ML20077S304

Proposed Tech Specs Revising Pressure Alarm Setpoint Allowable Values for ECCS & RCIC Sys Keep Filled Pressure Instrumentation Channels

ML20077S304
Person / Time
Site:	LaSalle
Issue date:	01/13/1995
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20077S293	List: ML20077S290 ML20077S304
References
NUDOCS 9501240041
Download: ML20077S304 (48)

Text

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EMERGENCY CORE CCOLING $YSTEMS SURVEILLANCE REQUIREMENTS 4.5.1 ECCs divisions 1, 2 and 3 shall be demonstrated OPERABLE by:

a.

At least once per 31 days for the LPCs, LPCI and HPCS systems:

1.

Verifying by venting at the high point vents that the ~ system piping from the pump discharge valve to the system isolation valve is filled with water.

2. '

, Performance of a CHANNEL FUNCTIONAL TEST of the:

a) Discharge line " keep filled" pressure alare instrumentation, and b) Header delta P instrumentation.

3.

Verifying that each va?ve, manual, power operated or autoestic, in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

4.

Verifying that each ECCS corner rose watertight door is closed, except during normal entry and exit from the room.

b.

Yorifying that, when tasted pursuant to Specification 4.0.5, each:

1.'

LPCs pump develops a flow,of at least 5350 pm against a test line pressure greater than or equal to 290 psig.

2. LPCI pump develops a flow of at least 7200 gpa against a test line pressure greater than or equal to 130 psig.

3. HPCS pump develops a flow of at least 5250 pm against a test line pressure greater than or equal to 370 psig.

c. For the LPCS, LPC and HPCS systems, at least once per 18 months:

l

1. Performing a system fu'nctional test which includes simulated automatic acteation of the systas throughout its emergency operating sequence and verifying that each automatic valve in

• the flow path actuates to its correct position. Actual injection

• of coolant into the reactor vessel may be excluded from this test.

2. . Performing a CHANNEL CALIBRATION of the: .

a) Discharge line ' keep fill ssure a ru instrumentation and verifying the: gf og ggg

1) High pressure setpoi and the low pressure setpo

._, of the:

"The specified 18 month interval may be waived for Cycle 1 providcd surveillance is performed during Refuel 1.

LA SALLE - UNIT 1 3/4 5-4 Amencment No. 25

^ 9501240041 950113' '

PDR ADOCK 05000373 P PDR

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. BERGDICY CORE C00LIIIG SYSTBIS SURVEILLANCE REQUIRBENTS (Continued) 1

. (a) LPCS system to be 1500 psig and > 55 psig, respectively.

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P %p (b) LPCI sub temstobe1400psigand>55psig,.

\

l

g. respecti ly. - ,

Low pressure setpoint of the WCS system to be > )

i(2) 63 psig. -

1 b) Needer delta P instrumentation and veri the setpoint .

of the:

- 0llOWable Va tw

1) LPCS system and LPCI subsystems to t 1 ps .

2) HPCS system to be 5 t 2.0 psid greater than the normal indicated AP.

3. Deleted.

4. Visually inspecting the ECCS corner room watertight door seals und room penetration seals and verifying no abnomal degradation, damage, or obstructions.

d. For the ADS by:  !

1. At least once per 31 days, performing a CHAlflEL RETI0llAL TEST of the accesulator backg compressd gas system low pressure alarm system.

2. At least once per 18 months:

a) Performing a system functional test which includes simulated '

automatic actuation of the system throu operating sequence, but excluding actua@ valve actuatton.ut -

b) Manually opening each ADS v 'alve and observing the eqected change in the indicaten valve position. ,

) Perfoming a CHANNEL CALIBRATION of the accumulator backup compressed lyas system low pressure alarm system and verifying an alarm se". point of 500 + 40, - O psig on decreasing pressure.

4 3

l LA SALLE - UNIT 1 3/4 5-5 Amendneut No. 78, al l

ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSEffECHNICAL SPECIFICATIONS INSERT A (a) LPCS system to be s 500 psig and 2 45.5 psig, respectively.

(b) LPCI subsystem "A" to be s 400 psig and 2 41.0 psig, respectively.

(c) LPCI subsystem "B" to be s 400 psig and 2 38.5 psig, respectively.

(d) LPCI subsystem "C" to be 5 400 psig and 2 45.0 psig, respectively.

2) Low pressure setpoint allowable value of the HPCS system to be 2 42.5 psig. '

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g. P SYSTEMS 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM LIMITING CONDITION FOR OP'ERATION 3.7.3 The reactor core isolation cooling (RCIC) system shall be OPERABLE with an OPERABLE flow path capable of taking suction from the suppression pool and transferring the water to the reactor pressure vessel.

APPLICABILITY: OPERATIONAL ONS 1, 2, and 3 with reactor steam done pressure greater than 150 psig. -

ACTION:

a. With a RCIC discharge line " keep filled" pressure alam instrueenta-tion channnel inoperable, perform Surveillance Requirement 4.7.3.a.1 at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. -

b. With the RCIC system inoperable, operation may continue provided the HPCS system is OPERABLE; restore the RCIC system fo OPERABLE status '

within 14 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reduce reactor steam done pressure to less than or equal to 150 psig within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• SURVEILLANCE REQUIREMENTS 4.7.3 The RCIC system shall be demonstrated OPERABLE:  !

a. At least once per 31 days by: '

1. Verifying by venting at the high point vents that the system piping from the pump discharge valve to the system isolation valve is filled with water.

2. Performance of a CHANNEL FUNCTIONAL TEST of the discharge line

" keep filled" pressure alars instrumentation, and

3. Verifying that each valve, manual, power operated or automatic in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.

4. Verifying that the pump flow controller is in the correc't position,

b. At least once per 92 days by verifying that the RCIC pumn. develops a ficw of greater than or equal to 600 gpa in the test flow path with a system head corresponding to reactor vessel operating pressure when steam is being supplied u the turbbt at 1000 - M. - 80 psig."

%ne ;;,rovmons et 5pecificationm.0.4 are not applicacie provided tne surveillance is performed within 12 neurs after reactor steam pressure is ,

quate to perform the tests.

Special Test Exception 3.10.7 LA SALLE - UNIT 1 3/4 7-7 ,

~

PLANf SYSTEMS SUWEILLANCE REOUIREIENTS

c. At least once per 18 months by: *

1. Perfoming a system functional test which includes simulated autametic actuation and verifying that each automatic valve in the flow path actustas to its correct position, but may exclude actual injection of coolant into the reactor vessel.

2. Verifying that the system is capable of providing a flow of greater than or equal.to 600 gum to the reactor vessel when g steam is supplied to the turbine at a pressure of 150 2 15 psig using the test flew path." -

3. Perfo ming a CALIBRATI ' the siscnarge une " keep

'1ai filled" pressure a a m i ion and verifying the low pressure setpoi be > g. -

d. By demonstrating MCC-122y and tAs volt battery and charger OPERABLE:

l16

1. At least once per 7 days by verifying that:

a) MCC-123y is energized, and has correct breaker alignment, indicated power availability from the charger and battery, and voltage en the panel with an overell voltage of greater than or equal to 250 volts.

b) The electrolyta level of each pilot cell is above the plates, c) The pilot cell specific gravity, corrected to 778F, is greater than or equal to 1.200, and -

d) "he overall battery voltage is greater than or equal to 250 volts.

2. At least once per 92 days by verifying thst:

a) The weltage of each connected battery is greater than or equal to 250 volts under float charge and has not decreased more than 22 volts from the value observed during the original test, b) The specific gravity, corrected to 77'F, of each connected cell is greater than or equal to 1.195 and has not decreased more than 0.05 from the value observed during the previous test, and  ;

c) The electrolyte level of each connected cell is above the  :

l plates.

3. At least once per 28 months by verifying that:

a) The bettery shows no visual indication of ptysical damage or abnomal deterioration, and b) Battery taminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.

' *The provisions of Specification ~ 4.0.4 are not applicably provided the surveillance is performed within 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> after reactor steam pressure is i adequate to perfom the tests. *

. Le i LA SALLE - UNIT 1 3/4 7-8 Am.andment No. 28 l l

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,, 3/4.5 EMERGENCY CORE COOLING SYSTEM j

BASES 3/4.5.1 and 3/4.5.2 ECCS - OPERATING and SMTTDOl8f -

ECCS Division 1 consists of the low pressure core spray system low pressure coolant injection subsystem "A" of the NR system, and the, automatic depressurization system (ADS) as actuated by ADS trip system "A". ECCS ,

Division 2 consists of low pressure coolant in action subsystems "B"and "C"  ;

of the RHR system and the automatic depressuri ion system as actuated'by ADS trip system B". i The low pressure core spray '

core is adequately cooled followin(g a loss-of-coolant accident and p a unte core cooling capaci for all break sizes up to and including the -

do le-ended reactor recircul tion line break breaks following depressurization by the ADS., and for transients or smaller The LPCS 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 LPCS sys-ten will be OPERABLE when required. Al all active components are testable and full slow can be demonstrated recircu ation through a test loop during reactor operation a complete funct onal test requires reactor shutdown. The pump discharge pi ing is maintained full to prevent water hammer damage to piping and to start cooling at the earliest moment. ( _

The low pressure coolant injection (LPCI) mode of the NR system is pro-vided to assure that the core is tely cooled followi a less-of-coolant -

accident. Three subsystems, each wi one pump, provide core flooding for all break sizes up to and including the double ended reactor recirculation line break, and for transients or small breaks following depressurization by the ADS.

The surveillance requirements provide adequata assurance that the LPCI system will be OPERABLE when required.

testable and full flow can be demonstratedAlthough all active components are loop durin recirculation through a test shutdown. gThe reactor operation, a complete f ional test requires reactor p dische pipi is maintained full to prevent water hammer damage to p ping to sta cooling at the earliest moment. ( A ECCS Division 3 cons high pressure core sprey (istssystem of the 'shigh pressure core spray tea. The NPCS provided to assure t the reactor core is adequately cooled to 1 mit fuel clad tamperature in 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 IPCS system )g fl persits the reactor to be shut down while maintaining sufficient reactor '

vessel water level inventory until the vessel is depressurized. The HPCS system operates over a range of 1160 psid, differential pressure between j -f reactor vessel and HPCS suction source, to O psid.

The capacity of the HPCS system is selected to provide the required core 9 '

, cooling. Tm HPCS pump is desi to deliver r than or equal to

' 516/1550/6200 gpa at differenti 1 pressures of /1130/200 psin Water is takenfromthesupressionpoolandinjectedintothereactor.

LA SALLE - UNIT 1 8 3/4 5-1 Amendment No. 29. 81

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O ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS INSERT B The low pressure setpoint allowable value for the discharge line " keep-filled" alarm is based on the head of water between the centerline of the pump discharge and the system high point vent.

INSERT C The low pressure setpoint allowable value for the discharge line " keep-filled" alarm is based on the head of water between the centerline of the associated pump discharge and the system high point vent.

i kr\nla\lasalle\keepf1sw.wpfl5 1

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EMERGENCY CORE COOLIE SYSTEMS '

BASES c SE T ECCS-0PERATI E and S WTD0 lei (Continued)

,l i With the HPCS system inoperable adequata core cooling is assured by the OPERABILITY of the redundant and dive,rsified automatic depressurization system i and both the LPCS and LPCI systems. In addition, the reactor core isolation  :

cooling (RCIC) systas, a tem for which no credit is taken in the hazards  !

analys's, will automaticahy provide makaus at reactor operating pressures I on i

.a reactor low water level condition. The iPCS out-of-service period of 14 days is based on the demonstrated GPERABILITY of redundant and diversified low pressure core cooling systems. i The surveillance requirements provide adequate assurance that the HPCS system will be DPERABLE when reevired. Although all active components are test-able and full flow can be demonstrated by recirculation through a test loop during reactor operation, a cos tion requires reactor shutdown.plete functional The pug discharge test pipino with reactor vessel in.iec-is maintained full to prevent water hammer damage and to provide cooling at the earliest moment.

Upon failure of the WCS system to function properly if required, the

- automatic depressurization systas CADS) automatically caus,es selected safety-relief valves to open depressuriz9ng the reactor so that flow from the low i pressure core cooline, systems can entar the core in time to limit fuel cladding  !

temperature to less than 2200*F. ADS is conservatively required to be OPERABLE whenever reactor vessel pressuru exceeds 122 psig even though low pressure core )

cooling systems provide adequate core cooling up to 350 psig.

ADS automatically controls seven selected safety-relief valves. Six valves are required to be OPERABLE since the LOCA analysis assumes 6 ADS valves in addition to a single failure. It is therefore appropriate to permit one of the recuired valves to be out-of-service for up to 14 days without materially recucing system reliability.

3/4.5.3 SUPPRESSION CHAS ER .

The suppression chamber is also required to be OPERABLE as part of the ECCS to ensure that a sufficient supply of water is available to the HPCS, LPCS and LPCI systaas in the event of a LOCA. This limit on suppression chamber minimum water volume ensures that sufficient water is available to permit recirculation cooling flow to the core (See Figure B 3/4.6.2-1). The OPERABILITY of the suppress on chamber in OPERATIONAL COM ITIONS 1, 2 or 3 is required by Specification 3.6.2.1.

Repair work might require making the suppression chamber inoperable.

This specification will permit those repairs to be made and at the same time give assurance that the irradiated fuel has an adequate cooling water supply when the suppression chamber must be made inoperable in OPERATIONAL C0E ITION 4 or 5.

4 In OPERATIONAL CDEITION 4 and 5 the suppression chamber minimum required water 200*F. volume is reduced because the reactor coolant is maintained at or below Since pressure suppression is not, required below 212*F, the minimum water voline is based on NPSH, recirculation volume, vortex prevention plus a 2'-4" safety margin for conservatism.

LA SALLE - UNIT 1 8 3/4 5-2 Amendment No. H, 81 i

A ' *. -" ~

ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSEffECHNICAL SPECIFICATIONS INSERT D The low pressure setpoint allowable value for the discharge line " keep-filled" alarm is based on the head of water between the centerline of the pump discharge and the system high point vent.

kt\nla\lasalle\keepfisw.wpf16

3/4.7 PLANT SYSTBtS BASES 3/4.7.1 EE91 STEsY s&si.ING 5Yaien - EOUIppENT COOLING WATER SYSTEMS The OPERA 8ILITY of the core standby cooling system - equipment cooling water systems and the ultimate host sink ensure that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions.

The redundant cooling capacity of these systems, accident conditions within acceptable limits. assuming a single failure, 3/4.7.2 CONTROL A00N AND AUKILIARY ELECTRIC EDUIPIENT ;;-

FILTRATION SVMEM ar==H-$

i The OPERASILITY of the control room and auxiliary electric equipme'nt room emergency filtration system ensures that the rooms will remain habitable for operations personnel during and following all design basis accident conditions.

The OPERABILITY of this systsu in conjunction with room design provisions is based on limitir the radiation esposure to personnel occupying the rooms to 5 ren or less whole bo%, or its equivalent.

This limitation is consistent with Part 50. the requirements of General Design Criteria 19 of Appendix "A".10 CFR Cassulative operation of the system with the heaters OPERABLE for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to ?oduce the buildup of moisture' on the adsorbers and EPA filters.

3/4.7.3 REACTOR CORE InnLATION COOLING SYaitn ^

The reactor core isolat?on cooling (RCIC) system is provided to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without requiring actuation of any of the Emergency Core Cooling System equipment. The RCIC system is conservatively required to be OPERABLE whenever reactor pressure exceeds 150 psig even though the LPCI mode of the the residual heat removal (RNR) system provides adequate core cooling up to 350 psig.

The RCIC system specifications are applicable during OPERATIONAL CONDITIONS 1, 2 and 3 when raector vessel pressure exceeds 150 psig because RCIC is the primary pressurized. non-ECCS source of core cooling when the reactor is With the RCIC system inoperable, adequate core cooling is assured'by the OPERA 8ILITY of the NPCS system and justifies the specified 14 day out of-service period.

i be OPEKABLE The surveillance requirements when required. provide adequate assurance that RCICS will Although all active components are testable and full flow can be demonstrated by recirculation during reactor operation, a complete functional test r aquires reactor shutdown. 1.iithal startup test program data may be used to determine equivalent turbine / pump capabilities between piping test flow path is maintained and full to the vessel prevent water injection hammer flow path. The pimp discharge at the earliest possible moment. < -

and to start cooling Ak g1NSERT "

LA SALLE - UNIT 1 B 3/4 7-1 Amendment 5 i

b*. Ab g ,

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h ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS INSERT E The low pressure setpoint allowable value for the discharge line " keep-filled" alarm is based on the head of water between the centerline of the pump discharge and the system high point vent.

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. SURVEILLANCE 8mm_rf8m 9fr5 -

4.5.1 ECS divisions 1, 2 and 3 shall he demonstrated tyERABLE by:

a At least emse per 31 days for the LPCI, LPt2, and WC5 systems:

1. Verifying by wanting at the high point vents that the system '

piping from the pump discharge valve to the system isolation

, velve is filled with untar. 1 L Performance of a Cn415EL MBICTIONAL TEST of the:

1 l

a) Diesharge line " keep ff11ed" preneure alars fastrementaties,

• l and -

b) Needer delta p instr uestshten. .

2. Verifyisy that ensk valve Mammal, power-sperstad, or automatic,)

in the new path that is est lashed, esaled, or otherwise '

l ensured fa posities,is in its sorrect peettien.

l

~ 4. . Verifying'thstr esalt EEE corner team waterti'ght. door is elesad, mesyt derfag entry ta and suit free the room.

h.. . Verifying that, edian tasted parnuest. to Specification 4.0.5, each:

1. LPCS pump develops a fisw of at least 8350 gis against a  !

test line pressure greater than er egeal to 250 peig. .

, j L LPCI peep develops a flew of at least.7200 gis assinet a test i Time pressere greater them er egent to 130 psis. l

~

3. WC5 peep develops a flew of at lasst 5200 gis agninst a test

.... . Itas

. . c.

c;-j For n.x.,,tha ;LPC5',

.~ pressure LPCI and WC5 greater theeenener por egeal la months:to 330 po systems, at least Z".f' Phrflensfag a system fonctional test which includes simulated g*e-UCautomatic actuation of the systas throughout its emer p.

' sperating segeance and verifying that each estamatic valve in the flew path Mktustas ta its correct positten. Actual injection of seelest ists the reacter vessel any be excluded free tais tast.

2.

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-' L th SALif - talIT 2 -

<- 3/4 5-4 L- 1

EfERGENCY CORE COOLING SYST9t$ -

' SURVEILLANCE REQUIRDENTS (Continued)

2. Perforniig a CHANNEL. CALIBRATION of the: I a)

Discherm and ver'fyingline the: " keep filled" pressure alam instrumentat High pressure setpointd and the low pressure setpoint b of the:

{' ) _

(a) LPCS system to be 1 500 psig and 1 55 psig, qkB[gc8

,8 respectively.

d 1 55 n ig, (y$EBT (o tPCI respecti s e gly.m . to be s 4 . ,sig

2) Low pressure setpoint of the HPCS system to be 1 63 psig.

b) Header delta P instrumentation and verifying the setpoint of the:

1) LPCS syst.am and LPCI subsystems to be t I psid.

2) HPCS system to be 5 t 2.0 psid greater than the nomal indicated AP.

3. Deleted

4. Visually inspecting the ECCS corner room watertight door seals and room penetration seals and verifying no abnormal degradation, damage, or obstructions.

d. For the ADS by.

1. At least once per 31 days, performing a CHANNEL FUNCTIONAL TEST of the accumulator backup compressed gas system low pressure alarm systan.

2. At least once per 18 months:

[ a) Performing a system functional test which includes simulated l

automatic actuation of the system throughout its emergency i operating sequence, but excluding actua' valve actuation.

b) Manually opening each ADS valve and observing-the expected change in the indicated valve position.

c) Performing a CHANNEL CALIBRATION of the accumulator backup compressed gas system low pressure alarm system and verifying an alam setpoint of 500 + 40, - O psig on decreasing pressure.

LA SALLE - UNIT 2 3/4 5-5 AfGDENT NO. 65 I --

O ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSEfl'ECHNICAL SPECIFICATIONS INSERT A (a) LPCS system to be s 500 psig and 2 45.5 psig, respectively.

(b) LPCI subsystem "A" to be s 400 psig and 2 41.0 psig, respectively.

(c) LPCI subsystem "B" to be s 400 psig and 2 38.5 psig, respectively.

(d) LPCI subsystem "C" to be s 400 psig and 2 45.0 psig, respectively.

2) Low pressure setpoint allowable value of the HPCS system to be 2 42.5 psig.

k:\nla\lasalle\keepfinw.wpf14 t

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PUWIT SYSTRE 4/4,7.3 MACTOR CDRlERATIOff CDOLINB SYSTyl Luumin M1uun FOR OPERATIM I.7.3 The reacter omre insisties cooling (EIC) systas shall he OPERABLE vfth an OPERABLE flew path capable of taking sustian from the segyression peel and transferring the unter to the reacter pressure vessel.

. APPLICABILITY: OPERATIMAL 1, 2, and 3 with reacter stame done pressure greater then 350 poi M

. a. Wfth a E!C dfacharge line 'hony ff11ed pressure alam instroente-  :

ties channnel insperable, perfem surveillance Requirusent 4.7.3.a.1 at least once per N hours. .

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Wfth the KIC system insperable, aperstian ser continue provided the 2 NPCS system fs SPERABLI; resters the EIC system to OPERABLE status l witMa 34 daye er he in et least MF alsiTDelse witMa the nest 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> <

and reduce reacter steem dome pressure to less ther er equal to 150 poig witMe the fellendag M heers.

SURVEILLAf1CE ---a__.ia - i 4.7.3 The RCIC system shall he demonstrated OPERABLE:

a. At least esce por 31 days hy:

1. Verifying by wanting at the Mgh point vents that the systas piping from the pump discharge valve to the system isolation valve is fl11ed with water.

L performance of a CHA18EL RBICTIONAL TEST of the discharge line

" keep filled" pressure alam instrumentation, and 3' . Verifytay that each valve, menes1 power operstad or autamstic i

le the new path that is not locked, sealed or othemise secured te peoities, is in.its correct position.,

A . Verifytag that the pump flow controller is in the correct posities. .

h. At least once per SE days by verifying that the RCIC-pump develops a flew of greater then er equal to 800 p in the test flew path with a systas head corresponding to reactor vessel aperating pressure when

, stamm is'being supplied to the turtine at 1800 + 5 . - 80 pois.*

"The provistens of 5pecification 4.0.4 are not applicable pewided the surveillance is perferend witMa 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> after reactor stase pressure is

" ta to nerfsrs the t t.s.

@see specia' Test Eaception 3.10.7[

LA SALLE - LatIT 2 2/4 7-7

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SURVEILLAN E HERf!RB etl'5

c. At least eacs por as mentas ay:

_;. 2.

perfbrutag a system feastfonal test which inc.ludes.staatstat. _.__ ..._

autenstic astustian and verifytag that each automatic valve in the flew path actustas to its emerset posities, but sur exclude actus1 fajestien of esolant ists the reester vessel.

L Verifying that the system is capable of providing a flew of greater then er equal to 800 pm to this reacter vessel when ,

. steem is supplied to the tureine at a pressure of 150 a 15 psig i using the tant flew path.*

• l

- 3. performing a CHAlem. CALIBRATIIBI of the discharge line " keep allowable fiii n eress re a>ar= 1 frias the is-gg - . astpoin.,. he 3, ,

d. as IEI:-223y and the 1 and charger

. 1. At. least once per 7 esys by verifytag thst: -

a) IEC-2EIr is enerWiEnd, and has correst brother aligneont, indicated power availahtlity free the charger and, hattery, and weltage en the panel with as evere11 voltage of grestar

• them er equal to 250 volts, b) The elastrolyte level of each pilot call is aheve the platas, .

c) Ths pilot call specific gravity, corrected to 77'F is 4

greater then er esmal-tm L208, red d) The evere11 hattery voltage is greater then er egust to 250 volts.

L At least once*per 92 days by verifying that:

a) The weltage of sech connected battery is grestar then er ageal to 250 vs.Its under flest charge and has not decreased more than 12 volta from the value sheerred during the -

origins 1 tast, b) The specific gravity, corrected ta 77'F, of each connected en11 is greater then er egen) to LISE and has not decreased sure thee 0.05 from the value ahearved during the previous -

g,,g, ,,g , . ..

c)* The electrolyte level of each connected cell is eheve the j

plates.

3. At. least once per 28 eenths by verifying that: .

a) The battery shows ne visus 1 indication of physical demoge er abnerosi estarieration, and b) Battery terminal connections are clean, tight, free of corresten and casted with anticorrosien estarial.

"The previsions of Specification 4.0.4 are not applicably provided the surveillance is perfomed within 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> after reactor staes pressure is adeguate ta perfers the tests. ~

, LA SAlif - UNIT 2 1/4 7-4

3/4.5 EDERGENCY CORE COOLING SYSTEM BASES

, Aco " INSERT  ;

3/4.5.1 and 3/4.5.2 ECCS - OPERATING and SIRffDOlAl ECCS Division 1 consists of the low pressure core spray system, low pres-sure coolant injection subsystem "A" of the NR system, and the automatic de-pressurization system (ADS) as actuated by ADS trip.sy" stem "A". ECCS Division 2 consists of low pressure coolant in;iection subsystems B"and"C"oftheRHRsgs-tan and the automatic depressurization system as actuated by ADS trip system B".

h low pressure core spray (LPCS) system is provided to assure that the I core is adequately cooled following a loss-of-coolant accident and provides adequate core cooling capacity for all break' sizes up to and including the .

double-ended reactor recirculation line break, and for transients or smaller breaks following depressurization by the ADS.

h LPCS is a primary source of emergency core cooling after the reactor vessel is depressurized and a source for nooding of the core in case of accidental draining.

N surveillance requirements provide adequate assurance that the LPCS sys-tan 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 reactor shutdown. The pump discharge piping is maintained full to prevent water hammer damage to-piping and to start cooling at the earliest moment. <

h low pressure coolant injection (LPCI) mode of the NR system is pro-vided to assure that the core is adequately cooled following a loss-of-coolant .

accident. Three subsystems, each with one pimp, provide adequate core flooding i for all break sizes y to and including the double-ended reactor recirculation j line break, and for transients or smal breaks following depressurization by the l ADS.  !

h surveillance requirements provide adequate assurance that the LPCI l 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 coglete functional test requires reactor shutdown. h pump discharge piping is maintained full to prevent water i hammer damage to piping and to start cooling at the earliest moment. 4 -- 1 3

ECCS Division 3 consists of the high pressure core spray systas. The A--

high pressure core spray (HPCS) system 's provided to assure that the reactor D-- l core is adequately cooled to limit fuel clad tamperature in the event of a 3 small break in the reactor coolant system and loss of coolant which does not H result in rapid depressurization of the reactor vessel. h WCS system permits the reactor to be shut down while maintaining sufficient reactor hZ M

vessel water level inventory until the vessel is depressurized. h HPCS ITT system operates over a range of 1160 psid, differential pressure between reactor vessel and HPCS suction source, to O psid. %i M

N capacity of the HPCS system is selseted to provide the' required core O cooling. h HPCS pump is designed to deliver tar than or equal to e 516/15$0/6200 gpa at differential pressures of /1130/200 psid. Water is taken from the suppression pool and injected into the reactor.

LA SALLE - UNIT 2 8 3/4 5-1 Amendment No. 27, 65

ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS INSERT B The low pressure setpoint allowable value for the discharge line " keep-filled" alarm is based on the head of water between the centerline of the pump discharge and the system high point vent.

INSERT C The low pressure setpoint allowable value for the discharge line " keep-filled" alarm is based on the head of water between the centerline of the associated pump discharge and the system high point vent.

k:\nlatlasalle\keepfisw.wpf15 I

EERGENCY CORE COOLING SYSTEMS l

BASES _

ECCS-0PERATINGandSNUTDOWN(Continued) g With the HPCS system inoperable, adequate cote cooling is assured by the  !

OPERA 8ILITY of the redundant and diversified automatic depressurization system i l and both the LPCS and LPCI systans. In addition, the reactor core isolation ] l cooling (RCIC) system, a system for which no credit is taken in the hazards l analysis, will automatically provide makeup at reactor operating pressures on {

l a reactor low water level condition. The HPCS out-of-service period of  ;

14 days is based on the demonstrated OPERASILITY of redundant and diversified low pressure core cooling systans.

j The survaillance requirements provide adequate assurance that the HPCS l system will be OPERABLE when required. Although all active components are { {

testable and full flow can be demonstrated by recirculction through a test l loop during reactor operation, a complete functional test with reactor vessel l l

in action requires reacter shutdown. The pump dische piping is maintained fu1topreveitwaternemmerdamageandtoprovidecoo'ingattheearliestmoment.g i Upon failure of the IPCS system to function properly, if required, the automatic depressurization system (ADS) automatically causes selected safety-relief valves to open, depressurizing the reactor so that flow from the low pressure core cooling systems can enter the core in time to limit fuel cladding '

temperature to less than 2200*F. ADS is conservatively required to be OPERABLE l whenever reactor vessel pressure exceeds 122 psig even though low pressure core i cooling systems provide adequate core cooling up to 350 psig. l ADS automatically controls seven selected safety-relief valves. Six ~

valves are required to be OPERABLE since the LOCA analysis assumes 6 ADS valves in addition to a single failure. It is therefore appropriate to permit ,

l one of thcs required valves to be out-of-service for up to 14 days without  :

materially reducing system reliability. I 3/4.5.3 SUPPRESSION CHAfBER The surpression chamber is also required to be OPERABLE as part of the ECCS to ensure that a sufficient supply of water is available to the HPCS, LPCS and LPCI systems in the event of a LOCA. This limit on suppression chamber minime water volume ensures that sufficient water is available to permit recirculation cooling flow to the cora (See Figure 8 3/4.6.2-1). The OPERASILITY of the suppression chamber in 0PERATIONAL CONDITIONS 1,' 2 or 3 is required by Specification 3.6.2.1.

Repair work might require making the suppression chamber inoperable.

This specification will permit those repairs to be made and at the same time give assurance that the irradiated fuel has an adequate cooling water supply when the suppression chamber must be made inoperable in 0FERATIONAL CONDITION 4 or 5.

In DPERATIONAL C01CITION 4 and 5 the suppression chamber minimum required water voltme is reduced because the reactor coolant is maintained at or below 200*F. Since pressure suppression is not required below 212*F, the minimum water volume is based on NPSH, recirculation volume, vortex prevention plus a 2'-4" safety margin for conservatism.

La SALLE - UNIT 2 , 8 3/4 5-2 Amen h nt No. H . 65

ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSEffECHNICAL SPECIFICATIONS INSERT D The low pressure setpoint allowable value for the discharge line " keep-filled" alarm is based on the head of water between the centerline of the pump discharge and the system high point. vent.

k \nla\lasalle\keepfisw.wpf16 b

. l A.

• 3/4_7__.P3 4 E .fYIYB 5 ,

aASEE 3/4J 1 CIN' STNmf CIMILIlW SY5fB - EN SpMP ISTS SYSTB5 j tea GPERASILITY er the aere steniEy eseling system - equipment coeling l unter systems amt the sitimmte hast sink ensure that sufficient costing copecity l 1s available for aestinued operstian of safety-related equipment during normal ,

and ascident conditions. The redundant asoling cepecity sf these systems, .

l asseing a single failure, is sensistent with the asseptions used in the asetemet conditions withis asseptable limits.

3/4.7.3 CDNfML EllBI Als AINILIARY 88 88"ft!C m'eserf "'" - =%i FILTWA Mal aTaiun The WERASILITY er' the sontrei room and ausiliary electric equipment room emergency Mitration gystem ensurer that the teams will remais hehitable for aparations pereennel eering and following all desige basis accident conditions, j The WBASILITY ef this system is eenjuncties with room dentpe previsions is. -

hosed en lietting the radiation augmourt to pereennel ecungr og the reens to i 5 res or less dele hog, or its ogstwelest. This limitatism is consistent '

with the requirements of General Desip Criteria 19 of Appendix "A* 10 CPR Part.30. Caulative aparettom of the systan with the hasters GPSASLE for la. hours ever a IL der perted,is sufficient., to reese the buildup of meisture 1

( en the admertere and W4 filters 3/4.7,7 IIEACTOR GlK INLpTION COOLIMB SYSTR The reactor care iselsttee cooling (ICIC) systas is provided ta assure  !

I adegusta core coeling is ther event of venctor isolation from its prienry hest f sink and the less of fasesstar flew to the reacter vessel without requiring

• l actuation of agf of tha Emergenry Core Caeli Systas equipsont. The RCIC systeer is conservettvely required to be whenever reacter pressure exceeder 150 psig sees theagh the LPCI ende of the the resideal host removal (NR) systam provides adegasta core cooling g to 350 peig.

' The ACIC. systas specifications are applicable dring OpBATTOIEL l CllWITIGE I;,1 amt 3 when remeter vessel pressure enceeds 150 psig because . . . i M:IC is the primary new ElCE source e' core cooling when the reacter is l pressurtand. '

With the EIt,' insperable, adequate core cooling is' assured by the OPRASILITY ef the system and justifies the specified 14. day out-of-service ,

periest.

The surveillasse requirements provida adequate assuranse that ACICS will be OPSASLE when required. Although all active components are testable and ,

full flew can ha dmoonstrated by restruulaties during reacter 'speration, a l completa functional test regoires reester shstdeun. Initial starte test program esta may he used to deterwise equivalent turtrine/puso capabilities betassen test f?ew path and the vessel injection.f1su path. Th #pu p discharge piping is maintained fuli.te prevent unter hemmer damage and ta start cooling N. at the earliest possible masent. y & l LA SALLE - IBIIT 2 8 3/4 7-1 Ac;c! 1NSEATE, l

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A'ITACHMENT B PROPOSED AMENDMENTS TO THE LICENSE /TECIINICAL SPECIFICATIONP INSERT E The low pressure setpoint allowable value for the discharge line " keep-filled" alarm is based on the head of water between the centerline of the pump discharge and the system high point vent.

k;\nla\lanalle\keeptisw.wpf17 1

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ATTACHMENT C SIGNIFICANT HAZARDS CONSIDERATION Commonwealth Edison has evaluated the proposed Technical Specification Amendment and determined that it does not represent a significant hazards consideration. Based on the criteria for defining a significant hazards consideration established in 10 CFR 50.92, operation of LaSalle County Station Units 1 and 2 in accordance with the proposed amendment will not:

l

1) Involve a significant increase in the probability or consequences of an accident previously evaluated because:

a. The proposed change in the technical specification allowable values for the ECCS and RCIC discharge line " keep filled" alarm instrument channels does not change the design bases or function of these systems as described in the technical specifications and UFSAR. An analysis performed by engineering demonstrates that the proposed allowable values are suflicient for verifying that the ECCS and RCIC pump discharge lines are full of water. In addition, setpcint calculations have l

been performed to verify that sufiicient margin exists between the recommended calibration setpeints and the analytical limits for these instrument channels to account for all applicable instrument errors. This provides high assurance that the trip setpoints of these instrument channels will not drop below the minimum required value. The " keep filled" instrumentation is not a factor in the assumptions of any accidents, thus, the probability of analyzed accidents is not increased.

b. The proposed technical specification amendment does not revise the i configuration of the ECCS and RCIC discharge line " keep filled" l instrument channels or sensing lines. The proposed setpoint allowable values and 1ssociated calibration setpoints are within the calibration ranges of the existing pressure switches. Thus, implementation of the proposed amendment does not involve any physical alterations to the plant except for the recalibration of the pressure switches to the new calibration setpoints.  !

c. The ECCS and RCIC discharge line " keep filled" instrument channels only perform a monitoring function. Other than ensuring system readiness they do not perform a function important to safety. Thus, the probability of a ECCS or RCIC failure is not increased since the operation and function of the ECCS and RCIC discharge line fill systems is not affected by this change.

ki\nla\lasalle\keerfisw.wpfl9

_ _ . J

ATTACHMENT C SIGNIFICANT HAZARDS CONSIDERATION

d. The failure of a ECCS or RCIC discharge line fill system will not go undetected by the proposed change, since water leg pump trips are annunciated in the control room. In addition, quarterly surveillances are performed on these pumps to check for degradation.

e. The ECCS and RCIC discharge line fill systems are not used to mitigate the consequences of an accident or transient. These systems are not required after the ECCS and RCIC pumps are activated.

Therefore, the proposed change does not cause an increase in the probability or consequences of an accident previously evaluated.

2) Create the possibility of a new or different kind of accident from any accident previously evaluated because:

This technical specification amendment only lowers the trip setpoint allowable values for the ECCS and RCIC discharge line " keep filled" alarm instrumentation channels. As described above, the proposed setpoint allowable values are sufficient for verifying that the ECCS and RCIC discharge lines are full of water. Thus, the probability of a water hammer occurring during system activation for a surveillance test is not increased. In addition, each instrument channel is independent from the other channels so that a failure in one channel will not propagate to another channel. Therefore, the operation of the facility in accordance with the proposed amendment does not create the possibility of a new or different kind of accident.

3) Involve a significant reduction in the margin of safety because:

The margin of safety is not affected by this amendment, because this change involves monitoring instrumentation only. The purpose of the ECCS and RCIC discharge line keep fil'ed" alarms is to alert the operators when a ECCS or RCIC system may not be operable due to empty or partially empty discharge lines. The proposed amendment does not alter or degrade this function, since the new setpoint allowable values are adequate for verifying that the discharge lines are full of water. Therefore the operation of the facility in accordance with the proposed amendment does not involve a significant reduction in a margin of safety.

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k: tr.la \lasalle \ keeg f isw.wTf19 l

e ATTACIIMENT C SIGNIFICANT HAZARDS CONSIDERATION Guidance has been provided in " Final Procedures and Standards on No Significant IInzards Considerations," Final Rule,51 FR 7744, for the application of standards to license change requests for determination of the existence of significant hazards considerations. This document provides examples of amendments which are and are not considered likely to involve significant hazards considerations. These proposed amendments most closely fit the example of a change which may either result in some increase to the probability or consequences of a previously analyzed accident er may reduce in some way a safety margin, but wilere the results of the change are clearly within all acceptance criteria with respect to the system or component specified in the standard review plan. (e.g., a change resulting from the application of a small refinement of a previously used calculational model or design method). This proposed amendment does not involve a significant relaxation of the criteria used to establish safety limits, a significant relaxation of the bases fbr the limiting safety system settings or a significant relaxation of the bases for the limiting conditions for operations. Therefore, based on the guidance provided in the Federal Register and the criteria established in 10 CFR 50.92(c), the proposed change does not constitute a significant hazards consideration.  ;

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l A'ITACHMENT D ENVIRONMENTAL ASSESSMENT STATEMENT APPLICABILITY REVIEW l i

1 Commonwealth Edison has evaluated the proposed amendment against the criteria l for identification oflicensing and regulatory actions requiring environmental assessment in accordance with 10 CFR Part 51.21. It has been determined that the proposed changes meet the criteria for categorical exclusion as provided for under  :

10 CFR Part 51.22(c)(9). This conclusion has been determined because the changes requested do not pose significant hazards considerations or do not involve a significant increase in the amounts, and no significant changes in the types of any effluents that may be released off-site. Additionally, this request does not involve a significant increase in individual or cumulative occupational radiation exposure.

k k:inla\lasalle\keerfisw.wpf21 1

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9 ATTACHMENT E CECO NED Nuclear Design Information Transmittal (NDIT) No. ElC-93-011-2, dated 6/3/94, summary report of the calculations that determine the ECCS system " Keep Filled" Alarm Ideal Setpoint and Technical Specification Allowable Values.

k:inla\lasalle\keepfisw.wpf22 i

CHRON#

Exhibit A 209886 esc-os-si.s

. Revision 0 page1ot2 CECO NED NUCLEAR DESIGN INFORMATION TRANSMTITAL (NDIT) m SArraf RELATED NDIT NO. EIC-93-011-2 o NON-SAFETY RELATED PAGE 1 OF 1 SUBJECT LaSalle Station Units 1 & 2 - ECCS System " Keep Filled" Alarm Ideal Setpoint and Tech Specification Allowable Value SENT TO (Name/ Dept.) J. Abel- SEC Manager, LaSalle County Station DISTRIBUTION R. Shields (1/0) M. Cray (1/1) R. Ayer (1/1)

T. Hammerich (1/0) G. Swihart (1/1) D. Sharko (1/1)

J. Lockwood (1/0) E. Seckinger (1/1) M. Tennyson G. Wagner (1/1)

(1/0) J. Miller (1/1)

DESCRIFFION OF NUCLEAR DESIGN INFORMATION AND PURPOSE OF ISSUANCE.

At the request of Gerald Swihart (Reg. Assuraace, LaSalle Station), I&C has evaluated the errors associated with the ECCS " Keep Filled" Alarm System Instrumentation. The purpose of this evaluatica was to determine a new Analytical Limit, new setpoint, and an associated Tech Spec Allowable Value for these loops. This analysis applies at normal operating conditions, for the following instruments; LPCI - A: 1(2)-E12-N512-A 1(2)-E21-R500 LPCI - B: 1(2)-E12-N512-B 1(2)-E12-R510 LPCI - C: 1(2)-E12-N512-C 1(2)-E12-R510 LPCS: 1(2)-E21-N005-B 1(2)-E21-R500 HPCS: 1(2)-E22-N013 1(2)-E22-R500 RCIC: 1(2)-E51-N034 1(2)-E51-R501 This revision incorporates a set of recommended Published Tech. Spec. Allowable Values referenced to the pump discharge no721e centerline.

This NDIT transmits the attached error analysis summary report which provides 1) the detailed of the loop accuracy calculation,2) associated Measurement & Test Equipment, used for normal lo calibration, 3) the assumptions, references and design inputs that provide input to the calculation.

V. R. SHAH (S&S) D. L. RAHN (S&S)

Pt E. A. Kaczmarski r (PRINT) Reviewer (PRINT) Approver (PRINT) m csis%. bdQ ec,/oshy sqVA s-s-n

$lgnaturt/Date Signature /Date Sifnitutt/Date STATUS OF INFORMATION: m APPROVED FOR USE a PRELIMINARY web r ,=s a eine puty etc. 4 ---. y n of s.ch i. form.m.m.  : a a. es puty = w e. acurny, c.=,s.m== ., -frmsms mr.

NDIT SOURCE DOCUMENT (S) NED-I-EIC-0153 Rev. I NED I-EIC-0156 Rev. I NED-I-EIC-0154 Rev.1 NED-I-EIC4157 Rev. I NED-I-EIC-0155 Rev.1 NED-I-EIC-0158 Rev.1 QF 51.M(8) l

. .~ - ..

4 ATTACHMENT TO NDIT EIC-93 011-2 Page 1 Cf 18 l LASALLE STATION - UNFT 1 & 2 ECCS SYSTEM " KEEP FELED" ALARM i IDEAL SLTPODfr AND TECH SPEC ALLOWABLE VALUE SYSTEM CALCULATION NC. .

INSTRUMEPfr NO. '

LPCI - A NED I EIC-0153 (Rw.1) 1(2)-E12 N512-A 1(2)-E21-R500 LPCI- B NED-I-EIC-0154 (Rw.1) 1(2)-E12-N512-B 1(2)-E12-R510 LPCI - C NED-I EIC 0155 (Rw.1) 1(2)-E12-N512-C 1(2)-E12-R510 LPCS NED-I-EIC 0156 (Rw.1) 1(2)-E21-N005-B 1(2)-E21-R500 HPCS NED-I-EIC4157 (Rw.1) 1(2)-E22-N013 1(2)-E22-R500 RCIC NED-I-EIC-0158 (Rw.1) 1(2)-E51-N034 1(2)-E51 R501.

'the results prwuled in the table 'A'should be included in the LaSella Caumey Seenom Survedlance Procedures for *he ECCS

' Keep Filled Alarm

• pressure switches. This results includes the head conocnos taeacassed with the ECCS 'Ecop Filled Alarm System.

TABLE "A" ECCS r.iaa.a.a uh C- . , ". -

8% em M i

" Keep Analytical Tech Spec Tech Spec CaMbration Discharge Aemptance Filled" Lipiit ABowshie A5owable Vahse Satpoint Pressure Criteria Alann at the Value at the Pimmy at the Switch Indic=*iam for System Switch at the Switch Discharge (PSIG) Erwer Piany (PSIG) (PSIG) Centerline (PSIG) Discharge ,

(PSIG) Pressure Operating Survalligere (PSIG)

LPCI - A 41.7 42.1 41.0 48.3 4 i t.5 4

i$.818 56.0 LPCI B 38.4 38.8 38.5 45.0 4

• 1.5 i5.318 57.0 LPCI - C 45.4 45.8 45.0 52.0 e t1.5 i5.818 57.0 LPCS 44.7 45.1 45.5 51.3 e it.5 t5.$18 56.0 HPCS 42.2 42.8 42.5 51.7 e it.5 i5.818 57.0 RCIC 28.9 29.5 29.0 38.14 it.0 +5.818 43.1 t

. - - . . . = . .

ATTACHMENT TO NDIT EIC-93-011-2 Page 2 cf 18 LAS/LLE STATION - UNFT 1 & 2 ECCS S13 TEM " KEEP HLLED" ALARM IDEAL SETPODff AND TECH SPEC ALLOWABLE VALUE NED CALCULATION NO: NED-I EIC-0153. Rev.1 PROCEDURE: LIS-RH 1(2)16-A (Rev. 0)

TITLE: LOS-LP-Q1 (Rev. 22)

RHR Pmnp 1(2)A Discharge High/Imv Low Pressure Core Spray Pressure Refuel Calibration System Inservice Test For Operaung Conditions 1,2,3,4, and 5.

INSTRUMENT NO: 1(2)-E12-N512 A 1(2)-E21-R500 MANUFACTURER: STATIC-O-RING ASHCROFT MODEL NO: 4N6-B45-NX-C1A-JTITX7 1279 CALCULATED ANALYTICAL LIMIT: 41.7 PSIG (At the Switch)

PRESSURE INDICATOR SWITCH (2) E12-N512A EXISTING LIS VALUE RECOMMEND @llS_YADIE CALIBRATED RANGE: 4 to 75 PSIG 4 to 75 PSIG CALIBRATED TOLERANCE: i 1.5 PSIG i 1.5 PSIG CALIBRATION FREQUENCY: Every Refuehag Octage (18 Months) Every Refuehag Outage (18 Monti.s)

CALIB. FREQ. LATE FACTOR: 25% of calibration frequency 25% of calibranon frequency CALIBRATION SETPOINT:

58.5 PSIG 4 (Does taa Include Head 48.3 PSIG 4 (At the Switch)

Correction) 47.0 PSIG 4 (At the Panp)

TECH. SPEC. ALLOWABLE VALUE: 55 PSIG (Does not Include Head 42.1 PSIG (At the Switch)  !

Correction) 41.0 PSIG (At the Pump)

DISCHARGE PRESSURE INDICATOR 1(2)-E21 R500 EXISTING LOS VALUE CALIBRATED RANGE: 0 to 100 PSIG CALIBRATED TOLERANCE: i 1.0 PSIG CALIBRATION FREQUENCY: Ever) 'nfueling Outage (18 Mondis))

CALIB. FREQ. LATE FACTOR: 25% of calibration frequency CALCULATED DISCHARGE PRESSURE INDICATION ERROR: i5.818 PSIG CALCULATED MINIMUM ACCEPTANCE CRITERIA FOR PUMP DISCHARGE PRESSURE: 56.0 PSIG (CONTINUED NEXT PAGE)

ATTACHMENT TO NDIT EIC-93-011-2 Page 3 of 18 LASALLE STATION UNIT 1 & 2 ECCS SYSTEM " KEEP FILLED" ALARM IDEAL SETPOINT AND TECH SPEC ALLOWABLE VALUE 1 (CONTINUED PROM PREVIOUS PAGE)

NED CALCULATION NO: NED-I-EIC-0153, Rev.1 PROCEDURE: US-RH-1(2)l6-A (Rev. 2) LOS-LP-Q1 (Rev. 22)

TITLE: RHR Pump 1(2)A Discharge High/Imv Low Pressure Core Spray Pressure Refuel Calibraten System Insemco Test For Operating ,

Conditions 1,2,3,4, and 5.

MEASUREMENT & TEST EQUIPMENT (M&TE) REQUIREMENTS ANALOG PRESSURE GAUGE f(21-E12-N-512-A Manufacturer: Heise Mensor Model CMM 2455 Range: 0 to 100 PSIG 0 to 100 PTJG Scale Graduation: 0.1 PSIG 0.1 PSIG Calibration Accurney: 2 0.2 PSIG 0.2 PSIG 1(21-E21 R500 Manufacturer.- Heise Mansor Model CMM 2455 Range: 0 to 200 PSIG 0 to 200 P!7JG ,

Scale Graduation: 0.2 PSIG 0.2 PSIG .,

Calibrarien Accuit.cy: i 0.4 PSIG i 0.4 PSIG i

ATTACHMENT TO NDIT EIC-93-011-2 Page 4 cf 18 LASALLE STATION - UNFr 1 & 2 ECCS SYSTEM " KEEP HLLED" ALARM I IDEAL SETPOINT AND TECH SPEC ALLOWABLE VALUE NED CALCULATION NO: NED-I-EIC 0154, Rev.1 PROCEDURE:

LIS-RH-1(2)16-B (Rev. 0) LOS-RH-Q1 (Rev. 23)

TITLE: RHR Pumps 1(2)B and C Discharge Hish/ Low RHR B&C Service Water Pressues Refuel Calibration System Operability and Inservice Test .

INSTRUMENT NO: 1(2)-E12-N512-B 1(2)-E12-R510 MANUFACTURER: STATIC-O-RING ASHCROFT MODEL NO: 4N6-B45-NX-CIA-DTTX7 1279 CALCULATED ANALYTICAL LIMIT: 38.4 PSIG (At the Switsch)

PRESSURE INDICA'IOR SWITCH 1(2)-E12-N512B EXETING LIS VALUE RECOMMENDED LIS VALUE CALIBRATED RANGE: 4 to 75 PSIG 4 to 75 PSIG CALIBRATED 'IOLERANCE: i 1.5 PSIG i 1.5 PSIG CALIBRATION FREQUENCY: Every Refueling Outage (18 Months) Every Refuehag Outage (18 Months)

CALIB. FREQ. LATE FACTOR: 25% of calibratmo frequency 25% of calibratson frequency CALIBRATION SETPOINT:

58.5 PSIG 4 (Does not Include Head 45.0 PSIG 4 (At the Switch)

Conecten) 44.6 PSIG & (At the Pump)

TECH. SPEC. ALLOWABLE VALUE: 55 PSIG (Does not Include Head 38.8 PSIG (At the Switch)

Conection) 38.5 PSIG (At the Pump)

DISCHARGE PRESSURE INDICATOR 1(2)-E12-R510 EXISTING LOS VALUE CALIBRATED RANGE: 0 to 100 PSIG CALIBRATED TOLERANCE: i 1.0 PSIG CALIBRATION FREQUENCY: Every Refueling Outage (18 Months)

CALIB. FREQ. LATE FACTOR: 25% of cahhutma frequency CALCULATED DISCHARGE PRESSURE INDICATION ERROR: 15.818 PSIG CALCULATED MINIMUM ACCEPTANCE CRITERIA FOR PUMP DISCHARGE PRESSURE: 57.0 PSIG (CONTINUED NEXT PAGE)

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ATTACHMENT 'ID NDIT EIC-93 011-2 Page 5 of 15

. g LASALLE STATION - UNIT 1 & 2 '

ECCS SYSTEM " KEEP Frr1Rn" ALARM I IDEAL SETPOINT AND TECH SPEC ALLOWABLE VALUE l

(CONTINUED FROM PREVIOUS PAGE)

NED CALCULATION NO: NED-I-EIC4154, Rev.1 PROCEDURE: LIS-RH 1(2)16-B (Rev. 0)

TITLE: LOS-RH-Q1 (Rev. 23) -

RHR Pumps 1(2)B and C Discharge High/Im RHR B&C Semce Water Pressure Refuel Calibration System Opernbdity and Inservice Test .

MEASUREMENT & TEST EQLUMENT (MATE) REQUIREMENTS ANALOG PRESSURE GAUGE 1(21.E12-N512-B Manufacturer: Heist Meesor Model CMM 2455 I Range: 0 to 100 PSIG 0 to 100 PSIG Scale Graduation: 0.1 PSIG 0.1 PSIO Calibration Accurney: i 0.2 PSIG i 0.2 PSIG 1(21-E12-R510 ,

l Manufacturer: Heise Mansor Model CMM 2455 Range: 0 to 200 PSIG 0 to 200 PSIG Scale Graduation: 0.2 PSIG 0.2 PSIG ,

Calibration Accuracy: i 0.4 PSIG i 0.4 PSIG

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ATTACHMENT 'IO NDIT EIC-93-011-2 Page 6 cf 16 LASALLE STATION - UNTT 1 & 2 ECCS SYSTEM " KEEP Frre ALARM I IDEAL SETPOINT AND TECH SPEC ALLOWARLE VALUE }

NED CALCULATION NO: NED-I-EIC-0155, Rev.1 PROCEDURE: LIS-RH-1(2)16-B (Rev. 0)

TITLE: LOS-RH-Q1 (Rev. 23)

RHR Pmeps 1(2)B and C Discharge High/ Low RHR B&C Service Water Preseme Refuel Calibracon System Operabdity and Inservice Test . ,

INSTRUMENT NO: 1(2)-E12 N512-C 1(2)-E12-R510 MANUFACTURER: STATIC-O RING l ASHCROFT MODEL NO: 4N6-B45-NX-CIA-FITX7 )

1279 CALCULATED ANALYTICALLIMIT: 45.4 PSIG (At the Switch)

PRESSURE INDICATOR SWITCH 1(2)-E12-N512C Exm c4G T It VALUE RECOMMENDED LIS VALUE i CALIBRATED RANGE: 4 to 75 PSIG 4 to 75 PSIG CALIBRATED TOLERANCE: i 1,5 PSIG 1.5 PSIG CALIBRATION FREQUENCY:

Every Refuehag Outage (18 Months) Every Refuehag Outage (18 Months)

CALIB. FREQ. LATE FACTOR: 25% of calibranon frequency CALIBRATION SETPOINT: 25% of calibrenos frequency 58.5 PSIG 6 (Does not Include Head 52.0 PSIG 6 (At the Switch)

Correence) 50.8 PSIG & (At the Panp)

TECH. SPEC. ALLOWABLE VALUE: 55 PSIG (Does notInclude Hand i

45.8 PSIG (At the Switch)

Correenon) 45.6 PSIG (At the Pianp)

DISCHARGE PRESSURE INDICATOR I(2)-E12-R510 EXISTING LOS VALUE ,

CALIBRATED RANGE: 0 to 100 PSIG CALIBRATED TOLERANCE: i 1.0 PSIG CALIBRA110N FREQUENCY: Every Refueling Outage (18 Months)

CALIB. FREQ. LATE FACTOR: 25% of calibration frequency CALCULATED DISCHARGE PRESSURE INDICATION ERROR: i5.818 PSIG CALCULATED MINIMUM ACCEPTANCE CRTTERIA FOR PUMP DISCHARGE PRESSURE: 57.0 PSIG l

(CONTINUED NEXT PAGE)

ATTACHMENT TO NDIT EIC-93-011-2 Page 7 cf 18 LASALLE STATION - UNIT 1 & 2 ECCS SYSTEM " KEEP FffLN ALARM IDEAL SETPOINT AND TECH SPEC ALLOWABLE VALUE (CONTINUED FROM PREVIOUS PAGE)

NED CALCULATION NO: NED-I-EIC-0155, Rev.1 PROCEDURE: LIS-RH 1(2)l6-B (Rev. 0)

TITLE: LOS-RH-Q1 (Rev. 23)

RHR Pumps 1(2)B and C Dicharge High/Imv RHR B&C Service Water Pnesure Refuel Calibration System Operability and Inservice Test .

MEASUREMENT & TEST EQUIPMENT (MATE) REQUIREMENTS ANALOG PRESSURE GAUGE 1(21-E12-N512-C Manufacturer: Heise Mansor Model CMM 2455 Range: 0 to 100 PSIG G to 100 PSIG Scale Graduation: 0.1 PSIG 0.1 PSIG Calibration Accuracy: i 0.2 PSIG i 0.2 PSIG

, i 1(2)-E12-R510 1

Manufacturer: Heise Mensor Model CMM 2455  !

Range: i 0 to 200 PSIG 0 to 200 PSIG i Scale Graduation: 0.2 PSIG 0.2 PSIG ,

Calibration Accuracy: i 0 4 PSIG t 0.4 PSIG l

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ATTACHMENT TO NDIT EIC-93-011-2 Page 8 cf 18 LASALLE STATION - UNrr 1 & 2 ECCS SYSTEM " KEEP HLLED" ALARM IDEAL SETPODff AND TECII SPEC ALLOWABLE VALUE i

NED CALCULATION NO: NED-I-EIC-0156, Iwv.1 PROCEDURE: LIS LP-1(2)08 (Rev. 2)

TITLE: LOS-LP-Q1 (Rev. 22)

LPCS Pmnps High/Imv Discharge Low Pressure Core Spray Pressure Alarm Refuel Calibration System Inservice Test For Operstmg Conditions 1,2,3,4, and 5.

INSTRUMENT NO: 1(2)-E21 N005-B 1(2)-E21 R500 MANUFACTURER: STATIC-O-RING ASHCROFT MODEL NO: 4N6-B45-NX CIA-HTTX7 1279 i

CALCULATED ANALYTICAL LIMTT: 44.7 PSIG (At the Switch)

PRESSURE INDICATOR SWITCH 1(2) E21-N005 B EXISTING LIS VALUE RECOMMENDED LIS VALUE CALIBRATED RANGE: 4 to 75 PSIG 4 to 75 PSIG CALIBRATED TOLERANCE: i 1.5 PSIG i 1.5 PSIG CALIBRATION FREQUENCY: Every Refueling Outage (18 Months) Every Refueling Outage (18 Months)

CALIB. FREQ. LATE FACTOR: 25% of calibranon frequency 25% ofcalibranon frequency CALIBRATION SETPOINT:

58.5 PSIG 4 (Does not Include Head 51.3 PSIG 4 (At the Switch)

Correction) 51.6 PSIG 4 (At the Pump)

TECH. SPEC. ALLOWABLE VALUE: 55 PSIG (Does not Include Head 45.1 PSIG ( At the Switch)

Correction) 45.5 PSIG (At the Pump)

DISCHARGE PRESSURE INDICATOR I(2) E21 R500 EXISTING LOS VALUE CALIBRATED RANGE: 0 to 100 PSIG CALIBRATED TOLERANCE: i 1.0 PSIG CALIBRATION FREQUENCY: Eve y Refueling Outage (18 Months)

CALIB. FREQ. LATE FACTOR: 25% of calibration frequency CALCULATED DISCHARGE PRESSURE INDICATION ERROR: i5.818 PSIG CALCULATED MINIMUM ACCEPTANCE CRITERIA FOR PUMP DISCHARGE PRESSURE: 56.0 PSIG I

(CONTINUED NEXT PAGE)

ATTACHMENT TO NDIT EIC-93-011-2 Page 9 of 18 ,

LASALLE STATION - UNIT I & 2 ECCS SYSTEM " KEEP Frr1rn" ALARM IDEAL SETPOINT AND TECH SPEC ALLOWABLE VALUE (CONTINUED FROM PREVIOUS PAGE)

NED CALCULATION NO: NED-I-EIC-0156, Rev.1 PROCEDURE: LIS-LP-1(2)08 (Rav. 2)

TITLE: LOS-LP-Q1 (Rev. 22)

LPCS Pumps High/Iaw Discharge I.aw Pressure Core Spray Pressure Alarm Refuel Calibration Systems Insemco Test For Operating Conditions 1,2,3,4, and 5.

MEASUREMENT & TEST EQUIPMENT (M&TE) REQUIREMENTS ANALOG PRESSURE GAUGE 1(21-E21-N005-B Manufacturer: Heise Mensor Model CMM 2455 Range: 0 to 100 PSIG 0 to 100 PSIG Scale Graduation: 0.1 PSIG 0.1 PSIG Calibration Accuracy: i 0.2 PSIG i 0.2 PSIG 1(2bE21-R500 Manufacturer: Heise Mansor Model CMM 2455 Range: 0 to 200 PSIG 0 to 200 PSIG Scale Graduation: 0.2 PSIG 0.2 PSIG -

Calibration Accuracy: i 0.4 PSIG i 0.4 PSIG

ATTACHMENT TO NDIT EIC-93-011-2 Page 10 of 18 LASALLE STATION - UNIT 1 & 2 ECCS SYSTEM " KEEP FILLED" ALARM IDEAL SETPODff AND TECH SPEC ALLOWABLE VALUE NED CALCULATION NO: NED-I-EIC-0157. Rev.1 PROCEDURE: US HP 1(2)09 (Rev. 2)

TITLE: LOS-HP-Q1 (Rev. 26)

HPCS Law Water lag Une HPCS System Operability Pressure Calibration and laservice Test.

INSTRUMENT NO: 1(2)-E22-N013 1(2)-E22 R500 MANUFACTURER: BARTON ASHCROFT MODEL NO: 288A 1279 CALCULATED ANALYTICAL LIMIT: 42.2 PSIG (At the Switch) i PRESSURE INDICATOR SWITCH 1(2)-E22-N013 EXISTING LIS VALUE RECOMMENDED LIS VALUE CAUBRATED RANGE: 0 to 100 PSIG 0 to 100 PSIG CAUBRATED TOLERANCE: i 1.5 PSIG t 1.5 PSIG CAUBRATION FREQUENCY: Every Refueling Outage (18 Months) Every Refuehag Outage (18 Months)

CALIB. FREQ. LATE FACTOR: 25 % of calibratio=, frequency 25% of calibration frequency CALI'BRATION SETPOINT:

68.25 PSIG 4 (Includes 3.75 PSIG of 51.7 PSIG & (At the Switch)

Head Correction) 51.1 PSIG 4 (At the Pump)

TECH. SPEC. ALLOWABLE VALUE:

66.75 PSIG (Includes 3.75 PSIG of 42.8 PSIG (At the Switch)

Head Correction) 42.5 PSIG (At the Pump)

DISCHARGE PRESSURE INDICATOR 1(2)-E22 R500 EXISTING LOS VALUE CAUBRATED RANGE: 0 to 100 PSIG CALIBRATED TOLERANCE: i 1.0 PSIG CAUBRATION FREQUENCY: Every Refueling Ourage (18 Months)

CAUB. FREQ. LATE FACTOR: 25% of calibration frequency CALCULATED DISCHARGE PRESSURE INDICATION ERP.OR: i5.818 PSIG CALCULATED MINIMUM ACCEPTANCE CRITERIA FOR PUMP DISCHARGE PRESSURE: 57.0 PSIG (CONTINUED NEXT PAGE)

ATTACHMENT TO NDIT EIC-93-011-2 Page 11 cf 18 LASALLE STATION - UNIT 1 & 2 ECCS SYSTEM " KEEP FILLED" ALARM IDEAL SETPOINT AND TECH SPEC ALLOWABLE VALUE (CONTINUED FROM PREVIOUS PAGE)

NED CALCULATION NO: NED-I EIC-0157. Rev.1 PROCEDURE: LIS-HP-I(2)09 (Rev. 2)

TITLE: LOS-HP-Q1 (Rev. 26)

HPCS I.aw Water Iag Line HPCS System Operability Pmesure Calibration and Insemco Test.

MEASUREMENT & TEST EQUIPMENT (MATE) REQUIREMENTS ANALOG PRESSURE GAUGE 1(21-F77-N013 & 1(2).F77-R500 Manufacturer: Heise Mansor Model CMM 2455 Range: 0 to 200 PSIG 0 to 200 PSIG Scale Graduation: 0.2 PSIG 0.2 PSIO Calibration Accuracy: i 0.4 PSIO to.4 PSIO

• 1 ATTACHMENT TO NDIT EIC-93-411-2 Page 12 cf 18 LASALLE STATION - UNIT 1 & 2 i ECCS SYSTEM " KEEP MLLED" ALARM IDEAL SETPODir AND TECH SPEC ALLOWABLE VALUE l

1 NED CALCULATION NO: NED-I-EIC 0158, Rev.1 PROCEDURE: LIS RI-1(2)13 (Rev. 0)

TITLE: LOS-RI-Q1 (Rev. 21)

RCIC Pump Water lag Line RCIC System Pump Opershility Low Pressure Calibration and Valve Inservice Teste in Conditione 1,2, and 3.

INSTRUMENT NO: 1(2)-E51 NO34 1(2)-E51 R501 MANUFACTURER: ROBERTSHAW ASHCROFT MODEL NO: SP-222-C09 1279 CALCULATED ANALYTICAL LIMFT: 28.9 PSIG (At the Switch)

PRESSURE INDICATOR SWITCH 1(2)-E51-N034 EXISTING LIS VALUE RECOMMENDED LIS VALUE CALIBRATED RANGE: 0 to 100 PSIG 0 to 100 PSIG CALIBRATED TOLERANCE: i 1.0 PSIG i 1.0 PSIG CALIBRATION FREQUENCY: Every Refuehng Outage (18 Months) Every Refuelag Outage (18 Months)

CALIB. FREQ. LATE FACTOR: 25% of calibration frequency 25% of calibration frequency CALIBRATION SETPOINT: 63 PSIG 4 (Does not Include Head 38.1 PSIG & (At the Switch)

Correction.) 37.5 PSIG 4 (At the Pump)

TECH. SPEC. ALLOWABLE VALUE: 62 PSIG (Does not Include Head 29.5 PSIG (At the Switch)

Correction.) 29.0 PSIG (At the Pump)

DISCHARGE PRESSURE INDICATOR 1(2) E51 R501 EXISTING LOS VALUE '

CALIBRATED RANGE: ,

0 to 100 PSIG '

CALIBRATED TOLERANCE: i 1.0 PSIG CALIBRATION FREQUENCY: Every Refueling Outage (18 Months)

CALIB. FREQ. LATE FACTOR: 25% of calibration frequency CALCULATED DISCHARGE .

PRESSURE INDICATION ERROR: 5.818 PSIG CALCULATED MINIMUM ACCEPTANCE CRITERIA FOR PUMP DISCHARGE PRESSURE: 43.1 PSIG (CONTINUED NEXT PAGE)

1 j ATTACHMENT TO NDIT EIC-93-011-2 Page 13 of 18 ,

LASALLE STATION - UNIT 1 & 2 ECCS SYSTEM " KEEP FrrJJ'n" ALARM IDEAL SETPOINT AND TECH SPEC ALLOWABLE VALUE 1

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(CONTINUED FROM PREVIOUS PAGE)

NED CALCULATION N0: NED-I EIC-0158. Rev.1 PROCEDURE: LIS.RI-1(2)13 (Rev. 0) LOS-RI-Q1 (Rev. 21)

TITLE: RCIC Putnp Water Lag Line RCIC System Pump Operability low Pressure Calibrance and Valve Inservice Tests ,

in Conditions 1,2, and 3.

MEASUREMENT & TEST EQUIPMENT (MATE) REQUIREMENTS ANALOG PRESSURE GAUGE 1(21-E51-NO34 & 1(21-E51-R501 Manufacturer: Heiss Mansor Model CMM 2455 Range: 0 to 200 PSIG 0 to 200 PSIG Scale Graduatica: 0.2 PSIG 0.2 PSIG Calibration Accuracy: i 0.4 PSIG to.4 PSIG t

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c ATTACHMENT TO NDIT EIC-93-011-2 Page 14 cf 18 LASALLE STATION - UNFT 1 & 2 ECCS SYSTEM "XEEP FILLED" ALARM IDEAL SIfrPODir AND TECH SPEC ALLOWABLE VA".UE ERROR ANALYSIS REFERENCES

1. ANSI /ISA-S67.04-1988, "Seapoints for Nuclear Safety Related Instr ====e= tion.*

2. TID-E/I&C 20, ' Basis for Analysis ofInstrument Channel Seepoint Error & Loop A iracy", Rev. O, dated 4/6/92.

3. TID-E/I&C-10. " Analysis ofInstrument cha==al Setpoint Error and Instrussent Imp Accuracy" Rev. O, dated 4/6/92.

4. LaSalle Station Instrument Survallanca Procedures:

LPCI-A US-RH-116A, 216A, Rev. O, dated January 10,1992, " Unit 1(2) RHR Pumps 1(2)A Discharge High/ Low Pressure Refuel Calibrahon.'

LOS-LP-Q1, Rev. 22, dated August 18,1992, " Unit 1(2) Law Pressure Core Spray Systema Inservice Test for Operstm's Conditions 1,2,3,4 and 5." l LPCI-B & LPCI-C LIS-RH-1(2)168, Rev. O dated January 10,1992, " Unit 1(2) RHR Pumps 1(2)B and C Discharge High/ Low Pressure Refuel Calibration.'

LOS-RH-Q1, Rev. 23, dated Dar===har 11,1991, " Unit 1(2) B RHR & C RHR Service Water System Operability and Inservice Test.*

LECS LIS-LP-1(2)08, Rev. 2, deled November 1,1990, " Unit 1(2) LPCS Pumps High/Im Discharge Pressure Alarm Refuel Calibranon."

LOS-LP-Q1, Rev, 22, dated August 18,1992, ' Unit 1(2) Low Pressure Core Spray System Inservice Test for Operating Conditions 1,2,3,4 and 5."

HECS LIS-HP-1(2)09, (Rev.2), dated October 29,1991, " Unit 1(2) HPCS Low Water lag Une Pressure Calibration

• LOS-HP-Q1, Rev. 26, dated January 30,1992, " Unit 1(2) High Pressure Core Spray System Operability And '

Inservice Test.'

ECLC LIS-RI 1(2)13, Rev. 0, ' Unit 1(2) RCIC Pump Water Lag Une Low Pressure Calibranon."

LOS-RI-Q3, Rev. 21 dated April 1,1992, " Reactor Core Isolation Cooling (RCIC) System Pump Operability And Valve Inservice Tests In Conditions 1,2, and 3.*

1

5. SOR Inc., Form 216, Revised 3/90.

6. TIT Barton Product Bulletin 288A/289A-4,1987

7. Acragage Corp., SP-200 Series Pressure Switch Bulletin Q-3412A, dated 8/90.

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B ATTACHMENT 10 NDIT EIC-93411-2 Pag) 15 cf 18 a

LASALLE STATION - UNIT 1 & 2 ECCS SYSTEM " KEEP FILLED" ALARM IDf1 L SETFOINT AND TECH SPEC ALLOWABLE VALUE ERROR ANALYSIS REFERENCES (enatammad)

8. Ashcroft Pressure Gauges, Bulletin DU-1, Rev. 3/80.

9. LaSalle County Station Updated Final Safety Analysis Report, " Chapter 3.11, Envuonmental Design of Mechanical and Electrical Equipment", Rev.3, April 1987.

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11. LaSalle County Station Tarhaw=1 Specification, A===A===* No. 68, dated 07/19/89, Page 3/4 0-2. " Surveillance Requirements, Paragraph 4.0.2"

14. ASHCROFT Pressure Gau8o, Bullete DU-1. dated 12/91.

15. ASME Steam Tables dated 1967, provulas the following converman froma Pt. of W.C. to PSIG.

Ft. Of W.C. X 0.43352 = PSIG 16.

Commonwealth FAman Co., ' Report ofInvestigmica of Static O-Ring Diffierential Pressee Switches, f 22=11a County Station", Section 3, 'SOR Differential Switch Evaluation", dated 08/01/86

17. Sargent & Lundy single line paping drawing depsetag 'as built

• field arrangensents Dms.l Ellig Revision Deled Draxi Eilf Barama Dased

• M-839 10 AC 3/26/93 M-939 10 AD 5/15/92

• M-839 12 AF 7/29/91 M-939 12 Y 7/13/89

• M-839 11 AR 9/21/88 M 939 11 AD 7/13/88

• M-837 3 AJ 5/27/93 M-937 3 P 4/14/89 i

• M-838 2 AJ 2/14/93 M 938 2 AC 6/24/92

• M 844 4 AM 5/27/93 M 944 4 W 7/22/92 k

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,. ATTACHMENT TO NDIT EIC-93-011-2 Page 16 ef 18 LASALLE STATION - UNIT 1 & 2 ECCS SYSTEM " KEEP F1LLED* ALARM IDEAL SETPOINT AND TECH SPEC ALLOWABLE VALUE ERROR ANALYSIS DESIGNINPUTS 1.

Elevation Measurements for ECCS 'Kasp Filled Alarm" Pressure Switches and system High Points, date 28,1987 by Mr. D. Lyon and Mr. R. Rohrer (Design Input 1 has been used for System Hiah Point Elev

2. Trend Data as follows, LOS-LP-Q1, of Quarterly inspacham Results for pump difforential pressure, taken 6/21/88 through 8/17/92 fo and 7/12/88 through 10/13/92 for 2E21-C002.

LOS-RH-Q1, of Quarterly T==parha= Results for pump differential pressure, taken 5/26/88 through 8/10/92 C003 and 7/20/88 through 10/20/92 for 2E12-C003.

LOS-HP-Q1, of Quarterly faapar+=a= Results for pump differential pressure, taken 10/3/88 through 8/31/

C003 and 8/19/88 through 9/29/92 for 2E22-C003.

LOS-RI-Q3 1(2)A/QS-1(2)A, ofQuarterly fa=parhaa Results forpump difIssential pressure, taken 7/16/

for 1E51-C003 and 7/29/88 through 9/11/92 for 2E51 C003, i

l 3.

Record of Telephone Conversation between V. R. Shah of Signals & "' ; -i , Inc. and D. Spencer & M of LaSalle Station Tech Staff Department regarding

• Keeping track of ambient "

- - . of reactor building

• dated

)

1/07/93. ,

4.

A Facsimile from Mr. Bob Davidson of SOR, Inc. to V. Shah of Signals & * ' ; _/ , Inc., transmitting the Pressure Switches

• Temperature Influence Test Results*, dated 01/06/93.

5.

The following printed data sheets froen Stone & Webster engmeenng Corp. Instruenset Database Progra County Station.

1(2)-E12-N512 A dated 12/4/92 '1(2)-E21-R500 dated 12/4/92 1(2)-E12-N512-B deced 12/4/92 1(2)-E12 R510 dated 12/4/92 1(2)-E12-N512 C dated 12/4/92. 1(2)-E12-R$10 dated 12/4/92 1(2)-E21-N005-B doesd 12/4/92. 1(2)-E21-R500 dated 12/4/92 1(2)-E22-N013 dated 12/4/92. 1(2)-E22-R500 deced 12/4/92 1(2FE51 N034 dated 12/4/92. 1(2)-E51-R501 dated 12/4/92 6.

Basic Statistics: A Modern Approach by Morris Hamburg, Pubhahed by Harcourt Bruce Jovanovich, Inc the formula 3.9 for sample standard deviation on page 64.

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ATTACHMENT 10 NDIT EIC-93-011-2 Page 17 of 18 ,

LASALLE STATION - UNIT I & 2 ECCS SYSTEM " KEEP PILLED" ALARM IDEAL SETPOINT AND TECH SPEC ALLOWABLE VALUE ERROR ANALYSIS ASSUMPTIONS 1.

Published instrument and MATE vendor specifiestacas are ca==laned to be 2 sigma values unless specific information is available to indacase onberwise.

2. Only normal envir===neal conditions have been consulared unless specifically identified. Temperature, radiation and humidity errors, when avadable from the manufacturer, wese evalumsed with respect to the nonnal conditions speciRed in the I.aSalle Station EQ zones. The EQ aone requiremanes for each instnument was ah*==ad from Design Input 5 and the LaSalle Station EQ Zoos maps (Reference 11). Seessic Errors have not been evalussed, as amanne events are not considered under nonnal operanng conditions.

3. Temperature, humidity and pressure errors have bees !E- ;i _- " when provided by the ===nbe=rer. Otherwise, these errors are ==imed to be included within the manufacturer's reference accuracy , W =

4. Drift error has been assaned to be 15 of span per year, unless specined oeberwise by the maanks=rer. The calculated drift error will be adjussed for survedlance inservals of grosser or lammar length based as calibranca frequency.

5. Head correctices have been ovatussed and '=+ ,~.- ^ 'in abis studywhere applicable. Tap and mammangelevances were obtained from Design Input 5. Head corr =+ia== derived from walkdown data have basa used in the calail=han Density corrections have been !s-- i ' into abe specific instrumsat hand correction using abs assumed =ian=== sverage ambient temperature of 85'F. (Design Input 3) 6.

The only temperature induced MATE errors that were evaluated were those speci5ed by abe manufacturer for a specific model number. His methodology used abs sonet conservative error evaluation by ? ' .g the Edi range of ambient ,

temperature change as specified for the ;;--M EQ aans.

It is ==imed that the M&TE listed is calibrated to the requued ====bh=e's r=ca====d=*ia== & within tbs manufacturer's required envuommental conditions. Temperature related errors are based on the difference between the

(

manufacture's special calibrance temperature and the worst case temperature at wMch tbs device is used.

7.

Instrument reference accuracy was ah*===d from the publiebed ===nbhwers' accuracy specifications.

8.

The use of particular M&TE as specified in the appixable US or by LaSalle IM Department was assened even though the specified M&TE scale umies did not always exactly immach the LIS data sheet enginsenag units. It has been ==imad that the IM using the MATE would make correct and accurses convermans where necessary.

9. The following assumption is made with regard to M&lTs accuracy:

Pressure gauges: A value equal to 2 times the ===d=e*==er's specified reference accuracy was ====ad to be a 2. sigma value under plant opersang conditions.

10.

Evaluation of M&11! enere is based on the assmapnon that the test eqmpment lisend is used. Use of test equipment less accurate than that previcuely listed will require evaluation of the effiset upon the calenl=han readts.

11.

Process measurement errors for nonnal operenng conditions were assumed to include only head correenon.

12. Instrument sensing lines are ====ad to be cold and dead. ended. Derefore, process fluid - ,---a-e in contact with the instrunnent is ==me==d to be at ambient " - f e-w.

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ATTACHMENT TO NDIT EIC-93-011-2 Page 18 cf 18 '

e fantJR STATION - UNIT 1 & 2 ECCS SYSTEM " KEEP HLLED" ALARM IDEAL SETPOINT AND TECIISPEC ALLOWABLE VALUE ERROR ANALYSIS ASSUMFTIONS Pand==d) 13.

Radiation induced errors associated widimormal envuna-*= heve been incorporated when provuled by the manu Otherwise, these enors are assumed to be small and capable of being adjusted out each time the instnunset is re-calibrated. Therefore, unless speci5cally published by the equipment vendor, the normal radiation errors can be =

to be included within tbs insinunset drift related errors.

14.

Calibration Tolerance was obtained fiosa the associated IJS calibration data sheet.

15.

Based on Assenption 6, it is assuased that the calibrataan standard ac ,1aracy error of MATE is neglig the other error tenas.

16.

When detenmmag new calibration eespoints, the margin (MAR) that accounts for unknown companan uncertainties is calculated as 0.5% of the process measurement span.

17.

Since cold water has a higher density than hot water, for conservatiam, the analytical limit is al=la*M at 39.2*F. i 18.

Whsm the instnunset locanon is not in a dseignated EQ Zone, the envuosumantal nonnat operatag conditions ar to be a temperanare range of 40' to 150*F, pressure of 14.7 PSIA, re& anon of 1.0 x 10' (TID over 40 years humidity of 20 to 905.

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