ML20115A817

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Proposed Tech Specs,Relocating Spec 3/4.9.6, Refueling Platform to Document Which Is Controlled Under Requirements of 10CFR50.59
ML20115A817
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 02/29/1996
From:
PENNSYLVANIA POWER & LIGHT CO.
To:
Shared Package
ML17158B670 List:
References
NUDOCS 9607090013
Download: ML20115A817 (10)
v • d • e


Text

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_ LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE Rfou!REMENTS E

. .'8tE 3/4.8 ELECTRICAL POWER SYSTEMS

3/4.8.1 A.C. SOURCES j A. C. Sources-Operating. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-1 A. C. Seurses-5hutdown. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-9 i

3/4.8.3 0.C. SOURCES .

.a i 0.C. Sources-Operating............................... 3/4 b le i 0.C. Sources-shutdown...........................,.... 3/4 6-15 i

!, 3/4.8.3 ON5!TE POWER DISTRIBUTION SYSTEMS a

l Distribution - Operating..........'................... 3/4 9-17 1 Distribution - shutdown.............................. 3/4 6-19

3/4.8.4 ELECTRICAL EQUIPIENT PROTECTIVE DEVICES l

1 Primary Cantainment Penetration Conductor Overcurrent i Protecti ve Devices. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-22 1, 9 l Motor-Operated Valves . Thermal Overload Protection.... 3/4 4-28 1

- Reacter Protection System Electric Power Moni tori ng. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8- 33 i

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3/4.9 REPUELING OPERATIONS 3/4.9.1 REACTOR OWDE SWITCH.................................. 3/4 9-1 f

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3/4.9.2 INSTRsetTATI0N...................................... 3/4 F 3 s

! 3/4.9.3 CONTML MO P0$ITION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-5 I 3/4.9.W OECAY TDE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-4

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3/4.9.S CWetNIICAT!0NS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2/4 F7 i .

3/4.9.6 M Lp s / pTf0pt./.......,. . 4./...f.../../...f'.../ T/44 JF Dw w

. 3/4.9.7 CRANE TRAVEL - SPetf REL STORAGE 3/4 b le i P00L.................................................

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i ta Amendment No. 29

./ SUSQUENANNA - UNIT 1 4

9607090013 960610 -

PDR ADOCK 05000387
p PDR ,

j ; < . .. .p l INDEX

. BASES.

k 5.lEIE f6tE 3/4.7 PLANT SYSTEMS 1

3/4.7.1 SERVICE WATER SYSTEM 5........................... B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERGENCY OUT510E AIR SUPPLY....... B 3/4 7-1  !

i 3/4.7.3 REACTOR CORE !$0LATION COOLING SYSTEM........... S 3/4 7-1 3/4.7.4 SNUB 8E RS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3/4 7-2 l 3/4.7.5 SEALED SOURCE CONTAMINATION..................... 8 3/4 7-3 3/4.7.8 FIRE SUPPRESSION SY57 EMS........................ 8 3/4 7-3  !

i 3/4.7.7 FIRE RATED A55EM LIES........................... B 3/4 7-4 1

1 l 3/4.7.8 MAIN TURSINE BYPASS SY5 TEM. . . . . . . . . . . . . . . . . . . . . . 8 3/4 7-4 ,

1 3/4.8 ELECTRICAL POWER SYSTEMS J

i 3/4.8.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C. SOURCES

' - . and ONSITE POWER 015TRIBUT10N SYSTEMS. . . . . . . . . . . 8 3/4 8-1

,f 3/4.8.4 ELECTRICAL Equ!PMENT PROTECTIVE DEVICES......... B 3/4 8-3 I

i 3/4.9 REFUELING OPERATIONS 4

3/4.9.1 REACTOR MODE 5 WITCH............................. B 3/4 9-1 7

3/4et.2 INSTRUMENTATION................................. B 3/4 9-1 p 3/4 9-1 i 3/4.9.3 CONTROL A00 P05IT!0N............................

' 3/4.9.4 DECAY T DE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . E 3/4 9-1 I

3/4.9.5 C0f010NICATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3/4 9-1 1

si4.9.8 etru<!p{ PskrFanN. s. . ./. . . . ,t. . ./ . . . g . y n 3i4R l - J DELc2 3/4.9.7 '

CRANE TRAVEL-SPENT FUEL STORAGE 8 3/4 9-2 P00L............................................

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3/4.9.8'and 3/4.9.9 WATY.R LEVEL - REACTOR VESSEL

) and WATER LEVEL - SPENT FUEL STORAGE P00L....... B 3/4 9-2 j J

8 3/4 9-2 1

- 3/4.9.10 CONTROL 200 REMOVAL............................. ,

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3/4.9 11 RESIOUAL HEAT RS WWAL AND COOLANT CIRCULATIO i

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$USQUENANNA - UNIT 1

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REFUELING OPERATIONS 3/4.9.6 REFUELING PLATFORM i

! i>ELETEE) u m ilmi CONDITION FOR OPERATION l - 1 .

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\.9.8 The refueling platform shall be OPERA 8LE andwsed for handling fuel a

emblies or control rods within the reactor pressurgvessel.

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APP JCASILITY: Ouring handling of fuel assembifes or c\ontrol rods witnin tne j reec" pressure vessel. \,

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ACTION: \

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i With the requirements for refueling platfern CPERA8ILITY not sat'isfied, suspend

- use of any inoperahle refueling platfom equipment from operations1nvolving the handling \of control rods and fuelassembifes within the reactor" pressure i vessel after placing the load in a safe condition.

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SURVEILLANCE RE0 IREMENTS \

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4.9.8.1 The refueling platfore main hoist used'for handling of control rods l or fuel assembifes within the reactor pressure vessel shall be demonstrated

! OPERA 4LE within 7 days or to the start of such yrations by:

a. . Demonstrating operation of the overload cutaff when the cable load I is1200t50pog. N
b. Demonstrating operation of the normal uptravel stop when uptravel brings the tip of the grapple hook to greater than or equal to a feet l below the refueling floor level. '

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c. Demonstrating operation of the downtravel stop when downtravel of tne i

grapple tip is 4 + 0, - 1 inches below the top of the'fual s bundle handle.

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! d. Demonstrating operation of the slack cable cutoff when the load is j 50

  • 10 pounds.
e. Desenstrating operation of the hoist loaded interlock when the 1oac is S$0 + 0, - 30 pounds. ,

3 f. Performing a load test of UOO + 50,\0pounds applied to the hoist cable.

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i SUSQUEHANNA - UNIT 1 1/4 9-s Amendment No. 36 4

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REFUELING OPERATIONS Su b EILLANCE REQUIREMENTS (Continued)

N 4.9.6.2 The refueling platform auxilia . hoist used for handlik of control rods or f I asseenlies within the reactor pressure vessel shall 'ae demonstrated l OPERASLE w fn 7 days prior to the start ofssuch operations by: - '

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a. strating operation of the overt h cutoff when the cabia load a

is a 50 pounds. \

b. Demonst ting operation of the hoist 1 interlock when the Toad is 400 + , - 50 p.unds. y N
c. Gemenstrati operation of the downtravel stoa when less than or s equal to SS f t of cable is played out from the anxieue uptravel N Itsit. '

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d. Demonstrating oper ton of the normal uptravel stop when the cable end connector is ;-eater than or equal to 4 feet belo(the refueling l floor level. \

i i e. Performing a load test o 1000 + 50, -0 pounds app 11ed to the hoist

cable. -

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SUSQUENANNA - UNIT 1 3/4 t-9 4

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Y REFUELING 09tRATTCNS l j- ,

aAsES . I j 3/4.9.6 REFUELING PLATFORM bg,,,ggg >

ine vrpasiu p requirement.s ensure that (1) the refueling platform will T >

used for"Nand1t control rods a fuel assemblies- thin the rea or pres re ves 1 (2),each hof has sufficient capacity for ling fuel semelie and trol rods, and ( core interna pressure v 1 are pro tad j from exc ive lifting, force . event they are inadvertently aged dur g j Iffting ope,r ns.

j i.. i. 7 suas rnAVEL - $ PENT FUEL STORAGE POOL '

l The restriction on movement of loads in excess of the nominal weight of a 4 fuel assembly over other fuel assemblies in the storage pool ensures that in  ;

i the event-this load f r dropped 1) the activity release will be Itaited to that  ;

i ceintained in a single fuel assembly, and 2) any possible distortion of fuel in  !

j the storage racks will not result in a critical arrey. This assumption is j consistent with the activity release assumed in the safety analyses.

! 3/4.9.8 anc 3/4.9.9 WATER LEVEL - REACTOR vt53EL and WATER LEVEL -5 PENT FUEL l uonAGE R UL The restrictions on minimum water level ensure that sufficient water depth l

! is available to remove 9gE of the assumed 105 todine gap activity released from the rupture of an irradiated fuel assembly. This sinto m water depth is

! consistant with the assumptions of the safety analysis. l I 3/4.9.10 CONTROL A00 REMOVAL i These specifications ensure that maintenance or repair of control rods or control rod drives will be performed under conditions that limit the probability of inadvertent criticality. The requirementa for simultaneous renoval of more

than one control rod are more stringent since tne SHUTDOWN NARGIN specification i provides for the core to remain suberitical with only one control rod fully j withdrawn.

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! 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION l

. The requirement that at least one residual heat removal loop be OPERA 8LE or that an alternata method capable of decay heat removal be demonstrated and that l

an alternate method of coolant sixing be in operation ensures that 1) sufficient cooling capacity is available to remove decay heat and maintain the water in the i reactor pressure vessel below 140*F as required during. REFUELING, and 2) suffi-cient coolant circulation would be available through the reactor core to assure i accurate temperature indication and to distribute and prevent stratification of i the peisen in the event it becomes necessary to actuate the standby liquid

! control systan.

The requirement to have two shutdown cooling mode loops OPERA 8LE when there is less than 22 feet of water above the reactor vessel flange. ensures that.a 1 i single failure of the operating loop will not result in ar complete loss of resid--

! ual heat removal capability. With tne reactor vessel head removed and 22 feet l

of water above the reactor vessel flange, a large heat sink is available for core cooling. Thus, in the event a failure of the operating RHR loop, adequate  ;

l time is provided to initiata alternata methods capable of decay heet removal or j ,,

emergency procedures to cool the core. ,

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,' SUSQUEHANNA - UNIT 1 8 1/4 9-2 Amendment No.1.9 l

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! Limune CON 0!TIONS FOR OPERATION ANO SURVEILLANCE 88mIREMENT5 i IIEIE! f.8EE i 3/4. 9 ELECTRICAL POWER SY!TEMS 3/4.8.1 A.C. 5000CES i

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- A. C. Sources - Operati ng. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-1 i

i A.C. Sources - Shutdown.............................. 3/4 4-10 1

4 3/4.8.2 0.C. SOURCES

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0. C. Sources - Operati ng. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-11 i

! 0. C. Sources - Shutdown. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-14 1

i 3/4.8.3 ONSITE POWER OISTRIOUTION SYSTEMS l a.

Ofstributten -

Operating............................. 3/4 i P18  ;

01stribution - Shutdown............... .............. 3/4 F'21 5

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! 3/4.8.4 ELECTRICAL EQUIMENT PADTECTIVE DEVICES 1

! Orimary Containment Penetration Conductor Overcurrent Protecti ve 0evices . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-24 I

Notor-Operated Valves Thermal Overleed Protection.... 3/4 6-30 l

l Reacter Protection Systae Electric Power l Mani tori ng. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8- 35 4

3/4.9 REFUELJNBOPERATIONS 3/4 9-1 n.

i 3/4.9.1 REACTOR N10E SW1TCH..................................

3/4.9.2 IN5TMsENTATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9- 3 l 3/4. '/ CONTROL M10 P0$ITION. . . . . . . . . . . . . . . .'. . . . . . . . . . . . . . . . . 3/4 t 5 3/4. 4' OECAY TIM........................................... 3/4 9-4 3/4.9.5 Comast! CAT!0NS. . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-7 3/4.9.6 I$a /M. . . . . . . . . . . ./. . ./ . ./.' .y. ./. .g.' . .] }/R l 3/4.9.7 CRANE TRAVEL - SPENT F M L STORAGE 3/4 9-lo

/ r00L.................................................

in SU54UEHANNA - LNIIT 2

yv*w s:: % : % y s t. 4-s se M w ei. n~

y sASES i

1 4 .I.ES.UE! ,

f. Aft 1

!. 3/4.7 Puuff SYSTEMS i

l 3/4.7.1 SERVICE WATER SY5TEMS........................... 8 3/4 7-1 1

3/4.7.2 CONTROL ROOM EMERGENCY OUT5IDE AIR SUPPLY....... 8 3/4 7-1 4

3/4.7.3 REACTOR CORE 150LATION COOLING SYSTEM......... 7' s 3/4 7-1 3/4.7.4 $NuesERS........................................ a 3/4 7-2

! 3/4.7.5 SEALED SOURCE CONTAMINATION. . . . . . . . . . . . . . . . . . . . . 8 3/4 7-3 i 3/4.7.6 FIRE SUPPRES5!m 5YSTEMS........................ S 3/4 7-4 1

i 3/4.7.7 FIRE RATED A55EM LIES........................... 5 3/4 7-4 1

3/4.7.8 MAIN TURBIM SYPA55 5YSTEM...................... B 3/4 7-4 3/4.8 ELECTRICAi. POWER SYSTEMS j

4 i 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES,

! and ONSITE POWER DISTRIBUTION SYSTEMS........... 5 3/4 s-1 i

i 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES......... 8 3/4 4-3 I

' 3/4.9 REFUELING OPERATIONS l 3/4.9.1 REACTOR MOE 5 WITCH............................. 8 3/4 9-1 us.s.: InsTRunmTArla. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . u4 s-1 i

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I i us.s.3 COuTROL me p05 m 0N............ ............... s v4 e-1 S

u4.s.4 OscAv TIME......................................

s v4 e-1 us. s. s CmMn! car!0ns. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . s v4 9 1 3

l 3 % s.s , & M M # on s .. ....... l. 6 4 . 4 . 4 4 x g y y y p ~

l [ MS.7 CRANE TRAVEL-SPENT PUEL STORAGE p00L............................................ s v4 e a

ma 3/4.9.8 and 3/4.9.9 W TER LEVEL - REACTOR VE5SEL S 3/4 9 2 and WATER LEVEL - SPWT PUEL STORAGE P00L.......

8 3/4 9-2 1 I 3/4.9.10 CONTROL 800 REM 0 VAL.............................

k / 8 3/4 S-2

, f 3/4..t.11 RE5100AL MEAT RENMIRL AM COOLANT CIRCULATION...

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$USQUENANNA - UNIT 2 E

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!, REFUELING OPERATIONS j 3/4.9.8 REFUELING PLATFORM M E.TCD

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LIMITING CONDITION FOR OPERATION'

! 3.9.8 The refueling platform shall be OPERA 8LE and for handling fuel  !

i \ assemblies or control rods within the reactor pressure ssel.  !

LICASILITY: Ouring hand ng of fuel asseselies or cent rods within the

, reacter pressure vessel. l l \ l l  :

j With requirements for refueling Dlatfore OPERASILITY not satisfi suspenc j j use of day inoperable refueling platfare equipment from operations invo ing  ;

i the handfyng of control rods and fuel assemblies within the reactor pressure i j , vessel af ' r placing the load in a safe condition. l l

j 5URVEILLANCE QUIREMENTS l 4. 9. 8.1 The refue ng platfore asin hoist used for ling of control rods J

ior fuel. assemblies w thin the reactor pressure vesse1Nha11 be demonstrated _.

0PERABLE within 7 day prior to the start of such opera' s by:

a. Demonstrating ration of the overload cutoff the cable load  ;

l is 1200 2 50 po s. 3 1

l . b. Demonstrating operation of the ne,rmal uptravel stop n uptravel  !

j brings the tip of thAgrapple hook to greater than or ual to  ;

] 8 feet below the refueling floor level.  ;

c. O b' strating operation of the downtravel stop when downtra el of the e tip is 4 + 0, - 1 feches below the top of the fuel 4)qdle  ;
I handle. N i

l d. Demonstrati operation of the slack cable cutoff when the load is MzM

-N I Demonstrating ope tion of the hoist \ oaded interlock when the load a.

is 550 + 0, - 50 pou'hds. ,

f. Perfoming a load test of 1200 + 50 -0 pounds applied to the hoist Q cable, i

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SUSQUEHANNA - UNIT 2 Va PS i

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REFUELING OPERATIONS D a e N_.

SURVEILLANCE REQUIREMENTS (Contirmed) 4.9.6.2 The refueling platform auxiliary hoist used for hand 11 of control rods or fuel assemeltes withto the reactor pressure vessel shall besdemonstrated OPEAABLE within 7 days prior th e start of such operations by:

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i a.- Demonstrating operation of the overload cutoff when the cable \1oad j xis 1000 2 50 pounds.

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b. Demonstrating operation of the. hoist loaded interlock when the load is 400 + 0, - 50 pounds.
c. DemonstratingoperationofthedoMravelstopwhenlessthanor i
equal to 85 feet of cable is played aut from the maxieue uptravel ,

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d. Demonstrating operation of the normal uptravel stop when the cable end connector is greater than or equal to 8 feet below the refueling  ;'

j floor level.

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e. Perfoming a load test of 1000 + 50, -0 pounds applied'to the hoist '

cable. )

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SUSQUEHANNA - UNIT 2 V4 F9 j

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, e REFUELING OPERAT!0NS SA$t$ _

3/4.f.6 REFUELING PLATPORM g a- m ,

l The OPERA 81L TY requirements ensure that (1) the ret.nting platfem willg _}

pe used for hand 1{1De control rods and fuel assesklies the wit 11 reacte pres &ure f eessel, (t) each heitst has su ficient 16td capaci for hand 1 ng fuel a emeli%

andcontre(rods,a (3) the re into 1s and p ssure vess 1 are pro ted

, frbs essesafve 11fting orce in event are i ertanti agaged ig

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, lif%ng operanens.

3/4.9.1 CRANE TRAVEL - $pOff FUEL aiviiAGE Fwi.,

The restriction en movement of loads in excess of the nominal weight of a fuel assembly ever other fuel assemblies in the storage, peel ensures that in the event this lead is dropped (1) t's activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistant with the activity release assumed in the safety analyses.

1/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL -$ PENT FUEL-aeviiAGE Fwi.

The restrictions on minimum water level ensure that sufficient water depth is available to remove SSE of the assumed 105 fodine gap activity released from the rupture of an irradiated fuel assembly. This minimum water depth is consistant with the assumptions of the, safety analysis.

3/4.9.10 CONTROL R00 REMOVAL f These specifications ensure that maintenance er repair of control rods or control rod drives will be performed under conditions that limit the probahtlity

ef inadvertent criticality. The requirements for simultaneous removal of more

.than aos control rod are more stringent since the $NUTDOWN MARGIN specification

provides for the core to remain subcritical with only one control rod fully I withdrawn.

3/4.9.11 RE$100AL HEAT REMOVAL AND COOLANT CIRCULATION I The requirement that at least one residual heat removal loop be OPERA 8LE i

or that an alternate method capable of decay heat removal be demonstrated and that l an alternate method of coolant mixing be in operation ensures that (1) sufficient i

cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140*F as required during REFUELING, and (2) suffi-

' cient coolant circulation would be available through the reactor core to assure accurate temperature indication and to distribute and prevent stratification of the peisen in the event it becomes necessary to actuate the staney liquid j

l control systas.

The requirement to have two shutdown cooling mode loops OPERABLE when there

' is less than 22 feet of water above the reactor vessel flange ensures that a l single failure of the operating loop will not result in a complete loss of resta-ual heat removal capability. With the reactor vessel head removed and 22 feet

! ', of water above the reactor vessel flange, a large heat sink is available for

- core cooling. Thus, in the event' a f atture of the operating AMR leep, adquate j time is provided to initiate alternate entnods capable of decay heat removal or j -

emergency procedures to cool the core.

SU$QUENANNA - UNIT 2 3 3/a 9-2

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