Text

Proposed Tech Specs Re TS Upgrade Program Section 3/4.10
	ML20087H865
Person / Time
Site:	Dresden, Quad Cities
Issue date:	05/02/1995
From:	; COMMONWEALTH EDISON CO.
To:	;
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ML17180B180	List: ML20087H865;
References
	NUDOCS 9505050084
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' ATTACHMENT C Marked-Up Current Dresden Unit 2pnd Ound Cities Unit 2 - l Technical SpeciEcatiom j

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9505050084 950502 PDR ADOCK 05000237 i

a. P PDR l

l fORIMORMATlallORY o4=i' . g, f"-"

s . :

3.10 LIMITING CONDITIONS FOR OPERATION '4.10 SURVEILLANCE REQUIREMENTS !

REFUELING REFUELING f Applicability: i (Applicability-fphestofuelhddling A es to the periodi and e reactivity test %of those jnterlocks ;

limita on / and inst (uments sed during j refueling.

Object'ive: t !

Obj ective. . !

To ssure core r ctivity is' To verify the operakilitys !

'/ thin capability b( the of/nstrumentationandT l control rods and to prevent interlocks used in l dticality during refueling. refueling. l Specification: Speci fication: -

[

A. Refueling Interlocks A. Refueling Interlocks l l

The reactor mode switch Prior to any fuel handling, l gut shallbe locked in the ARefuel) position during ry p with the head off the

, reactor vessel, the core alterations and the , refueling interlocks shall ,

t refueling interlocks shall be functionally tested.

I

[fQ<x be operable except as specified in S -

They shall also be tested at weekly intervals l

3.103 and @p_ecifications 0 thereafter until no longer

/ N - required and following any (N t t r1 c B. Core Monitoring [B. Core Monitoring !

During core alterations Prior to making any ,

two SRM's shall_b.e. alterations to the core the ;

pf t pttrablef6ne in the core - SRM's shall be functionally

11 quaFr'aM where' fuel or u p&gg2 L tested and checked for control rods are being uneutron response s moved and one in an ' Thereafter, the SRM's will \

[J adjacent quadrant. For be checked daily for (Tsuh>t)/ IDM to De considered operable, the following response, except when the conditions of 3.10.B.2.a conditions shall be and 3.10.B.2.b are met.

satisfied: t

/ 1. The SRM shall be /

af.lh inserted to the nonnal p h 3/4.10-1

DRESDEN II DPR-19 i Amendment No. 34, 82 !

)

3.10 LIMITING CONDITIONS FOR OPERATION 4.10 SURVEILLANCE REQUIREMENTS !

tcont'd.) (Cont'd.)

ing leved (Use f g $3 7 f~special moveable,

. p @0 ' dunking type detectors 3 f o, d , ,

' $ b" l during initial fuel 72g:/,y 3 loading and major core alterations in place of '

d

nonnal detectors are l permissible as long as ~

i the detector is i connected into the S

RhLcircuit.] p M'

2. The SRM or dunking type f detector shall have a 1 minimum of 3 cps with !

all rods fully inserted in the core except whe -

both of the following ,

conditions are '

(ulfilled: _

a) No more than 5 75 fuel assemblies are present in the core

//N.

/ !

quadrant associated i ith t the SRM.

A gS 0 p ,3, F-b) While in core, 9 Mg2 ,

these fuel assemblies are in locations adjacent '

to the SRM. -- -

C. Fuel Storage Pool Water f C. Fuel Storage Pool Water <

Level Level Whenever irradiated fuel Whenever irradiated fuel is is stored in the fuel stored in the fuel storage storage pool, the pool pool, the pool level shall l water level shall be be recorded dafl'. ,

maintained at a level of j- -

Q3) feet. / l

/ odi Tb", fr 7/p

/ T5 d $*tO A L 3/4.10-2 ,

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f f V DRESDEN II _ DPR-19

[- AmendmentNo.}>[,ps,82 3.10 LIMITING CONDITIONS FOR OPERATION 4.10 SURVEILLANCE' REQUIREMENTS (cont'd.) (cont'd.)

. Control Rod and Codrol D. Control Rod Drive and Control Rod Drive Maintenance Rod Drive Maintenance 9- A maximum ofttk non-adjacent control rods separated by more than two control 7 d 3*N'gg cells in any direction, may be withdrawn from the core for the purpose of performing control rod and/or control rod drive P j c/a> # ,3 maintenance provided the following conditions are atisfied:

[ The $ actor mode

1. This surveillance switch shall be

'g,g locked _in the requirement-is as given in 4.10. A.the sam g) f, hosition, y 7

'5

ro ,

[ [ interlock which

! prevents more than one d

_ / control rod from being tr# jh withdrawn may be 62Je

' ] 'k) 'f s bypassed for one of the p# control rods on which - - - - -

maintenanc 1Atjm perf 11 other. '

e- ling interlocks ,

shall be operable.

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2. Specification 3.3. A.1 # 2. Sufficient control rods shall be met o , e i shall be withdrawn entr51 rod directional prior to performing

, 3,g 1, control valves for a n q- this maintenance to /

L , minimum of ig demonstrate with a

~

control rods margin of 0.25 percent [

surrounding each driv delta k that the core out of service for can be made subcritical

/ maintenance will be at any time during the ytMgg disarmed electrically and sufficient margin i

maintenance with the strongest operable control rod fully (todemonstrated.

criticality '

withdrawn and all other s . - - ~

( Reviseo 'with change 17303R-19 dated 3/17/72 A M vised wlth change 9 to DPR-25 dated 3/17/7

/'

3/4.10-3

FORINFORMAIl0N DEY AmendmentNo,y/,82 3.10 LIMITING CONDITIONS FOR OPERATION 4.10 SURVEILLANCE REQUIREMENTS (Gont'd.) (Cont'd.)

perable rods fully I

3j ## insert N.hern ely, minimum ofje

> control rods / p t

_ surrounding each

' ~' control rod out of b service for maintenance M

are to be fullyinsertedandhav directional cor. trol

-r%'p/

Yy valves electrically disarmed, the 0.25 I percent delta k margin '

will be met with the ygoS' strongest enntrol rod

(

[ f56). - remaining in service

( during the maintenance Qeriod fully withdrawn

3. SRM's shall be operable 3. This surveillance (a) in each core requirement is the same quadrant containing as that given in a control rod on which 10.B.

maintenance is being performed, and (b) in a t quadrant adjacent to f

one of the quadrants {ryg 4, fos.Z.

s)ecified in 3.10.D.3.a a)ove. Requirements for an SRM to be considered operable are iven in 3_in n -

g x

. Extended Core Maintenance E. Extended Core Maintenance More than two control rods may be withdrawn from the reactor core provided the

/ -

following conditions are 3 ,

satisfied: -

e

1. The reactor mode . This surveillance switch shall be requirement is the same locked in the as that given in 4.10,A.

3/4.10-4 1

DRESDEN II DPR-19 Amendment No. }8, ?/2, 82 j I

3.10 LIMITING CONDITIONS F0F OPERATION 4.10 SURVEILLANCE R'EQUIREMENTS i (Lont'd.) -l cont'd.) ;

ition. The !

refueite.g interlock

[ which prevents more than one control rod

'r from being withdrawn p 48 y' /g f ,

f may be bypassed on a withdrawn control rod QA & E U ,

after the fuel '

assemblies in the cell containing (controlled !

by) that control rod '

have been removed from bo 'i/, S the reactor core. All b/

other re-fueling .p interlocks shall be f5W grable. 9, fo.f, L

d. SRM's shall be operable . This surveillance in the core quadrant requirement is the same '

where fuel or control as that given in ;l rods are being moved 4.10.B. I and in an adjacent l quadrant. The ;

requirements for an SRM l to be considered i operable are' given in i b _

Spent Fuel Cask Handling F. Spent Fuel Cask Handling F.

1. Fuel cask handling 1. Prior to fuel cask above the 545' handling operations, elevation will be the redundant crane done with the reactor including the rope,

^ building crane in the hooks, slings, shackles; RESTRICTED MODE only and other operating /

I)s o'p /except as specified i,

' mechanisms will be /

i

- - V inspected.

Q.10.F. 2.

t The rope will be replaced if any of th following conditions exist:

Y[ 4l0-1

. I 3/4.10-5 9

DRESDEN II DPR-19 Amendment No. 120 3.10 LIMITING CONDITIONS FOR OPERATION 4.10 SURVEILLANCE REQUIREMENTS (Cont'd.

(Cont'd.)

a. Twelve (12) randomly distributed broken '

wires in one lay or four (4) broken wires l in one strand of one ;

rope lay. l

b. Wear of one-third the original diameter of g, - )# outside individual

< wire. ,

c. Kinking, crushing, or any other damage resulting in distor-tion of the rope.

d. Evidence of any type !

of heat damage.

e. Reductions from nominal l gg diameter of more than :

' 1/16 inch for a rope 2 diameter from 7/8" to 1 1/4" inclusive.

r 3 !

2. Fuel cask handlin in 2. Prior to operation !

ther than the in t RESTRICTED DE R TRICTED MODE ill bejermitted a. the ntro,1 ed area emergencyorequipment limit w'tches will failu s uations be tes d:

only to e extent \

neces to get the b. th 'two-D ock" I cask th closest 1 it switc s will acc table s able e tested; lo6ation.

\ i gt'Q 06L YfJ 3/4.10-6

FOR INFORMAIl0N DEY DRESDEN II DPR-19 Amendment No.120 3.10 LIMITING CONDITIONS FOR OPERATION 4.10 SURVEILLANCE REQUIREMENTS ['

(Cont'd.) (Cont'd.)

E ist"

3. Operation with a failed 3. The empty spent fuel controlled area limit cask will be lifted switch is permissible free of all support by for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months providing a maximum of 1 foot and an operator is on the left hanging for 5 :

refueling floor to assure minutes prior to any !

the crane is operated series of fuel cask I within the restricted handling operations.

zone painted on the floor.

i p 3do 9, g af 9 ig > .F3 .

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3/4.10-7 l

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6 FORINFORMAIl0N ONLY !

DRESDEN II DPR-19 !

Amendment No. 82, 91, 104 ;

3.10 LIMITING CONDITIONS FOR OPERATION 4.10 SURVEILLANCE REQUIREMENTS (Cont'd.) (Cont'd.) !

Fuel Storage Reactivity Limit3 i G. Fuel Storage Reactivity Limit G.

l

1. The new fuel storage fa- 1. Prior to storing Fuel in /

cility shall be such that the new fuel storage facilf ,

the K dry is less -than ity, an analysis must be i 0.90Ifdlfloodedisless perfomed to demonstrate !

than 0.95. that the criteria in f 3.10.G.1 are satisfied, f {

2. Whenever a fuel assembly is 2. Prior to storing Fuel in !

stored in the spent fuel the spent fuel storage k storage pool, the peak pool, an analysis must be 1

assembly reactivity in a performed to demonstrate reactor lattice distri- that the criteria in bution shall be limited to .10.G.2 are satisfied. I less than or equal to the !

following values:

Assembly Type K inf GE 7x7 1.26 (11o VC0 i GE 8x8 1.32 W ?> M l' ANF 8x8 1.33 gb 6.0 ANF 9x9 1.27

( _

Whenever storing other assembly types or fuel rods in the spent fuel storage pool, their peak reactivity shall be bounded by the most limiting K inf V"I"'

listed _abg r .

f.

H. " Loads Over Spent Fuel Storage Pool -

No weightchds heavier tha3 thi TF le' spent fuel assemb] andling ( j tool sha ( be carr led over fuel'istored in the speh- <

fuel storage pool.

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3/4.10-8

)

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>T . t ATTACHMENT D !

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Marked-Up Draft Revision 4 of the BWR/4 Standard Technical Specifications I i

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QUAD-CITIES FORINFORMAll03 DNLY :

3.10/4.10 REFUELING LIMITING CONDITIONS FOR OPERATION SURVEll.l.ANCE REQUIREMENTS

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Applicability: 3 Applicability: 3 i Applies t uel handling and core tivity Applies to eriodic testin those interlocks ,

limitations. and instruments us 'n efueling ;

Objecthe: Objecth e-To assure core reacij ' y is within ca hijity of the To verify t. operability of in$trumentation and ;

control rods and to prevent criticality during interlockdsed in refueling. y

[ _

( ,

SPECIFICATIONS r

'gt P 3- to .h

... s A. Refueling Interlocks N A. Refueling Interlocks )

The reactor mode switch shall be locked in Prior to any fuel handling with the head off the {'

Refuer sition during core alterations. and the reactor vessel the refueling interlocks shall be I

re ueling iriterlocks listed below shall be opera- functionally tested. They shall also he tested at i y[3 ,.- ble except as specified in SpecificationsWD' weekly intervals thereafter until no longer re-and! @ quired and following any repair work awoci- 3

f. Contr'o'1 Rod B ocks 3ac I ated with the interlocks.

]

f 'f a. Mode switch in CFartup/l]A' M ,

gJ Standby and refueling platform gg T3 la4,,oJ 3' -

h. Fuel on any refueling hoist anF 4.jg refueling platform over the eactor.

_y- ]gf> 3,lo, A8 C

'l- c. Mode switch in elil4 with one J.h, d N

.y~ t .I control rod with rHFa1 permit. pp 3, TRefueling Platforrir ReWr~se Mown i g_y[ <[/4/j , s, (toward reactor vessel) Block - --

( /,vf u & (c)

a. Mode switch iniartup/iIoK )

. Standby. g Lt[> S ,/0 ,A 7-. O

b. con p W "

_ny refueling hoist. 3 .tv i Rhu$ ling Platform Hoist BWK _

a. Any control rod out and fuel on . T48 3 #

. any refueling hoist over the P'.

vessel.

V 3.10/4.10-1

~

F0HNFORMATIO10NI.Y QUAD CTTIES r_ ~,d 3' g?'cf' I b. Hoist overlo+d.

m DPR-30 3 op 3s'p '

' 'l.& ' ' f( 0.0 2- /

a

, Q High pos. .ition h.mitation.

3. Core Monitoring L re Manienring A

During core alterations. two SRM's shalL Prior to any alterations to the core, the SRM's shall be functionally tested and checked for )

\

puabig/oTeTIthe coreDfi6T'i' ere h fuel or control rods are beine moved and one in a1L) peutron3riponsefTheresfier. the SRM's shall F

' adjacent quadrany FWan SRM to be consid. be checked daily for response, except f

'y ired operable the fo!!owing conditions shall be when the Conditions of 3.10.B.2.a

MP satisfied:

kard 3.10.S.2.b are m/et.

1. The SRM shall be inserted to the nor-

/ mal operating levell(use of special

,,__s ~ Uunkir.g type detectors dur.

bl TsnP 4m, A, ggf,g[)3 ing initial fuelloading and major core alm-*tions in place of normal detec. (

4/tt" tots is permissib'c as long as the detec. j p ter is connected into the proper circui. -Q

- try which contains the requiredg g / //, /c ,/3 3 )

TV H ,' bloenst

-::= - /

J f,[ kap

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~

4

[2. The STNofor sinimsn dunking 3 eps with alltype detecter ter's fully shall have a N) incerted in the core exetpt when both of t.a.e --

( conditions are fulfilledsj"'follonng - _7

~

g 9, g f,

/aF~na sore thinWf217 sse .fG N 7 present in the core cpadrant asscciated ) 4,/ f/

g J. g 17 J

% 'j with the W1 _.

_C 4 g

' f

. (( $ g {a 'gp' fu

' p // l

- ~ - - - -

,bF NhiliIn_ core, these fuel aswtlies are

. __in locations Mjeeent to trie 5% g4j 'g'9/'2

~

,-~~3, C Fuel Storage Pool WEer Leelt [C Fuel Storage Poo1 Water Leel '%

Whencycr irradia:cd fuel is stored in the fue Whenever irradisted fuel is stored in the fuel M storage pool, the pool water level shall be / storage pool, the pool level shall be recorded ,/

ined at a level of at leasti33; feet.j D <D 'Contror R5T and

( ~.DControl Rod and Control Drive Maintenance Control. Rod Drive 4;[e 4 si

, A maximum ofgo nonadjacent control rod separated by more than two control cells an any

\ \

"I""*"

L.___

J bg 3 \

direction the purpose ofmay be withdrawn performing control rod and/or from the core \ for -).

p-7 , - control rod drive maintenance 7WQ$) foDowins conditions are satisfied: _' provided the,s [Q@

C,,

4 yy \

1' ' m be,

_ .- 1. The reactor mode switch shall I . Sumcient control rods shall be with-locked _in the Refuel position.Rhe re-

~ f drawn prior to performing this main.

-4

- Pfveling'iritericDEicff[revents more f tenance to demonstrate with a margir.

T*' 7 than one control rod from being with. l of 0.25% Ak that the core can be made

($M,'M"U drawn may be bypassed for one of the suberitical at any time during the ,-

'~

control rods on which, maintenance isq.

maintenance with the strongest opera- s' 4 g g t}'-q g p w being_ performed)All other refueling y ble controt rod fully withdrawn and I W)

-f{f' interlocinh7ill be operabic.p- Nother operable rods fully anygted.

g / f 2.~5peelficsTioI3.3411shali_be mDrj r'((s) IderniieTy3a minimum o('ei~gE) control rods surroundine each edntrol fthe control rod directional enntrol 'La-e,,

< N _T3k j cight diiiroIl ---> #

{ rod out of service for ma$ntenance are CN ^-

/ valves for a minimum sods surrounding each service for rnainiccance will be dis-o[drivI out ',oof\, '{ lo be fully inserted and h.ive their 5M directional controi valves electrically

/, ---g4 u IA 3 . armed electrica!!y and sumcient mar- # disarmed, the 0.25% M margin will W

w 7-Amendment No. 53 3,10/4e10-2

L A # FORINFORMAIl0N ONLY QUAD-CITIES D

@ j L(,ID I - j r'- Th#

hn to criticality d i be met with the strongest control rod Mhperdie (a) in e remaining in service during the main-tenance period fully withdrawn.

core quadrant containing a control rod on which maintenance is being per- j formed, and (b) in a quadrant adja- ( ;

cent to one of the quadrants specified s *

$ )y '*4 , ", 7in Specification 3.10.D.3.(a) above 10 g ' } , c, /

'bb ' o . 4 . - Requirements for an SRM to be con p4 /,/

sidered operable are given in Specifi -

on 3.10.B.

E. Eatended Core Maintenance N E. Extended Core Maintenance More than two control rods may be withdrawn , Prior to control rod withdrawal for extended core from the reactor core provided the following maintenance, that control rod's control cell shall conditions are satisfied: be certified to contain no fuel assemblies.

1. The reactor mode switch shall be locked in the, Refuel position. The re-F SpGbMT- .N qi , ,; Meling interlock wh,ich prevents more 1. Prior to fuel cask handling operations, } 1 j r e/ than one control rod from being with- the redundant crane including the rope, t

, y drawn may be bypassed on a with- hooks, slings, shackles and other opera-O' drawn control rod after the fuel assem- ting mechanisms will be inspected. i blies in the cell containing (controlled by) that control rod have been re- The rope will be replaced if any of the following conditions exist:

I moved from the reactor core. All other) refueling interlocks shall be ooerable. a. Twelve (12) randomly distributed ;

T-~5RMTilillibe operable in the ' "" * * "" "Y ' "'

broken wires in one strand of rope quadrant where fuel or control rods I / 5., y are being moved and in an adjacent 3# quadrant. The requirements for an b. Wear of one third the original dia-SRM to be considered operable are meter or outside individual wire.

i given in Specification 3.10.B.

c. Kinking, crushing, or any other Spent Fume E* * "" 8 "

F. .

f ,

l. Fuel cask handling above the 623' level of the Reactor Building will be done with the reactor building crane in the RESTRICTED _ MODE only; Eicept as ,.____c _ j specifle i p*

Nel'~isisk'liiindling in other than,theb > I6 j 1

RCSTR,1CTED MODE will,be permitted j in emergetrey r squipment failure situa- .

f-tionjs o *y-t e ex cessary to get !

jhe" cask to the closest accepta le stable location. (ggB / !

3.10/4.10-3 Amendment 35 2/26/77

. 3 p g P Mild

DPR-30 ,

i

3. Operation with a failed controlled area- d. Evidence of any type of heat damage.)-

limit switch is permissible for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

e. Reductions from nominal diameter of !' i providing an operator is on the refueling floor to assure the crane is operated with.

- more than 1/16 inch for a rope dia-in the restricted zone painted on the meter from 7/8" to 11/4" inclusive ,

, in the RESTPJCT MODE j

a. the contro ' area l' it switches will be tested; l

. g jp,p j ;

I t b. the "two blo be tested; li switches will .

.l

, c the ching hoist" controls ' I b-

d. ._

(

i b empty spent fuel cask will be lifted free of all support by a maximum of 1 .

foot and left hanging for 5 minutes prior i to any series of fuel cask handling operations. ;

)

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l 3.10/4.10-3a Amendment 35 2/26/77 - ,

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ATTACHMENT D 1

i Marked-Un Draft Revision 4 of the BWR/4 Standard Technical Specifications l l

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3/4.f FUELING OPERATIONS -

REACTOR MODE SWITCH. ,

LIMITING CONDITION FOR OPERATION n

0 -

3 Re The reactor mode switch shall be OPERABLE and locked in the Shutdown'or position. When the reactor mode switch is locked'in the Refuel position:

h -(j [ A control rod shall not be withdrawn unless the Refuel position one-rod-out Mterlock is OPERABLE.

gM CORE ALTERATIONS shall not be performed using equipment associated with a Refuel position interlock unless at least the following associ-ated Refuel. position interlocks are OPERA 8LE for such equipment.

1 All rods in. '

Refuel platform position.

. L "(2[.'6 Refuel

-d., platform hoists fuel-loaded.

d~4. Fuel grapple position. -

Q 5eWrce platform hoist fueT-loaded -

APPLICABILITY: OPERATIONAL CONDITION-5 [

ACTION:

p(af With the reactor mode switch not locked in the Shutdown or Refuel position as specified, suspend CORE ALTERATIONS and lock the reactor mode switch in the Shutdown or Refuel position. ~

gg(6~. With the one rod-out interlock inoperable, lock the reactor mode switch

, in the Shutdown position.

J With any of the above required Refuel position equipment interlocks b'3M c. inoperable, suspend CORE ALTERATIONS with equipment associated with the inoperable Refuel position equipment interlock.

e- hhV 00 ,

l (O

See Special Test Exceptions 3.10.J1 and 3. _0g La d'The reactor shall be maintained in OPERATIONAL COND N b 5 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully '

tensioned or with the head removed.

sum O

e as GE-STS (BWR/4) 3/4 9-1 4

6

c REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS 4'D[The reactor mode switch shall be verified to be locked in the Shutdown or Refuel position as specified: ,

a, Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to:

1. Beginning CORE ALTERATIONS, and

2. Resuming CORE ALTERATIONS when the reactor acde switch has been unlocked.

b. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c/

4 17 8' Each of the above required reactor mode switch Refuel position interlock 6 shall be demonstrated OPERABLE by performance of a CHANNEL JUNCIlqNACTEST within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the start of and at least once per g, 7 days during control rod withdrawal or CORE ALTERATIONS, as applicable.

,. y- $ d Each f the above required reactor mode switch Refuel position interjo_qksf that is affected shall be demonstrated OPERABLE by performance of a gJ F~ [CflANNEL FONCTIONAL TEST prior to resuming control rod withdrawal

@ ALTERATIONS, as applicable, following repair, maintenance or replacement of any component that could affect the Refuel position interlock.

.4 M The reactor mode switch may be placed in the Run or Startup/ Hot Standby position to test the switch interlock functions provided that all control rods are verified to remain fully inserted by a second licensed o other technically qualified (liiembeFof the unit techMRW_f(perator o ,

7 60 P

G e

W GE-STS (BWR/4) ,

3/4 9-2

t l

REFUELING OPERATIONS .

3/4T2bSTRUMENTAT!0N I LIMITING' CONDITION FOR OPERATION :

3..[Atleast2sourcerangesonto and inserted to the normal operating level (SRM)channelsshallbeOP[ERABLE-with:

@ca Continuous visual indication in the control room, b.

Atleastonewithaudibleindicationinthecontrolroomandonthe]

refueling floor, i j

g g c I One of the required SRM detectors located in the quadrant where CORE ALTERATIONS are being performed and the other required SRM detector located in an adjacent quadrant, and ;

l d.

The " shorting links" removed from the RPS cigcuitry prior to and during the time any control rod is withdrawn and shutdown margin' demonstrations are in progress.

poOC f

gg,P l APPLICABILITY: OPERATIONAL CONHWON gN adu

/- l'g,y

5) V!fJ . J g /AA ,yAAwf,)

g,,.4G,, w s M '""*"" ' l

" " **; n 4 c" [g 2 3 3.12 yfg & & L W A2 % Gh With the requirements of the above specificat on2 notasatisfie i M tely " d suspend all operations involving CORE ALTERATIONS *Cand insert all insertable control rods.

SURVEILLANCE REQUIREMENTS

\P

4. { 6 Each of the above required SRM channels shall be demonstrated OPERABLE by:

a. At least once per 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s:

1. Performance of a CHANNEL CHECK,

2. Verifying the detectors are inserted to the normal operating level, and

3. During CORE ALTERATIONS, verifying that the detector of an OPERABLE SRM channel is located in the core quadrant where CORE ALTERATIONS are being performed and another is located in an adjacent quadrant.

p }

- ($ FThe use of ypecial,inovable detectors during CORE ALTERATIONS in place of the normal SRM auglear detectors is permissible as long as these special detectors :

are connected to the normal SRM circuits. e

(~asExcept movement of IRM,-"SRM or PletT4T3iiNahle-detectorsr)j?

_ -/ ,

(0 NItrequiredforcontrolrodsremovedperSpecification3.'9 d Q1

~

GE-STS (SWR /4) 3/4 9-3 t> ,. _ l W

~ '

w, - - , - v--- n---

~

REFUELING' OPERATIONS SURVEILLANCE REQUIREMENTS (Continued)

[ Performance of a CHANNEL FUNCTIONAL TEST: ;

{ay >(7 Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the start of CORE ALTERATJONS, and !

p [ At least once per 7 days. '

c[.Verifyingthatthechannelcountrateisatleast3 cps- >

fj Prior to control rod withdrawal, ,

-A i j (2. Prior to and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during CORE ALTERATIONS, and .

3. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .'

h' ~&[d[y Verifying, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during, that the RPS circuitry " shorting links" have been removed during:

g ,

@ N The time any control. rod is withdrawn, orf)

[ ~ Shutdown margin demonstrat M 3,3.A d k ~' d' d

, a Lw L pLJo& k Lu Anenid' :

c(A P p<S. S.k1. A ,

i l

i i

I w c .

lb ONot required for control rods removed per Specification 3.9.10.1 or 3.9.10.27 GE-STS (BWR/4) 3/4 9-4 I

.e . . ., . . \

. .: Sc.=. / ' ~7/ .

..n: /- 4 .,ru. .;..,= .i32.

l i

w M-A REFUELING ~0PERATIONS- i 3/4M7bNTROL ROD POSITION _

f :

LIMITING CONDITION FOR OPERATION j i

.c M oh

~

r 3.$.y All_ control rods shall be inserted $ @

y j APPLICABILITY: OPERATIONALCONDHiON5,duringCOREALTERATIONSb*4ql,) l (1fc 0C i ACTION: !

(di With all control rods notjinserted, suspend all other CORE ALTERATIONS, except that one control rod may be withdrawn under control of the. reactor mode switch i Refuel position one-rod-out interlock. ~

I SURVEILLANCE REQUIREMENTS j to s ..Q gg j

4. 3) All control rods shall be verified ot' be, ins (erted, except as"4 specified:

gW l

% Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to:

(pfb The start of CORE ALTERATIONS. I J

gL2. The withdrawal of one control rod under the control of the reactor mode switch Refuel position one rod-out interlock.

,~,..>-

gQ b.> At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

G t a,T)

- Lah M Qcept control rods removed per Specification'3.lt (W A*See Special Test Exception 3. 0~3?

Q2T.# l I

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or m ciuQ uY h GE-STS(BWR/4) 3/4 9-5 amA.,

a c<5'N@ >y, LAuS l nud eghn cut .44 ktuM.

REFUELING OPERATIONS

,.- y :

3/4/9.4) DECAY TIME !

[

LIMITING CONDITION FOR OPERATION >

I h The. reactor shall be suberitical for at least4) hours.

mood APPLICABILITY: OPERATIONAL CONDtT19N 5, during movement of irradiated fuel in the reactor pressure vessel. ,

i ACTION:

a> l With the reactor subtritical for less thant(24) hours, suspend all-operations involving movement of irradiated fuel in the reactor pressure vessel. '

[

l l

SURVEILLANCE REQUIR MENTS I

hJ 4.S. ,

' 2')J' 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months sThe by reactor shall verification bedate of the determined and time of to have been suberiticality priorsuberitical to fo movement of irradiated fuel in the reactor pressure vessel.

]

O .

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am e

GE-STS(BWR/4) 3/4 9-6

l t

~

4-REFUELING OPERATION 5' i 5 OMMUNICATIONS i

LIMITING CONDITION FOR OPERATION !

r -

3 Direct communicatio all be maintained between the control room and ref ling ((platfo .

personnel. !

x ,.,u c &.,

APPLICABILITY: OPERATIONAL.COND E 9N 5, during CORE ALTERATIONS.O )

ACTION: l Whea di ect communication between the control room and refueli tford) eor)ipersonnel cannot be maintained, immediately suspend COR!(ALTERATIO i

l

)

1 I

J SURVEILLANCE REQUIREMENTS I s .

e c Direct communication between the control room and refueling dplatform)p ilnor)' personnel shall be demonstrated within one hour andatleastonceper12hoursduringCOREALTERATIONS.griortothestartof s ,

J _Y L"Except movement of incore Estrumentation an) control rods with their

-normal drive system.

W W

G e

e j t GE-STS (BWR/4) 3/4 9-7 ,

l l

l I

, _ _ .~ _ . , - . . . - - -

]

/ l L

REFUELING OPERATIONS 334.9.6 REFUELING PLATFORM pA h F RINFON Tig# ONLY:

l l

1IM\IJNGCONDITIONFOROPERATION y l

N 3.9.6 T refueling platform shall be OPERABLE and sed for handling fuel i

assemblies or control rods within the reactor pre ure vessel. -

APPLICABILI .: During handling of fuel assemb ies or control rods within the i reactor press re vessel.

ACTION:

With the require ts for refueling p1 form OPERABILITY not satisfied, suspend- !

use of any inopitra {e refueling platf equipeent from operatir,ris involving :

the handling of cont ol rods and f assemblies within the reactor pressure l vessel after placing he load in a afe condition. !

I SURVEILLANCE REQUIREMENT 5 l s ,

4.9.6 Each refueling plat crane or hoist used for handling of control rods or fuel assemblies within he reactor pressure vessel shall be demonstrated 3 OPERABLE within 7 days p or t the start of such operations with that crane '

or hoist by: ;

i

a. Demonstrat g operation of the overload cutoff on the main hoist when i the load coeds (1200 1 50) pounds,

b. Demonst ating operation o the overload cutoff on the frame mounted )

and so rail hoists when t load exceeds (500 t 50) pounds.

c. D strating operation of uptravel mechanical stop on the frame i moynted and monorail hoists uptravel brings the top of (active) )

fuel assembly to (8) feet below he (normal fuel storage pool) water

. 'evel.

1

d. Demonstrating operation of the down avel mechanical cutoff on the 1 main hoist when grapple hook down tra el reaches (4) inches below i fuel assembly handle. .

~

e. Demonstrating operation of the slack cab cutoff on the main hoist I when the load is less than (50 1 10) pou .

~

f. Demonstrating operation of the loaded interi k on the main hoist when the load exceeds (485 1 50) pounds. .

g. Demonstrating operation of the redundant loaded Interlock on the mairr hoist when the load exceeds (550 1 50) pounds. \

GE-STS(8WR/4) 3/4 9-8

1 j

r .; 1 REFUELING OPERATIONS-F RINFORMAIl0N ONil 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE POOL

)

LIMITING CONDITION FOR OPERATION .

I 3.9.7 Load d from travel over fuelassemblie\s.excessof(1100)poundsshallbeprohi n the spent fuel storage pool racks /.

t uel storage pool racks.

APPLICABILITY:-

ACTION:

Wi h fuel assemblies in the s9p ;

l With the requirements of the a load in a safe condition. The prbi ions of Specification 3.0.3 are notspecif catio !

t applicable. '

i f

SURVEILLANCE REQUIREMENTS 4.9.7 Cranelocks inter /

and physical stops which prevent crane travel with loads l in' excess of (1100) pounds over fuel assemblies in the spent fuel storage pool :

racks shall be demonstrated OPERABLE within 7 days prior to and at least once !

per 7 days during crane operation. I

w a 3> p.3g 3

)

J ao aus l

' ~

GE-STS(BWR/4) 3/4 9-9 ,

~. .. .. .. .- -- --

REFUELING OPERATIONS-h 3/ .s9. 8) WATER LEVEL - REACT 0k VESSEL LIMITING CONDITION FOR OPERATION

- ,2 e e

p .G T g- y !

3.{ J At least 23J feet of water shall be maintained over the top of the reactor pressure vessel flange. g -

APPLICABILITY: Duringhandlingoffuelassemblies/orcontrolrodswithinthe reactor pressure vessel while in OPERATIONAL CONDfFION 5 when the fuel assemblies being handled are irradiated or the fuel assembliesr seated within the reactor vessel are irradiated. T i er <c4ce() er n ,

""E ACTION: CM :

evds ;

With the requirements of the above Specification not satisfied, suspend all ,

operations involving handling of fuel assemblies or control rods within the :'

reactor pressure vessel after placing all fuel assemblies and control rods in a safe condition. ,

i l

l SURVEILLANCE REQUIREMENTS

- . .r 935 he reactor vessel water level shall be determined to be at least its mirilmum required depth within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to the start of and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during handling of fuel assemblies or control rods within the reactor pressure vessel.

l l

l 9

9 9

e e

so GE-STS (BWR/4) 3/4 9-10

i REFUELING OPERATIONS 1

3/4. . WATER LEVEL - SPENT FUEL STORAGE POOL LIMITING CONDITION FOR OPERATION TF 35S J At least 23)ffeet of water shall be maintained over the top of irradiated fuel assemblies seated in the spent fuel storage pool racks.

APPLICABILITY: Whenever irradiated fuel assemblies are in the spent fuel storage l

pool. .

ACTION:

With the requirements of the above specification not satisfied, suspend all movement of fuel assemblies and crane operations with loads in the spent fuel storage pool area after placing the fuel assembl{es and crane load in a safe condition. The provisions of Specification 3.0.@j e not applicable.

p SURVEILLANCE REQUIREMENTS t

toi .. a 4 SJP The water level in the spent fuel storage pool shall be determined to be at least at its minimum required depth at least once per 7 days.

e G

S S

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/ GE-STS (BWR/4) 3/4 9-11

REFUELING OPERATIONS j

.]9D[CONTROLRODREMOVAL SINGLE' CONTROL ROD REMOVAL l

i LIMITING CONDITION FOR OPERATION .

M One control rod and/or the associated control rod drive mechanism 1 may be removed from the core and/or reactor pressure vessel provided that at '

least the following requirements are satisfied until a control rod and associ-ated conten1 red drive mechanism are reinstalled and the control rod is fully, inserted in the core.

y Q The reactor mode switch is OPERABLE nd Tbcked in the Shutdown posit' ion h" _, s. or in the Refuel position per Table .23and Specification The source range monitors (SRM) are OPERABLE petSpecification9

?@2 The SHUTDOWN MARGIN requirements of Specification QLb , Wio. cD '

.1 J are satisfied, f(c. except that the control rod selected to be removed; eg([L May be assumed to be the highest worth control rod required to V be assumed to be fully withdrawn by the SHUTDOWN MARGIN test, '

and Mi Neednotbeassumedtogeimmovableor 7

[Qd

( /

All other control rodskn fbe-by-five array centered on the contrdi rod being removed are a inserted and electrically or hydraulically ,

disarmed or the four fuel assemblies surrounding the control rod or ;

control rod drive mechanism to be removed from the core and/or reactor vessel are removed from the core cell, i o

CIh(d g All other control rods are inserted.

A.we5 APPLICABILITY: OPERATIONAL-40 NOM 40NG 4 and 5.

ACTION: -

e.

With the requirements of the above specification not satisfied, suspend removal ;

of the control rod and/or associated control rod drive mechanism from the core and/or reactor pressure vessel and initiate actiontto satisfy the above requirements. 1 e.

, en GE-STS (BWR/4) 3/4 9-12 i

I I

g-._ , - . - - . . ..---r-.- L -

REFUELTNG OPERATIONS SURVEILLANCE REQUIREMENTS 10 3 m -

4 9.10 - Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to the start of removal of a control rod and/or the associated control rod drive mechanism from the. core and/or rbactor pressure vessel and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter until a control rod and associ-ated control rod drive mechanism are reinstalled and the control rod is i rted in the core, verify _that: -

/

h [ The ea to modeMtch is OPERABLE par surveillance Requiremen or W 9112 M f applicable, and locked in the Shutdown position or n

~1TIf the Refuel position with the "one rod out" Refuel position interlock OPERABLE per Specificationt @ Q ( f 76 B ,

j,4 The SRM channels are OPERABLE per Soectfication . . _ = )

MF The SHUTDOWN MARGIN requirements of Specification GJ N

are satisfied O# per Specificatiu #]l"~10 1 g c ' j C h o I 33

, d. All other control rod g a five-by-Tive array centered on the control rod being removed are ilerted and electrically or hydraulically disarmed or the four fuel assemblies surmunding the control rod or control rod drive mechanism to be removed from the core and/or reactor vessel are removed from the core cell.

g (p.,L All other control rods are inferted.

O O

e e

a w

GE-STS (8WR/4) 3/4 9-13

~ e - ~ - -- . c ---_.__-_a

REFUELING OPERATf0NS MULTIPLE CONTROL ROD REMOVAL LIMITING CONDITION FOR OPERATION

~,

h,'Tm- ,

3.Q.10 Any number of control rods and/or control rod drive mechanisms may be rem)oved from the core and/or reactor pressure vessel provided that at leas the followfng requirements are satisfied until all control rods and :ontrol rod drive mechanisms are reinstalled and all control rods are inserted in the core.

b' g The reactor mode switch is OPERABLE and lockede or in the Refuel position per SpecificationC.97 ;"except that the utdown position Refuel position "one-rod-out" interlock may be bypassed, as required, for those control rorts and/or control rod drive mechanisms to be removed, after the fuel assemblies have been removed as' specified beiow.

,, ,,g f[bi The source range monitors (SRM) are OPERABLE per SpecificationtFg"-~

I g",(p g I The SHUTDOWN MARGIN requirements of Specification p are satisfied.

SJA

( "~j.' All other control rods are either erted or have the surrounding four fuel assemblies removed from the core cell.

(pM. The four fuel assemblies surrounding each control rod or control rod !

drive mechanism to be removed from the core and/or reactor vessel are removed from the core cell.

l APPLICABILITY: OPERATIONAL EONDIT M N 5.

,vvog ACTION:

With the requirements of the above specification not satisfied,-suspend removal of control rods and/or control rod drive mechanisms from the core and/or reactor pressure vessel and initiate act4erkto satisfy the above requirements.

X

)

E e

SW d-GE-STS(BWR/4) 3/4 9-14

REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS 0) 4.fM Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to the start of removal of control rods and/or control rod drive mechanisms from the core and/or reactor pressurie vessel and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter until all control rods and control rod ;

drive mechanisms are reinstalled and all control rods are inserted in the core, verify that: -

hfg qqg ;

a. Theheactor mode switch is OPERABLE per Surveillance Requirementh;1s' 01' (.9.1.2f is applicable, and locked in the Shutdown position or in the Refuel position per SpecificationO;1Q]g7 x -

b. The SRM channels are OPERABLE per SpecificationtE97Ldp c.

QMN The SHUTDOWN MARGIN requirements of SpecificationG;TXa.re satisfied. '

d.

64 All other control rods are eithereinserted or have the surrounding '

four fuel assemblies removed from the core cell.

e. The four fuel assemblies surrounding each control rod and/or control rod drive mechanism to be removed from the core and/or reactor vessel are removed from the core cell.

Uy, {4 ,

n .~

49 0.2.2' Following replacement of all control rods and/or control rod drive mecha ses removed in accordance with this specification, perform a functional test of the "one-rod-out" Refuel position interlock, if this function had been bypassed.

_ /9 . W l ., 8 d _ S - A ,. ,. , . n d . . a

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m GE-STS (BWR/4) 3/4 9-15 I i

1 l

t (onsow owgi 7 REFUELING OPERATIONS Lrbow v c m F )

3Obh5100AMAT REMOVAP AND COOLANT CIRCULATION FORINFORMATION ONLY !

LIMITING CONDITION FOR OPERATION . !

, pC @bC) p-31 .11 n Cfithe_residuaLheal_temop

> 3{RHR sys em$ least shall one shutdown be OPERABLE s cooling ith and in operation p df at 100 least:

sac (T A [ One OPERABLE , _ .and b . oc)

C5 Hb~., One OPERABLE eat exchanger.

,wo r i

APPLICABILITY: OPERATIONAL CONBITION 5, when irradiated /fuelHs in the reactor i vessel and the water level is greater than or equal to({237 feet .above the top .

of the reactor pressure vessel flange.

ACTION:

soc.

@Hl h With no RBitshlttdowrtsoolinnai5d4 loop OPERABLE, within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, demonstrate the operability of at least one alternate method capable of decay heat removal. Otherwise, suspend all operations involving an increase in the reactor decay heat load and establish SECONDARY CONTAINMENT INTEGRITY within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Y soc (IM7 With no RHR3hutdown cocMng'aodd loop in operation, within one hour 4 establish reactor coolant circulation by an alternate methodgsonitor reactor coolant temperature at least once per hour .

y, a M LLJ Grevu.

SURVEILLANCE REQUIREMENTS " !2 w, ,-

4}S 11 tat least one buTd5dfccol_ing mode loo 16LthDaiidHaLheatlemoyaf-j Aysteror alternatEiieth5d'shall be verified to be in operation and circulating reactor co6 Tant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Y k 'The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per B-hour period.

O em GE-STS(BWR/4) 3/4 9-16 6

-w- c- -- , -_.

u rpc$U Coc L56 9% coct.h T CTVLu REFUELING OPERATIONS 9g~gg \

LOW WATER LEVEL h lf!h h h l h h h I C/MLY 1.IMITING CONDITION FOR OPERATION

~

Two shutdown coolin e ops if the_ residual heaLtenova _(JteRP "pcsP]itim~shall be OPERABLE and at least one loop shall be in operation c with each loop consisting of at least:

a. One OPERABL pump, and i b. One OPERABLEYheat exchanger.

i

' nocc APPLICABILITY: OPERATIONAL-CONDITION 5, dhe vesseI and the water level is less than feetd23)yTrradiated above the top of thefuel is in the re reactor pressure vessel flange.

ACTION:

M [ With less than the above required ~-down iin fmede?loopsdErthE Mild

! tsysten OPERABLE, within gne hour,apd at least siice~pe7 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months there-after demonstrate the, ope'raMiity of at least one alternate method ab e o decay he val for each inoperable (R_RRJIihtdoien rec 7

. - b

b. With no RHR shutdown co61in~si6di' loop in operation, within one hour i

(~9 establish reiftor cooliiit~t Fcdlation by an alternate method and monitor i

reactor coolant temperature at least once m per hou a itng d(tet.su

%g'Cygg l

SURVEILLANCE REQUIREMENTS k# ""

@,7

~ Q sd (

4.1LIEL At least one shutdown cootTngmd7 loo) of'fhemsidual_ heat _rino

% system-oralternate:meth5d' shill ~be verified to >e in operation and circulating

-_ 31A reactor 1561 ant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

A

/ -

b 6 ne shutoown t cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8-hour period. i i

- \

~ !

l GE-STS(BWR/4) 3/4 9-17 e

=., --- , , , ..,----,-,,n -, a

"~

]

I REFUELING OPERATIONS Q UA() Cc TIC 5 y

D 4 Q RESIDUAL I HEAT REMOVAL AND COOLANT CIRCULATION

'HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION ,

[ 3 At least one shutdown cooling mode e residual heat removal (RHR) system shall be OPERABLE tarid in opira on5'with at least:

h [ One OPERABLE RHR pump, and i

{ Y [ One OPERABLE RHR heat exchanger.

nup c APPLICABILITY: OPERATIONAL-CON &ITION 5, when irradiated /fueff's in the reactor

[

vesselandthewaterlevelisgreaterthanorequalto((237 feet.abovethetop j of the reactor pressure vessel flange.

ACTION: '

With no RHR shutdown cooling mode loop OPERABLE, within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, demonstrate the operability of at !

i least one alternate method capable of decay heat removal. Othentise, suspend all operations involving an-increase in the reactor decay heat load and establish SECONDARY C0hTAINMENT INTEGRITY within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . ,

b. ittrno1tHR~shstdown cooling mode loop in operation, within one hour establish reactor coolant circulation by an alternate method and monito.r i reactor coolant temperature at least once per hour. # ;

SURVEILLANCE REQUIREMENTS i

bNiLIAt leastM shutdown cooling mode loo) of theMsidual heat removal ~

I systes'er ilferiateMhod,shall be verified to >eioperatTon and, circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . i i

mCW o O Yr The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

, per 8-hour period.

e l

_ i

~

GE-STS(BWR/4) .

3/4 9-16 i

,,s , -~ ,,n..--,.w.-- r .--- ,- , . - - - --w., ---4r--+- p- y- r

__~

y ak f]cd;kuwvr zA A'

(.z & T(Drizfuy -

REFUELING OPERATIi W '

() M/r/) C t 7~/ 63~

N 'ow wa = = 5' *

. FORINFORMAIl0N DE .

LIMITING CONDITION FOR OPERATION

[M Two shutdown coolin modelo re RHR) system shall be OPERABLEtaW!E least bofjhe residual-oop M a'TT he in opirat with each loop consisting of atl irst P --

a. One OPERABLE RHR pump, and

b. One OPERABLE RHR heat exchanger.

moc APPLICABILITY: OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor !

vessel and the water level is less than J23) feet above the top of the reactor pressure vessel flange. N k ,

ACTION:

(a'y With less than the above-required shutdown cooling mode loops of the RHR i system OPERABLE, within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months there- '

after demonstrate the operability of at least one alternate method ;

capable of decay heat removal for each inoperable RHR shutdown cooling ;

mode loop. 1

.A

b. With no RHR shutdown cooling mode loop in operation, within one hour establish reactor coolant circulation by an alternate method and monitor ,

- reactor coolant temperature at least once per hour.

A -. ]

SURVEILLANCE REQUIREMENTS i

.s

]

4.

system b >orAt leastmethod alternate one shutdown shall be verifiedcooling to mode residualloobof heat removal iOperatiinEand> circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . /

Tl[h- \

2 )

%^ja h 12nr nu$ut . Y )kl "Ine shutcown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per B-hour period.

h 2

O GE-STS(BWR/4) 3/4 s-17

ML20087H865

Text

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