Text

Proposed Tech Specs Revising Footnote Specifying Conditions Where Isolation Valves Associated W/Lpci Sys Operation Are Repositioned
	ML20217J584
Person / Time
Site:	Fermi
Issue date:	03/27/1998
From:	; DETROIT EDISON CO.
To:	;
Shared Package
ML20217J574	List: ML20217J584; NRC-98-0034, Application for Amend to License NPF-43,revising Footnote Specifying Conditions Where Isolation Valves Associated W/ LPCI Sys Operation Are Repositioned;
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	NUDOCS 9804060331
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- c. Enclosure 3 to j NRC-98-0034 J 1

l ENCLOSURE 3-PARTl' PROPOSED TECHNICAL SPECIFICATION PAGE MARK-UP

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. i 3/4.5 EMERGENCY CORE COOLING SYSTEMS '. ,

1 E4' ECCS - OPERATING LIMITING CONDITION FOR OPERATION 3.5.1 The emergency core cooling systems shall be OPERABLE with: '

a. The core spray system (CSS) consisting of two subsystems with each subsystem comprised of: i

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1. Two OPERABLE CSS pumps, and (see Tsc 89-004) k I

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2. An OPERABLE flow path capable of taking suction from the )

kw E L 28u suppression chamber ano transferring the water through the

g. o) spray sparger to the reactor vessel.

N E. E' b. .The low pressure coolant injection (LPCI) system of the residual heat

,0]. removal system comprised of: consisting of two subsystems with each subsystem I(N $

( y Jj y 1. Two OPERABLE LPCI (RHR) pumps, and

=: 'E I 2.

l(;z An OPERABLE flow path capable of taking suction from the a suppression chamber and transferring the water to the reactor !

' (k O o ? vessel.***- l N?.h27 i c.

The high pressure cooling injection (HPCI) system consisting of:

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1. One OPERABLE HPCI pump, and f ;<r E '

2. An OPERABLE flow path capable of taking suction from the I

L E- 5 a: 1, suppression chamber and transferring the water to the reactor g. ;

vessel. WEE '

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The automatic depressurization system (ADS) with at least five i;P.! 2 b y

OPERABLE ADS valves. I E3lM E E. E '

ADPt IC ABil'ITY: OPERATIONAL CONDITION 1, W" # and s

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"Ine.HPCI system is not recuired to be OPERABLE when reactor steam dome pressure is less than or eaual to'150 psig. fe"g<

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"The ADS is not required to be OPERAGLE when reactor steam dome pressu lo s than or equal to 150 psig. re is (I jE'.gus eg P{

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ir. th: r.::r :hu; dan :a i;; .2d: :r :p=:t:= pr e-. E=g b"See Special Test Exception 3.10.6. '

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FERMI - UNIT 2 3/4 5-1 3!$b '

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A EMERGENCY CORE COOLING SYSTEMS 3/4 5.2 ECCS - SHUTDOWN g_g LIMITING CONDITION FOR OPERATION 3.5.2 At least two of the following subsystems shall be OPERABLE:

a.

Core spray system (CSS) subsystems with a subsystem com 1.

At least two OPERABLE CSS pumps, and 2.

An OPERABLE flow path capable of taking suction from at l one of the following water tources and transferring the water through the spray sparger to the reactor vessel:

a) From.the suppression chamber, or b)

When the suppression chamber water level is less than th limit required in 5pecification 3.5.3 or is drained, from the condensate storage tank containing at least 150 000 available 18 fset. gallons of water, equivalent to a level of b.

subsystem comprised of: Low pressure coolant injection (LPCI w ,sj 2 .o 1.

At least two OPERABLE LPCI (RNR) pumps, and 3

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2.

An OPERABLE flow path capable of taking suction from the l

lye o.E f w.oM' -

suppression chamber and transferring the water to the reactor vessel"*.

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..!jo2'{ APPLICABILITY:

'm ' 5 s - o OPERATIONAL CONDITION 4 and 5".

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o. ; ACTION:

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.E -c 3 .g% , '8 1 With one of the above required subsystem (

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all operations with a potential for draining the reactor' vessel.

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ALTERATIONS and all operations with a pot reactor vessel.

5. : k@2 g 8 Restore at least one subsystem to OPERABLE status jd

, ahE' Q.6 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or. establish SECONDARY CONTAIME the rwxt 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

a0 soE8 i

The ECCS is not requir-d to be OPERA 8LE provided that the reactor v I i is removed, the cavity fs flooded, the spent fuel pool gates

. esselare headremove

, and water level is maintained within the limits of Specification 3.9.8 ...

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FERMI - UNIT 2 3/4 5-6

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.8 c-8 hh=h.3/4.5 EMERGENCY CORE COOLING SYSTEM

-Q R o mEF ' BASES

-(y.8*E i a, R o 3 y ~a 3/4.5.1 and 3/4.5.2 ECCS - OPERATING and SHUTDOWN

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(N$jj.l The core spray system (CSS), together with the LPCI mode of the RHR ,

4o -. : g I system, is-provided to assure that the core is adequately cooled following a

'q 5 a 8 loss-of-coolant accident and provides adequate core cooling capacity for all break sizes up to and including the double-ended. reactor recirculation line j a,E E C y e Eo{ h break, and for smaller breaks following depressurization by the AD 8.8 e $ The CSS is a primary. source of emergency core cooling after the reactor vessel is depressurized and a som- for flooding of the core in case of 8 7,g$ a=ly accidental draining.

he ih The surveillance requirements provide adequate assurance that the CSS will be OPERABLE when. required. Although all active components are testable fp s i#~3s .8 sand full flow can be demonstrated by recirculation through a test loop during reactor operation, a complete functional test requires reactor shutdown. The

(]8 3E 7 y pump discharge piping is maintained full to prevent water hammer damage to a E c@ E = piping and to start cooling at the earliest moment.

s i s a d I 1 c i o ti , or- er or e r m al e or 1 me t ac e s o o.

o e P c po nts 1 to ic y ea gn s r a e ss y. j ;

The low pressure coolant injection (LPCI) mode of the RHR system is ~

provided'to assure that the core is adequately cooled following a loss-of- !

.k coolant accident. Two subsystems, each with two pumps, provide adequate core W flooding for all break sizes up to and. including the double-ended reactor p5 g :

E5 18 recirculation line break, and for small breaks following depressurization by j i

.) % $ p the ADS. i La E i

@5~Ou(t L The surveillance requirements provide adequate m urance that the LPCI Vs C system will be OPERABLE when required. Although al? 2 dice components are ds5-5I EO testable and full flow can be demostrated by recircA mon through a test i 1

I loop during reactor operation, a complete functional test requires reactor :

Mcj E :.5 M3 shutdown. The pump discharge piping is maintained full to prevent water hammer damage to piping and to start cooling at the earliest moment.

The high pressure coolant injection (HPCI) system is provided to assure

$$i s 2% < El :E? [ that the reactor core is adequately cooled to limit fuel clad temp -

s5h the event.of a small break in the reactor coolant system and loss of coolant ifg=

~2

. e .D which does not result in rapid depressurization of the reactor vessel. The HPCI system permits the reactor to be shut down while maintaining sufficient Q The (8

. %j .84 reactor vessel water level inventory until the vessel is depressurized.

L i? 5. ag s- 4 j iHPCI pressuresystem continues at which to operate CSS system operation untilorreactor vessel LPCI mode pressure of the is below the RHR system i E 8 E_-g l operation maintains core cooling,

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-Emu 1- ERMI - UNIT 2 B 3/4 5-1

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I Enclosure 3 to

' NRC-98-0034 l

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l ENCLOSURE 3-PART2 PROPOSED TECHNICAL SPECIFICATION REVISED PAGES INCLUDED PAGES:

3.5.1 AND 3.5.2 BASES 3.5.1 AND 3.5.2 l

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4 3/4.5- EMERGENCY CORE COOLING SYSTEMS 3 /4'. 5.1 ECCS - OPERATING LIMITING CONDITION FOR OPERATION _

3.5.1 The emergency core cooling systems shall be OPERABLE with:

a. The core spray system (CSS) consisting of two subsystems with each subsystem comprised of:

1. Two OPERABLE CSS pumps, and

2. An OPERABLE flow path capable of taking suction from the suppression chamber and transferring the water through the spray sparger to the reactor vessel.

b. The low pressure coolant injection (LPCI) system of the residual heat removal system consisting of two subsystems with each subsystem comprised of:

1. Two OPERABLE LPCI (RHR) pumps, and

2. An OPERABLE flow path capable of taking suction from the {

suppression chamber and transferring the water to the reactor i vessel.*** l

< c. The high pressure cooling injection (HPCI) system consisting of:

1. One OPERABLE fiMI pump, and

2. An OPERABLE flow path capable of taking suction from the j suppression chamber and transferring the water to the reactor i vessel.

d. The automatic depressurization system (ADS) with at least five OPERABLE ADS valves.

APPLICABILITY: OPERATIONAL CONDITION 1, 2* ** # and 3***. l

'The HPCI system' is not required to be OPERABLE when reactor steam dome pressure is less than or equal to 150 psig.

- The .4DS is not required to be OPERABLE when reactor steam dome pressure is less than or equal to 150 psig.

- - Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE durir.g alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut-in permissive pressure in OPERATIONAL CONDITION 3, if capable of being manually realigned and not otherwise inoperable.

See Special Test Exception 3.10.6.

FERMI ~ UNIT 2 3/4 5-1 Amendment No.

. - EMERGENCY CORE TOOLING SYSTEMS 3/4 5.2 ECCS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.5.2 At least' two.of' the following subsystems shall be OPERABLE:

i

a. Core spray system (CSS) subsystems with a subsystem comprised of: s

1. At least two OPERABLE CSS pumps, and

2. An OPERABLE flow path capable of taking suction from at least 3 one of the following. water sources and transferring the water through the spray ~sparger to the-reactor vessel: ,

J a) From the suppression chamber, or b) When the suppression chamber water level is less than the limit required in Specification 3.5.3 or is drained, from the condensate storage tank containing at least 150,000 available' gallons of water, equivalent to a level of 18 feet.

.b. Low pressure coolant injection (LPCI) system subsystems with a

. subsystem comprised of:

1. At least_two OPERABLE LPCI (RHR) pumps, and-u

~

2. An OPERABLE flow path capable of taking suction from the l suppression chamber and transferring the water to the reactor 1 vessel **.

APPLICABILITY:- OPERATIONAL CONDITION 4 and 5*.

ACTION:

a. With one of the above required subsystem (s) inoperable, restore at least two subsystem (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or suspend all operations with a-potential for draining the reactor vessel. ,

.b.. With both of the above required subsystems inop' erable', suspend CORE ALTERATIONS and all operations with a potential for draining the reactor vessel. Restore at:1 east one subsystem to OPERABLE status I

within.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or establish SECONDARY CONTAINMENT INTEGRITY within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

t *The ECCS is not required to be OPERAB'LE provided that.the reactor vessel head ?is removed,. the cavity is; flooded, the spent fuel pool gates are -

removed, and water level-is maintair,ed within the limits of Specification 3.9.8 and 3.9.9. . .

- LPCI subsystem (s) may be considered OPERABLE during alignment and operation. '

for decay heat removal if capable of being manually realigned and net otherwise inoperable.

FERMI'- UNIT 2 3/4 5-6 Amendment No.

e 7 .

I 3/4.5 EMERGENCY CORE COOLING SYSTEN-BASES 3/4.5.1 and 3/4.5.2 ECCS - OPERATING and SHUTDOWN The core spray system (CSS),.together with the'LPCI mode of the RHR system, is provided to assure that the core is adequately cooled following a loss-of-coolant accident and providos adequate core cooling capacity for all break sizes up to and including the double-ended reactor recirculation line break, and for smaller breaks following depressurization by the ADS.

The CSS is a primary source of emergency core cooling after the reactor vessel is depressurized and a source for flooding of the core.in case of accidental draining.

The surveillance requirements provide adequate assurance that the CSS

, will be OPERABLE when required. Although all active components are testable and full flow can be demonstrated by recirculation through a test loop during L reactor operation, a complete functional test requires reactor shutdown. The pump discharge piping is maintained full to prevent water hammer damage to piping and to start cooling at the earliest moment.

LPCI subsystems may be considered OPERABLE during alignment and operation for decay heat removal when below the actual RHR cut in permissive

pressure in OPERATIONAL CONDITIONS 3, 4, and 5, if capable of being manually realigned (remote or local) to the LPCI mode and not otherwise inoperable. At these low' pressures and decay heat levels, a reduced complement of ECCS subsystems should provide.the required core cooling, thereby allowing-p 'operatton of RHR. shutdown cooling.when necessary.. ,

i The low pressure coolant injection (LPCI) mode of the RHR system is provided to assure that.the core is adequately cooled following a loss-of-t coolant accident. Two subsystems, each with two pumps, provide adequate core l

flooding for all break sizes up to and includir.g the double-ended reactor recirculation line break, and for small breaks following depressurization by the ADS. j 1

. .The surveillance requirements provide adequate assurance that the LPCI J system will be OPERABLE when required. Although all active components are -!

testable and full flow can be demonstrated by recirculation through a test !

loop during reactor operation, a complete functional test requires rescior H

shutdown. The pump discharge piping is maintained full to prevent water hammer damage to piping and to start cooling at the earliest moment.

The high pressure coolant injection (HPCI) system is provided to assure that the reactor core is adequately cooled to limit fuel clad temperature in l

. the event of a small break in the reactor coolant system and loss of coolant '

which does not result in rapid depressurization.of the reactor vessel. The HPCI system permits the reactor to be shut down while maintaining sufficient i reactor. vessel' water' level inventory until the vessel is depressurized. The ;

HPCI system continues to operate until reactor vessel pressure is below the l pressure:st which CSS system operation or LPCI mode of the RHR system operation maintains core cooling.

FERMI - UNIT 2. B 3/4 5-1 Amendment No.

ML20217J584

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