool area in tho scroonhouse and in the Collapse 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.
ELIMINATE ALARM RELAY FEEDDACK SIGNAL IN RADI e.s otoo sx Am.33 sure t 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 during the source check.the AR system firmware to prevent the display o r~w Eliminating the alarm
(').
data during channel source checks. circuitry feedback signal durin sequence is acceptable because proper functionina of AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
L
4 1
09/27/88 MODIFICATIONS PAGE NO.
2 10CFR50.59 RdPORT FROM JANUARY THROUGH MARCH 1988
_ T
- (
LOG DoCUMENf TITLE M.MSER EVALUAff0 MODIFY RADIATION CENTRAL CONTROL TERMINALS a3 0009 rw At.34 This plant modification changes the firmware on the area radiation / process radiation (AR/PR) system contral control These changes will correct errors that terminals (CCTs).cause the CCTs to fail and will add a continu This plant alarm for FAIL and ALERT lighted alarms.
modification also changes the FAIL and ALERT tiles from stationary lights to lighted pushbutton alarm acknowledge This modification enhances the reliability of main control room annunciators and increases the operator's switches.
awareness of significant plant conditions.
P.S A RESULT OF TiiE EVALUATION, IT WAS DETERMINED TIIAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
ADANDON ELECTRODE BOILER RECIRCULATION FLOW es oota FA Astoo4 Differential pressure switches OPDS-AS023 and 24 by sensing differential pressure across recirculation pumps
(-'3 This field alteration abandons the
'~ ')
differential pressure switches in place to oliminate OASOSPA and D.
unnecessary electrode boiler trips caused by the sw This will not damage the boilor, but recirculation flow.
Overall auxiliary will result in lowered steam output.
steam system reliability will bo improved.
IT WAS DETERMINED TilAT AN AS A RESULT OF Ti!E EVALUATION,UNREVIEWED SAFETY QUESTION O_
.,i 09/27/88 MODIFICATIONS PAGE NO.
3
)
10CFR50.59 REPORT FROM JANUARY THROUGH HARCH 1988 too occuxtur TITtt NUMSit EVALUAfto DELETE DIFFERENTIAL PRESSURE ALARMS ACROSS as oos3 FA coroo',
This field alteration climinatos the high differential 040, 041, and 042, across the pressure alarms 1PDS-CD039, Upon completion of power condensato pump suction strainors. ascension testing, the fine m in-lino strainers were removed from all condensato pumps.
However, the high differential pressuro alarms which remain erroneously annunciate.
Clogging of coarse mesh scroons 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 DI REVISE DATA SHEETS FOR TIME DELAY RELAYS 87 2654 FA Croo9 This field alteration corrects discrepancies betwoon nameplato data and savon data shoots and adds a coil rating for Agastat tino delay relays located in the main contro 7-x
(
)
part dreuing numbers, and instrument service andThe corrections to the m room.
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 supprossion pool makeup, treatnent, 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 MODIFICATIONS PAGE NO.
4 10CFR50.59 REPORT FROM JANUARY THRO 70H KARCH 1988 t
i LOG 00CUMCHT IlfLE Numsta tvAtuAfto REVISE DRAWING TO SHOW EXPANSION JOINTS C-0078 FA cw oo$
for the The piping and instrumentation diagram (P&ID) system (FSAR F shows circulating water (CW) components 1CWO2MA.and B as restriction devices.
ts alteration revises the P&ID to correctly show the componen Expansion joints 1CWO2MA and B were installed as part of the original design to reduce the as expansion joints.
effects of thermal stress from the main condenser on th watorbox drain lines which are fixed in the basement floi of the turbine building.
t AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAl 7
UNREVIEWED SAFETY QUESTION DID NOT EXIST.
i l
4 LDING PROVIDE A STORAGE / MAINTENANCE AREA 88 0023 en fr so This plant modification installs a welded wire mes This f<snce will at' elevation 781' of the radwaste building.
change the cable tunnel into a storage and maintenance area l
to relieve crowded conditions in the control andUse of this area for stor
~
instrumentation (C&I) shop.
i f
4 and maintenance will not affect the structural integr ty o the radwaste building or the existing ventilation system.
l
,~
The added fire extinguishers provide the requircd fire Also, there is no safety related cablo or protection.
permanent plant equipment in the area.
I AS A RESULT OF THE EVALUATION, IT WAS DETERMINED TRA UNREVIEWED SAFETY QUESTION DID NOT EXIST.
t I
]
1 i O
d
,,s 99/27/88 MODIFICATIONS PAGE NO.
5 10CFR50.59 REPORT FROM JANUARY THROUGH MARCH 1988 n
I P
LOC 00CLMENT fifLE htsWER EVALUAf(0 REVISE POSITION OF GLAND SEAL SYSTEM VALVES 88 0035 #A csroo3 The gland steam system seal steam packingexhauster/ c from 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 controls and loop seal fill valves as normally open.
t will allow operations personnel to field adjust the valves so that the SPE drain / loop seal can be maintained at theT The gland seal proper level.
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.
REMOVE HEATER DRAIN CHECK VALVE 1HD0025 88 @M5 TA wrwr This field alteration removes heater drain check va
()
This check drain tank and replaces it with a pipe section.
valve was provided to prevent a backflow of flash Analysis turbine trip during turbine load reductions.showed that r
- Also, 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
i i
t 09/27/88 MODIFICATIONS PAGE NO.
6 10CFR50.59 REPORT FROM JANUARY THROUGH HARCH 1988
(,)
log 00CLMEnf TlftE mmett EVALMito CHANGE MATERIAL OF HP SYSTZM PUMP TOP SHAFT c)co33 #A paroo3 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 the physical properties of the replacementi.e., tens elongation, are equivalent or better than the original materials, material.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
INETALL JUMPERS TO BYPASS LEAK DETECTIO 88 0037 PM Lo 22 EE002, RF008 and Leak detection system handswitches RE001, RF009 in panel 1H13-P601 in the Main Control Room are not The present wired in accordance with the design. configuration renders t O
l This plant modification t
area sump fill timers inoperable.
installs jumpers which will bypass and eliminate the need l
for the handswitches and provide pov:r to the sump fi This modification will allow timers.
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 I
t I
()
l I
09/27/88 MODIFICATIONS PAGE NO.
7 10CFR50.59 REPORT FROM JANUAkY THROUGH MARCH 19s8 k_
LOG DOCUMENT fifLE WUMcit (VALUATCO INSTALL FLUSHING LINE TO FLOOR AND EQUIPME es ooos eM M 36 This plant modification installs a fiv~.ung lino from the system to the acid /cauntic drain makcup condensato (MC) lines of the equipment drain (WE) system f the drain This lino will allow flushing linos to provent plugging following acid / caustic additions.
(TF) system.
at acid-water This modification also adds lined check valvrinterfaces t This 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 ALLOW USE OF TEMPORARY STRAINERS IN RADWAST ss 0074 rA nro14 This field alteration adds a note to piping and
('3,)
instrumentation diagrams (FSAR Figures 11.2-2 and 11.4-3) to 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 the design for this class D piping system.
Also, the strainers will not impact pump operation b ANSI B31.1, positivo suction head difference they cause.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
l l
09/27/88 HODIFICATIONS PAGE NO.
8 10CFR50.59 REPORT FROM JANUARY THROUGH MARCl! 3 988
^N
/,
()
l LM ox& tut TITLE NUM8tt (VALUAtto REMOVE DOWHSCALE & POWER FAIL TRIP FROM PR MO 8a 0003 en Pa 34 downscale and power fail This plant modification removes ths trip functions from 16 process radit tion (PR) monitors and adds handswitches to allow a manual trip signal to beThe 16 initiated.
in the oxhaust containment fuel transfer pool vont plonum, ducts of the co in the fuel building ventilation system,ip outputs of those Tht tr containment purgo system.
monitors isolate the containment building vontilation system and the fuel building ventilation system, and start the Downscale and power fail standby gas treatment system.
annunciation for those monitors is provided in the mainTh a failed channel within the tino limit specified by the control room.
Technical Specifications.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED TilAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
l f REMOVE FILTERS IN LIQUID PROCESS RADIATION M I
L e.s oo22 fA Paroo4 This field alteration removes filtors from the inlots to seven of f-lino liquid process radiation (PR) monitors.
F' These monitors moneure the radioactivity in the liq I
l in the plant 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 design and provides an unnecessary flow restriction.
offluent.
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.
i i
l l
09/27/88 MODIFICATIONS PAGE NO.
9 10CFR50.59 REPORT FROM JANUARY THROUGH MARCH 1988 toc oot w wf ititt sweta tvattutto ADD SAM 1PLE LINE ISOLATION RthCK VALVE 8 se. cot 3 m Ps.13 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.
DELETE AUTohATIC kUNBACK OF RR FLOW CON 4 N 673 FA autoot This field alteration deletes the automatic runback of Automatic flow control valves.
reactor recirculation (RR) runback of these valves was initiated by a circulating water pump trip when all three pumps were operating with a low Loss This is a power generation feature.t 13 of condenser vacuum transients described in FSAR Chap er condenser vacv.1m.
O do not take credit for this runback feature.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTIO
-+
O
)
09/27/88 MODIFICATIONS PAGE NO.
10 10CFR50.59 REPORT FROM JANUARY THROUGH MARCH 1988
\\
tm
>x&ot Tlftt IA.M8(t (VALUAftD REVISE SAFETY CLASSIFICATION OF VALVES ISX095A u ootr FA rnoo3 safety classification of This field alteration revisos the spara valvon ISX095A and D from activo to passivo and from Those valvos are the shutdown 1E power to non-1E power.
system outlet valvos to the hydrogen service water (SX)ing compressor cubiclo coolers IVR09S and control system mixA previous modification removed the hydrogenthe cubicle IVR12S.
As a result, 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 DELETE AUTO ACTUATION OF VC SYSTEM CHLORINE M M ooc 2 m vc 42 This plant modification dolotos the automatic actuation of the chi)rino modo of the control room ventilation (VC)The
( ')
automatic actuation when chlorino is stored at least 100 system.
motors away from air intakes in containors having a capacity Presently, chlorino 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
09/27/88 NODIFICATIONS PAGE NO.
11 REPORT FROM JANUARY THROUGH MARCH 1988
)
10CFR50.59 Los ooomtut illLE,
lue(R tv&LUAfto INSTALL DOP INJECTION MANIFOLD 87240 Pm vt 05 This modification installs a permanent dioctyi phthalato injection manifold for the testing of laboratoryThis modification has (DOP) 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.
O l
l l
l i
1 l
l l
O
}
1 t
5 I
\\;
li l
f I
P l
CLINTON POWER STRTION 10CFR50.59 REPORT FOR TEMPORARY MODIFICATIONS.
FROM JAkcARY THROUGM MARCE 19..
-~
9 I
i I,
)
i 4
1 J
s
- - - ~ ~
PAGE NO.
1 TEMPORARY MODIFICATIONS 09/27/88 I
5 10CFR50.59 REPORT FROM JANUARY THROUGH MARCH 1988 LOG 00CtMtNi titte in.msta tvAwArto INSTALL STRAINERS IN SUCTION LINES OF RADWASTE PUMPS u oo39 ft e w e u ott 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 The installation of a strainer on WE surge / collector tanks.
the auction of each pump will provent resin migration into other systems.
Those pumps and their suction lines do not The 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.
REMOVE SMOKE DETECTORS FROM VC SYSTEM INTAKE AREA u oo61 tr e Mao u ott 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 combustible material and no ventilation l'
equipment.
Also, those detectors do not provido any automatic actuation.
Their removal improves operability of 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.
l I
OG i
,,e 09/27/88 TEMPORARY MODIVICATIONS PAGE NO.
2 10CFR50.59 REPORT FROM JANUARY THROUGH MARCH 1988 toc coowat Itut spots tvuuarto CRO85 TIE WM SYSTEM LINE FEEDERS TO 60FTENERS es cors itw nao so otr This temporary modification connects the makeup domineralizar (WM) system line feeder A to line softener B This allows line and line feeder 8 to line softener A.
softener B to remain in service while line tender B is Cross tying the WM line feeders and softeners repaired.
This will ensure a will increase system availability.
continued supply of high quality water for continued plant I
This modification does not impact the safety operation. design basis of the plant because the WM system performs no l
safety related function.
Also, failure of the WM system l
will not impact operation of any safety related system.
l This equipment is located in the makeup water pump house which is southwest of the plant service building.
l IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUA^ TION,UNREVIEWED SAFETY QUESTION DID NOT E INSTALL BLOWERS IN T33 TURBINE BUILDING MAIN STEAM TUNN f
sa oor, icw nao 88 019 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
s e
09/27/88 TEMPORARY MODIFICATIONS l
PAGE NO.
3
,s
\\~ J 10CFR50.59 REPORT FROM JANUARY THROUGH MARCH 1988 i /
h i
LOC 00CLMENT itttt EMatt tvAtuAfto (CRD)
ALTERNATE COOLING WATER SUPPLY FOR CONTROL ROD DRI as oost ice e asco the CRD pumps will bo out of During planned outage PO-2,This temporary modification providos an alternato cooling water supply to the CRDs by installing four hosensystem hose statio servico.
from the cycled condensato (CY)
The CRD supply lino high point vont/ low point drains.
l 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 cooling water to thoHowever, Also, multiple check CRDs.
c'sthough seal life will be shortened.
valves will provent reactor coolant inventory from leaking past the seals if seal cooling water is lost and the seals l
The system will be restored to its original degrado.
configuration at the end of PO-2.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN 1
UNREVIEWED SAFETY QUESTION DID NOT EXIST.
i O
INSTALL SPARE MOTOR OPERATOR ON RH SYSTEM VALVES ss 0091 ft e moo as c21 the motor operators on residual During planned outage PO-2, system valvos lE12-F024A and B will be removed and identical operators installed without electrical hoat removal (RH)
This will allow the valvos to be manually Those valves isolate the RH test return linos to terminations.
This modification will allow the RH operated.
i the suppression pool.
system to remain operable as required by the TechnicalThis modific Specifications.
and thus the automatic containment the plant in Mode 4, 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.
O
I i
t i
i O
t
'i I
i 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 RECEIPT OF TNE OPERRTING LICENSE AND
+-
i FROM JRNURRY THROUGM MRRCN i
1988 f
l O
l 09/27/88 PROCEDURE 0 AND DOCUMENTS PAGE NO.
1 E
l
( ) AND FROM JANUARY THROUGH KARCH 1 i
m ooctett!
Tint umsta tv ucarro EMERGENCY BREATHING AIR FILTER LEAK TEST t
I a4 024 tato.or a.o This new test procedure controls the testing of air t
inleakage of the emergency breathing air filter unit,This pr at the inlet and outlet of the filter enclosure and subjects ORA 02S.
the filter unit to vacuum conditions which are well within
)
The breathing air system is not j
its design capability.
safety related and the filter unit is not used during normal i'
plant operation
RUSKIN FIRE DAMPER DROP TEST l
88 039 2ast.ct s.0 l
This test procedure performs a drop test on Ruskin fire i
auxiliary dampers in the following ventilation systems i
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 be installed in place of a permanent t
The testing will be performed so as to maintain' system operability as required by the TechnicalIn inspection door.
Specifications.the plastic viewing windows will not impair fire protectio j
the systems will be 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[
+
i t
[
l l
l t
I
t 09/27/88 PROCEDURES AND DOCUMENTS PAGE NO.
2 OF THE OPERATING LICENSE 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT AND FROM JANUARY THROUGH MARCH 1988 tec coctetur fliLE R DEARINGS utteett (VALUAi!D FLUSH LINE FOR SERVICE WATER PUMP 1WS0 ca t u 01 035 for u@M This condition report identifies two discrepancio.', one i
the service water (WS) pumps 1WS01PA and C fl for The original a radially drilled hole in the WS pump shaf ts. design
" and The as-built finally connected to a 1/2" line.
The configuration does not include the 3/4" reducer.
l be original design also required that a 1/4" radial ho flow path for the pump bearings.
This condition report drilled and countersunk to 1/4'. justifies the acceptability il hole in tboir present configuration.does not adversely alter the the flush lino from 3/4" to 16 The 1/8" radial hole l
flow to the pump upper bearings.
impair the 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 REVISE DRAWING TO REFLECT AS-DUILT CO u oo67 ca 1 u 02 033 (FSAR Figuro 9.2-2)
The piping and instrumentation diagramspresently sh it This 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.
O i
09/27/88 FROCEDURED AND DOCUMENTS PAGE NO.
3 NG LICENSE 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT O
~.s AND FROM JANUARY THROUGH KARCH 1988 toc occLetut lifLE muMsta tvALUAff0 GENERAL REVISION OF THE CPS EMERGENCY PLAN C> M30 tua Puu at The Clinton Power Station (CPS) Emergency Plan was developed This 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.
REVIEW OF EMERGENCY PREPAREDNESS PROGRAM tJ oost EP P AP 06 a2 ensures This Emergency Plan Implomonting Procedure (EPIP) that the Emergency Plan and its associated implomonting procedures are reviewed and that revisions are made to This
/
correct inadequacios identified during the review. revi
\\s I
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 in accordance with roment management The parsonnel title changes requiro reorganization. revision to the Emergency Plan, which is part of the Fi The rest of the changes are Safety Analysis Report (FSAR).
consihtout with the Enorgency plan.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION O
l l
l 09/27/88 PROCEDURE 0 AND DOCUMENTS PAGE NO.
4 ING LICENSE l(
10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT AND FROM JANUARY THROUGH MARCH 1988 l
l Loc coaxar Tlftt CJpart tvAtuAfte i
ALERT AND NOTIFICATION SYSTEM C oo79 trir Ap.or as (EPIP) providos This Emergoney Plan Implomonting Proceduro guidanco for documenting the performanco of the alert and notification system (ANS) with respect to testing and This revision correcta rotorences to l
corrects "Siren Maintenance / Repairs Reporta, maintenanco.
the location of siren (15 due to relocatiori, and cla,
i Also, guidelines for to the Director - Emergency Response.
'ified to conform datormining siren operability have boon n
.$ monthly with system design, documents comprising performanco report have boon clarified, ano personnel titics I
have boon corrected in accordance with recent managomo reorganization.
design of the ANS because its now location moots the The position I
requirements for notification of the public.
i title char.ges require revision to the Emergency Plan, wh ch l
l is part of the FSAR.
with the Emergency Plan.
()
IT WAS DETERMINED THAT AN AS A RESULT OF TiiE E*. ALUATION,UNREVIEUED SAFETY QUESfION DID NOT E l
ElfERGENCY COMMUNICATIONS OPERABILITY CHEC te co77 tale A7 09 t2 onsures This Emergency Plan Implomonting Proceduro (EPI d
This 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 System The accordance with recent management reorganization.
(NARS).
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 l
i l
I
e.
PROCEDURES AND DOCUMENTT 09/27/80 PAGE NO.
5
~3 10CFR50.59 REPORT FiJf AMENDMtlNT 38 TO RECEIPT OF THE
)
AND FROM JANUARY THROUGH MARCH 1988 tm
>xpor Tittt Klett tvAtuAft0 af 2669 (PIP te 04 a2 ALEF,T 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 accordance with recant management
'the personnel title 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.
87 2668 (Pir (t c5 et SITE ARP' EMER,*ENCY This Emergency Plan Implomonting Proceduro describes k-This 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 and corrects personnel titles in accordance with The personnel titic
- format, recent management reorganization.
changes require revision to the Emergency Plan, which is The rest of the changes are consistent part of the FSAd.
/
with the Emergency Plan.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION DID 1
i l
l
t t
PAGE NO.
6 PROCEDUREC AND DOCUMENTS 09/27/88 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT Ot TdE OPERATING I.IC AND FROM JANUARY THROUGH MARCH 1988 I
too coammt l'
TITLt I
WUh.!t tyAtuA1(O ar her trip tc M a2 GENERAL EMERGENCY
~
This Emergency Plan Implementing Procedure describes the t
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 I
Classification".
In addition, thin revision provides direction regarding preparatico of waargency closeout r
and corrects personnel titles 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 l
UNREVIEWED SAFETY QUESTION DID NOT FXIST.
I i
TECHNICAL SUPPORT CENTER OPERATY.ONS 68 0096 trte fr 01 t3 This Emergency Plan Implementing Procedure describes the performance of activities in the Technical Support Center L
This revision modifiec text to improve compat*bility (TSC).
with related procedures, adds a requirement to connect the health physics network (HPN) telephone upon TSC activation, i
revises the definition of contaminated, and corrects i
personnel titles in accordance with recent management
[
The personnel title changes require reorganizeLion.
l revision to the Emergency Plan, which is part of the FSAR.
6 The rest of the changes are consistent with the Emergency l
Plan.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
i i
()
i l
l
09/27/88 PROCEDURES AND DOCUMENTS PAGE NO.
7 NG LICENSE 10CFL50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF AND FROM JANUARY THROUGH MARCH 1988 LOG 00CLMENT TITLE NUM8ER EVALUATED EMERGENCY OPERATIONS FACILITY OPERATIONS 88 0097 EPIP FE*03 a2 This Emergency Plan Implomonting Procedure (EPIP) describes the performance of activities in the Emergency Operations This revision modifies text to improve compatibility with related procedures, adds a requirement to Facility (EOF).
telephone upon EOF 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 The rest of the changes are consistent with the FSAR.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION D BACKUP EMERGENCY OPERATIONS FACILITY OPERATIONS 83 0096 EPIP FE*04 R2 provides This Emergency Plan Implementing Procedurc (EPIP)
(~N guidance on operations at the Backup Emergency Operations
( )
once it is determined that the EOF is no This revision clarifies transfer of Facility (BEOF) 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 The rest of the changes are which is part of the FSAR.
consistent with the Emergency Plan.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION D O
09/27/88 PROCEDURES AND DOCUMENTS PAGE NO.
8 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF T m/
AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT TITLE NUMBER EVA14ATED EMERGENCY COMMUNICATIONS EQUIPMENT 88 0036 EPIP FE 06 R2 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 AU MANUAL RADIOLOGICAL DOSE ASSESSMENT S3 0040 EPIP RA 01 R3 (EPIP) is a This Emergency Plan Implomonting Proceduro manual radiological dose assessment proceduro used as a This backup to,the computorized dono assessment method.
i revision adds timo correction factors and count rato correction factors for the accident offluent 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.
OU i
PROCEDURES AND DOCUMENTS 09/27/88 PAGE NO.
9 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OP
\\
()
AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT TIfiE NUMBER EVALUATED RADIOLOGICAL INJURIES 88 0095 EPIP RA 08 R2 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 This revision revises the Radiological Controlled Area.
procedure format; providos information for generatingaccide 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 The rest of the changes Plan, which is part of the FSAR.
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, the number of the 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 physically alter any fire barrior, affect the design
- arca, drainage capability, or adversely change the detection /supprossion systems.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION, UNREVIEWED SAFETY QUESTION DID NOT EXIST.
P
/
\\
09/27/88 PROCEDURES AND DOCUMENTS PAGE NO.
10 OPERATING LICENSE f}
10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF TH AND FROM JANUARY THROUGH MARCH 1988
~'
LOG 00CUMENT flTLE NUM8ER EVALUATED DERATING OF RADWASTE BUILDING FIRE RATED WALL G 0088 FPER FIC FP 17s Figure FP-176 in the CPS Fire Protection Evaluation Report shows a 1.9 hour1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> and Safe Shutdown Analysis (SSA) fire rated wall surrounding a stairwell and alovator at (FPER) elevation 720'-6" in row H.9, approximately column 124.9,Penotration 1SR2126 is located ini and does not have a f ro the radwaste building. 723'-1 1/2" this wall at elevation Figure FP-178 will be revised The portion of to show the wall surrounding the penetration as non-fire rated damper.
Derating the fire rated wall is acceptable because the combustible load is estimated to be within acc rated.
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
()
VENTILATIOh FILTER EXCEPTIONS TO REGULAT es 0263 rsAR 1.8 This FSAR chango identifies paragraphs of Regulatory Guido 1.140, Rev.O, with which Clinton Power Station does no provido guidance on the maintenanco and removal spaco comply.
Although the requirod for ventilation filter components.
j by specific requirements of the regulatory guido are not mot l
the radwaste building ventilation system and the drywel
~
adequato maintenanco spaco and access are i
provided as a result of the specific physical configurat on purgo system, of the filter units in thoso systems.
IT WAS DETERMINED THAT AN AS A RESULT OF THE EVA1JJATION,UNREVIEWED SAFETY QUESTIO t
s
PROCEDURES AND DOCUMENTS 09/27/88 PAGE NO.
11 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERA l
(,
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 The changes made in Section 13.2 of the FSAR requirements.
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.
REACTOR RECIRCULATION PUMP COASTDOWN REQUIREMENT 88 0227 FSAA 14.2.12.2 The acceptanco criteria for the reactor recirculation pump coastdown test in FSAR section 14.2.12.2.27.4B incorrectly requires that the flow coastdown transient be equal to or N
faster than the limiting curves.
Sinco the limiting curves s
defined by the Transient Safety Analysis Design Report are maximum and minimum curvos, the coastdown transient result This FSAk chango corrects the pump must be betwoon the two.
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.
a
PROCEDURES AND DOCUMENTS 09/27/88 PAGE NO.
12
/l 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPE p,
\\_/
AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT TITLE NUMBER EVALUATED REVISE MAIN STEAM LINE FLOW VENTURI DIFFERENTIAL PRESGU 88-0248 tsAn 14.2.12.2 This FSAR change revisos the startup test Level 2 acceptance I
criteria for the main steam line flow venturi differential The value specified in the FSAR is incorrect and is being revised from 84.60 pounds per square inch to 79.71 pressure.
The revised value is consistent pounds per square inch.
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.
SOURCE RANGE MONITOR COUNT RATE CRITERIA 88 0235 rsAR 14.2.12.2 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 full coro shutdown margin test proroquisites.
The requirement for a s,
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.
O
09/27/88 PROCEDURES AND DOCUMENTS PAGE NO.
13
(,.s')
10CFR50.59 RP. PORT FROM AMENDMENT 38 TO RECEIPT k/
AND FROM JANUARY THROUGH MARCH 1988 LM MOMENT TITLE MMBER EVALUATED BOUNDARIES FOR ESTABLISHING EFFLUENT RELEASE LIMIT u ots isAn 2.1.1.3 This FSAR change revises the name of the rostricted area to (OCA) and removec a statement 1
be the owner controlled area 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 There are no regulatory requirements for maintaining periodic surveillances or for preventing access systems.
to the OCA.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWEC SAFETY QUESTION DID NOT EXIST.
DELETE CHECK OF RECORDED AIR TEMPERATURE 88 0024 tsAA 2.3.3.2
(~
FSAR section 2.3.3.2 provides a description of the maintenance and calibration of meteorologicalThe FSAR requiremon
(_j instrumentation.
temperatures against values obtained on the tower w This requirement is 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.
O
PROCEDURES AND DOCUMENTS 09/27/88 PAGE NO.
14
~
,s
)
10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING ss/
AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT TITLE NUMBER EVALUATED SETTLEMENT MONITORING PROGRAM 88 0084 FsAn 2.5.4.13 FSAR section 2.5.4.13 and Figure 2.5-438 describe the plant settlement monitoring program and graph the settlement data, l
The plant settlement monitoring program was respectively.
instituted to track plant settlement and monitor excessive Review of settlement data shows or differential settlement.
that plant settlement has stabilized well within the FSAR Figure 2.5-438 will 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.
INTERNALLY GENERATED MISSILES FROM PRESSURIZED COMPONENTS 4
88 0224 FSAR 3.5.1.7 This FSAR change revises the description of the methodology
)
used to analyze the effects of internally generated missiles
\\
Single nut, bolt, nut and from pressurized components.
s, and nut and stud combinations are being excluded from
- bolt, consideration as potential missiles since the stress lovels to which these bolts and studs are torqued result in a bolt or strain en, orgy which is too low to permit the nut, Also, the 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.
Tho results of the revised thermowell impact critoria.
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.
1 O
u
PROCEDURES AND DOCUMENTS 09/27/88 PAGE NO.
15 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING
\\_)
AND FROM JANUARY THROUGH MARCH 1988 LM M CMENT
).
,4 NUMBER EVALUATED MAIN STEAM ISOLATION VALVE TESTING 88 0016 Fsat 5.4.5.4 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),
(NUREG 0853) or its in the Safety Evaluation Report This FSAR change deletes detail which is not supplements.
required to be in the FSAR.
AS A RESULT OF THE EVALUATION, IT FAS DETERMINED THAT AN UNREVIEWED SAFEfY QUESTION DID NOT EXIST.
REVISE CONTROL ROOM VENTILATION SYE TEM DESCRIPTION 88 0289 FSAA 6.4 This FSAR change revises the description of the control room 1
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 maintained in the control roca wh.:n the VC system is Thoso 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 10CFRSO.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING LICENSE m,
AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT NUM8ER EVALUATED TITLE 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 SGTS, VR SYSTEM, AND DRYWELL PENETRATION DESCRIPTIONS 88 0229 rsAR 6.5.1 This FSAR change revisos the descriptions of the standby gas gT
(,)
treatment system (SGTS), the containmolit building ventilation (VR) syscom, and drywell ponotrations.
The calculated capacity of the SGTS equipment train standby cooling air fan in FSAR section C.5.1.1.1 is being revised
,w 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.
l 4
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 Flow limiters in the main steam isolation valvo leakago g.,.
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.
O
PROCEDURES AND DOCUMENTS 09/27/88 PAGE NO.
18 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATI
()
AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT TITLE NUM8(R EVALUATED REACTOR PROTECTION SYSTEM 88 0181 rsAn 7.2 This FSAR change revises the description of the reactor system roset switch and the setpoint of the protection (RP) 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 The setpoint of the turbine stop valve and the roset.
turbine control valve fast closure is being revised to 40%
This setpoint is consistent with of rated reactor power.
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.
REVISE METHOD OF MAIN STEAM LINE AREA LEAK DETECTION 88 0247 rsAn 7.3.1.1.2 7.3.1.1.2.4.1.3.1 to This FSAR change revises section 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 Thoso methods of main steam line temperatubo difference.
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 Monitoring the temperaturo difference of water coolor.
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.
q
[
09/27/88 PROCEDURES AND DOClidLNTS PAGE NO.
19
(, n\\
10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF TH AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT fifLE NUMBER EVAWATED INSTRUMENTATION ADDITIONS TO THE REMOTE SHUTDOWN PA y,
88 0266 rsa 7.4.1.4.4 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 a safe The shutdown when the main control room is uninhabitable.
added components have been designed to moot the original l
and electrical specifications.
seismic, environmental, IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION DID DELETE CONTAINMENT PRESSURE INTERLOCK IN VR/VQ SY 88 0290 rsAt 7.7, 9.4 7.7.1.16.1 and 9.4.7.2.2 This FSAR change revises sections to delete reference to a containment pressure interlock on O
system / containment ventilation (VR) the drywoll purgo (VQ)
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.
GV
09/27/88 PROCEDURES AND DOCUHENTS P/4r IfD.
20 ING LICENSE 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT O
~
\\
'j AND FROM JANDARY THROUGH MARCH 198C LOG DOCUMENT TifLE NUMBER EVALUATED REVISE DESCRIPTION OF RADIATION MONITORING SYS 8s 0265 rsAa 7.7.1.9 This FSAR change makes minor revisions to the description of l
the radiation monitoring system monitors and the contra control terminals to clarify the oporation of the "as-built" No changes woro mado to the design orthe functions configuration.
- Also, functional requironents of the system.
of interfacing systems are not affected by those changes.
j IT WAS DETERMINED TIIAT AN AS A RESULT OF TIIE EVALUATION,UNREVIEWED SAFETY QUESTION D l
REVISION TO INSTRUMENT CABLE ROUTING CRITERIA e3 0257 rsAn s.3.1.4.4 This FSAR change allows for deviations from the routing Presently, critoria for instrument and control cables.
instrument cables that share racoways with control cables cannot be run parallel to the control cables unless tho raceway is equipped with internal barriors which provide Exceptions to this added electromagnetic shiolding.
()N requirement would be allowed in individual cases when justified by supporting analysis which moots the critoria of s
This chango does not adversely impact
-It plant safety because cach exception must be supp IEEE Standard 384.
of the cable routing.
IT WAS DETERMINED T!!AT AN AS A RESULT OF THE EVALUATION,UNREVIEWED SAFETY QUESTION V
i i
~ +
.! ?
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 DELETE FUEL CHANNEL GAUGING FIXTURE 88 0245 tsAn 9.1 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.
REVISED USE OF RE) CTOR VESSRL HEAD STRONGBACK 88 0278 rsAn 9.1.4.2 This FSAR change revisos the description of the reactor head strongback to allow its use when moving the drywoll head to N
,'-)
and from its storage location.
The combined weight of the drywell head and the strongback is within the rated capacity of the containment polar crano.
Also, the weight of the 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.
O
PAGE NO.
22 PROCEDURES AND DOCUMENTS 09/27/88 7.x
/
')
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 switches be manipulated te reopen the isolation valves, the f
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.
O
r.
l.
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 radioactive effluents released through the containment i
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 This change revises the response to Throo Mile Island (TMI)
.,7 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.
O v
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 REMOVE POWER FROM HIGII/ LOW PRESSURE INTERFACE VALVES 88-0268 rsAt Flo 5.1 3 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.
This valvo is a normally closed reactor head vent valve.
If the 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 Theso oporation to provent them from spuriously opening.
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 UNREVIEWED SAFETY QUESTION DID NOT EXIST.
4 RES,IDUAL HEAT REMOVAL SYSTEM LOOP B MINIMUM FLOW LINE 88 0231 FSAR FIG 5.4 13 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 This FSAR change revison the piping and flow requirement.
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.
l O
PROCEDURES AND DOCUMENTS 09/27/88 PAGE NO.
25 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERA g-( )
AND FROM JANUARY THROUGH MARCH 1988 LOG DOCUMENT TITLE NUM8ER EVALUATED MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL SYSTEM a8-0175 isAm rio 6.7 3 This FSAR change deletes Figuro 6.7-3 and references to the figure in the text.
This figure is the functional control leakage diagram for the main steam isolation valve (MSIV)
The information contained in the control system (IS).
figure is also contained in the CPS electrical schematic The electrical schematic diagrams for tbe IS diagrams.
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.
REVISIONS TO HPCS POWER SUPPLY INSTRUMENTATION 88-0283 rsAt r!c 8.3 2A 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 This change also revisos the provided for the transformors.
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 UNREVIEWED SAFETY QUESTION DID NOT EXIST.
i i
O
09/27/88 PROCEDURES AND DOCUMENTJ PAGE NO.
26 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT O
()
AND FROM JANUARY THROUGH MARCH 1988 LM MGMNT fl1LE uustR EVALUATED RESIDUAL HEAT REMOVAL SYSTEM PUMP START TIMES 37 2663 isAt Flo s.3 3 The start timing sequence for residual heat removal (RH) system pumps lA and 1B is 5 seconds after closure of the RH pump 1C starts O diesel generator circuit breaker.FSAR Figure 8.3-3, sheet 1, seconds after breaker closure.
shows a 5 second start 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 FUEL CHANNEL HANDLING BOOM 33 0221 FsAt Flo 9.1 13 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 The now base plato design provides support Previous plato.
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.
O i
i PROCEDURES AND DOCUMEMS 09/27/88 PAGE NO.
27
()
10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF TH m
AND FROM JANUARY THROUGH MARCH 1988 too occuncut TifLE NL.m8Et EVALUATED ADDITION OF ORIFICE 8 TO 8HUTDOWN SERVICE WATER SYSTE C 0251 ftAt fic 9.2 2 shoots 1 and 2, to l
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.
ADDITION OF ORIFICES TO SHUTDOWN SERVICE WATER SY 9
88 0249 FSAA FIG 9.2*2 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.
The design of the orificos moots the piping design critoria j
for this system.
AS A RESULT OF Ti!E EVALUATION, IT WAS DETERMINED TIIAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
I 1
1
PAGE NO.
28 PROCEDURES AND DOCUMENTS 09/27/88 10CFRSO.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING LICENSE 7-
!')
AND FROM JANUARY THROUGH MARCH 1988 LOG 00cJMENT TITLE NUM8Et EVALUATED ADD INTERTIE FROM WM SYSTEM TO TF SYSTEM 88 0269 rsAA ria 9.2-6 This FSAR change revises the piping and instrumentation diagram for the make-up water domineralizer (WM) system to j
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 be The 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 UNREVIEWED SAFETY QUESTION DID NOT EXIST.
i REPIACE AIR OPERATED VALVE 8 IN THE LIQUID RADWASTE SYSTEM l
C3 0262 rsAt ric 9.3 2 This FSAR change rosiscs Figures 9.3-2 and 11.2-2 to show
)
that the air operate 1 valves for the main radwaste filter l
drain valves OWEll8Ac B, and C have boon replaced with quick oxhaust shuttle valvos.
The function of the air operated valvos in to open the main drain valvos for backwashing.
l i
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 provisions for contr'olling radioactive releases are not affected.
This 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.
I
)
I O
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 REVIFE MODEL OF BREATMING AIR SYSTEM MANIFOLDS l
88 0271 rsAn rio 9.3 3 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.
RWCU ROOM SUPPLY AIR BACKDRAFT DAMPER EQUIPMENT NUMBER 88 0241 tsAt Fic 9.4 11 FSAR Figure 9.4-11 incorrectly identifies the equipment I
number of the reactor water cleanup (RWCU) system valve room D backdraft damper as being IVR43Y.
This chango revises the dampor number to IVR145Y, and thus provides an accurato g
description of the containment building ventilation system.
.)
The original design intent of the dampor is not changed.
AS A RESULT OF THE EVAIUATION, IT WAS DETERMINED THAT AN
-,a UNREVIEWED SAFETY QUESTION DID NOT EXIST.
I r
P 1
e I
1
([)
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
!!!LE WUM8Et EVALUATED FIRE DOOR COMPLIANCE TO 10CFR50 APPENDIX R 88 0291 rsAt ott 410.7 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 Unlike the swing-type doors, the the diesel generator bays.
rolling steel doors are not self-closing, and the rolling steel door to the Division III diesel generator room is not These rolling steel doors must be kept closed in locked.
order for the fire suppression systems in the diesel To ensure that the generator bays to function properly.
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.
SUMMARY
OF RADIOLOGICAL ANALYSES OF LIQUID PROCESS SAMPLES sa oNS rsAt TAs 11.5 4 FSAR Tabl,o 11.5-4 providos a summary of radiological This tablo is analysos performed on liquid process samples.
not referenced in any FSAR text and is being doloted from The information provided in this table is not 1
the FSAR.
required in the FSAR por the Standard Review Plan (NUREG-0800) Section 11.5 or Regulatory Guido 1.70, Rev. 3.
i AS A RESULT OF Ti!E EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID HOT EXIST.
I O
l i
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 l
uuMeta EVALUATED DELETION OF EQUIPMENT QUALIFICATION TABLES as 0201 tsaa TAs 3.10 1 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 which requires seismic and electrical equ environmental qualification.
Tables 3.11-3 and 3.11-4 Table 3.11-20 lists BOP provide qualification parameters.
and NSSS mechanical equipment which requires environmental i
These tables are being deleted from the qualification.
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
[
these tables are not required to be part of the safety
- 0800, Deletion of the tables does not release analysis report.
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.
REiISE CLASSIFICATION OF DIESEL GENERATOR AIR START SYSTEM 88 0255 FSAR T Ad 3.21 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 generators from "C with no N Stamp" to "D" (these quality 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.
O
09/27/88 PROCEDURES AND DOCUMENTS PAGE NO.
32 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF T
(
I
'm AND FPOM JANUARY THROUGH MARCH 1988 tm m ercur f!TLE m ysta EVALUAtt0 CMANGE IN CLASEIFICATION OF EO SYSTEM COMPONENTS u.0250 isAA TAs 3.2 1 This FSAR chango corrects throo entries in Table 3.2-1 associated with the classificat.4,on of the Division III The air start system components.
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 skid piping and valves, Finally, the "Quality and not to the air receiver tank.
Assurance Roquiremont" column for piping and piping This change comporonts is being changed from "N/A" to "B".
requires that piping and piping components conform to the Appendix D, which Quality Assuranco requirements of 10CFR50,ato consistent with IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION, UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REVISE CLASSIFICATION OF RA SYSTEM COMPONENTS M 0254 isAt TAs 3.2 1 This FSAR change revisos the quality group classification for the control room omorgency breathing air (RA) system (those quality groups are defined in from "C" to "C/D" This chango was nado to allow the Regulatory Guido 1.26).
Tho use of commercial grado air pressure regulators.
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 control, The RA system installation, and testing of the RA syston.
is not safoty related and is not required to mitigato the consequences of any analyzed accident.
.IT WAS DETERMINED THAT AN AS A RESULT OF THE EVALUATION, UNREVIEWED SAFETY QUESTION DID NOT EXIST.
O I
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 SEISMIC LOADS OF REACTOR PRES 8URE VE8SEL AND INTERNALS l
88 0228 FsAa fAs 3.7 10 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 l
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN I
UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REVISE STRESSES TO REFLECT AS-BUILT PIPING STRESS ANALYSES 88 0190 FsAt T AS 3.9 2 l
This FSAR table presents loading combinations, analytical methods, calculated stresses, and other design values for 4
the most critical areas in the design of ASME Code Class 1, 2, and 3 components, including component cupports and core support structures.
Values in this table are being revised t
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.
r j
t I
i i
O
~_
PAGE NO.
34 PROCEDURES AND DOCUMENTS 09/27/88
_IT
\\d 10CFR50.59 REPORT FROM AMENDMENT 38 TO RECEIPT OF THE OPERATING LICENSE 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) system drain valves from Table 3.9-5, "Balance of Plant i
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.
i AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
i M 0M2 r ut TAs 5.2 6 CORRECT UNIT 8 OF MEASUREMENT FOR CONDUCTIVITY
)
This FSAR change corrects the units of measurement for t
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 bonn designed to achieve and measure in the "micro" range.
i AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
t
)
1 i
I V
n i
l i
l l
t
4-I PAGE NO.
35 PROCEDURES AND DOCUNENTO 09/27/88
/
~
(,,
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.
4 l
i
! O l
l
~
i e ~ e.
e 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 time for this valve consistent with the closure time of i
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 Os outboard conteinment isolation valves to a vendor supplied 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.
O
e PAGE NO.
37 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 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 j
treatment system) is adequate to ensure that they perform their design function.
AS A RESULT OF THE EVALUATION, IT WAS DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
4 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.
O
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 WUM8ta EVALUAlt0 fiftt 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 leak tested by the manufacturer prior to installation at
(~N
(~_,)
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.
l r
i
f
.o.
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.
O