ML20087G916

Proposed Tech Specs Re Administrative Change to Afs LCO 3.7.1.2 Action a for License NPF-3

ML20087G916
Person / Time
Site:	Davis Besse
Issue date:	04/10/1995
From:	CENTERIOR ENERGY
To:
Shared Package
ML20087G907	List: ML20087G904 ML20087G916
References
NUDOCS 9504180046
Download: ML20087G916 (11)

Text

. ,

.LAR 96-0011 )

Page 9, .]

PLANT S STEMS

' AUXILIARY FEE 0 WATER SYSTEM

. LIMITING CONDITION FOR OPERATION 3.7.1.2 Two trains of auxiliary feedwater, each consisting of an auxiliary feedwater pump and associated flow path to both steam generators. shall be OPERABLE.

APPLICABILITY: MODES 1. 2, and 3. -

ACTION: ,

a. With one train of auxiliary feedwater inoperable to either y@gg steam generator within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or [Q.berestore the inoperable in H0T SHUTDOWN train within theto OPERABLE next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. s';a';us

b. With any Auxiliary Feed Pump Turbine Inlet Steam Pressure Interlocks Woperable, restore the inoperable interlocks to OPERABLE status within 7 days or be in 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 />.

c. With steam generator inlet valve AF 599 or AF 608 closed. re-o mn the closed valve AF 599 or AF 608 within one hour or be in HOT STA40BY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and H0T SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ,

SURVEILLANCE REQUIREMENTS 4.7.1.2.1 Each Auxiliary Feedwater train shall be demonstrated OPERABLE: ,

$16l I@SEUS$'

c p' Aq..%;rwmma~

9 yy:..a , ; g gnwmmt&ggiRymm%

3;; : pqqg q Q ( 9 3 y ; ~-wrw~v YY MW

2. ^t le::t once per 92 d:y: On : 57?CCEPE0 TEST "?. SIS by:*

1.

"crifying that 0:churc st02:

differenti:T pr00 Of ?turbin0 driven 1970 p:1d enpu"; dev010p reticulation ? !~;; der  ;

the :^condary st^:: supply pressure 1: greater th:n 900 pri:. ::

"catur^d On P! SP 12B for pmp I 1 :nd o! SP 12? for 1 2.

The provi:10n Of Speci'ic:UOn '.0.' :re not applica:10 :u ;for entry into "0DE 2.

• When conducting tests of an auxiliary feedwater train in MODES 1, 2. and 3 which require local manual realignment of valves that make the train inoperable. the Motor Driven Feedwater Pump and its associated flow paths shall be OPERABLE per Specification 3.7.1.7 during the performance of this surveillance. If the Motor Driven Feedwater Pump or an associated flow path is inoperaDie, a dedicated individual shall be stationed at the realigned j auxiliary feedwater train's valves (in communication with the control room) able to restore the valves to normal system CPERABLE status.

DAVIS-BESSE UNIT 1 3/4 7-4 Amendment No. 96 Z22.23Z.Z93 9504180046 950410 PDR ADOCK 05000346  ;

P PDR i

.9

%;A " INFORMATION.0NI.1 PLANT SYSTEMS-SURVEILLANCE RE0UIREMENTS (Continued)

b. At least once per 31 days on a STAGGERED TEST BASIS by: l

1. Verifying that each valve (power operated or automatic) in the l flow path is in its correct position.

2. Verifying that all manual valves in the auxiliary feedwater pump l-suction and discharge lines that affect the system's capacity to deliver water to the steam generator are locked in their proper position.

3. VerifyingthatvalvesCW196,CW197,FW32,FW91andFW106arel closed.

c. At least once per 18 months bf: l 1 Verifying that each automatic valve in the flow path actuates to its correct position on a, Steam and Feedwater Rupture Control System actuation test signal.

2. Verifying that each pump starts automatically upon receipt of a Steam and Feedwater Rupture Control System actuation test signal.

The provisions of Specification 4.0.4 are not applicable for entry in MODE 3.

3. Verifying that there is a flow path from each auxiliary feedwater pump to both steam generators by pumping water from the Condensate Storage Tank with each pump to both steam generators.

The flow paths shall be verified by either steam generator level l change or Auxiliary Feedwater Safety Grade Flo.w Indication.

Verification of the Auxiliary Feedwater System's flow capacity is not required.

d. The Auxiliary Feed Pump Turbine SteL. Generator Level Contro1' System l shell be demonstrated OPERABLE by performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHANNEL CALIBRATION at least once per 18 months.

e. The Auxiliary Feed Pum) Suction Pressure Interlocks shall be l demonstrated OPERABLE >y performance of a CHANNEL FUNCTIONAL TEST at least once per 31. days, and a CHANNEL CALIBRATION at least once per 18 months.

DAVIS-BESSE, UNIT 1 3/4 7-5 Amendment No. A),E),P ,J//, J/J,193

m . - - - . . . _ ,

D'h*"

PLANT SYSTEMS INFORMATION ONI.Y- '

' SURVEILLANCE REQUIREMENTS (Continued)

f. After any modification or repair to the Auxiliary Feedwater System l that could affect the. system's capability to deliver water to the steam ,

generator, the affected flow path shall be demonstrated available as *

.follows:

If the modification or re 1.

each auxiliary feed pum)(pair s) associatedis' downstream with the affected offlow thepath test flow line shall pump water from tie Condensate Storage Tank to the steam .

generator (s) associated with the affected flow path; and the flow ,

path availability will be verified by steam generator icvel change or Auxiliary Feedwater Safety Grade Flow Indication.

4

2. If the modification or repair is upstream of the test flow line, the auxiliary feed pump shall pump water through the Auxiliary Feedwater System to the test flow line; and the flow )ath availability will be verified by flow indication in tie test flow line.* l This Surveillance Testing shall be performed prior to entering MODE 3 if .

the modification is made in MODES 4, 5 or 6. Verification of the Auxiliary Feedwater System's flow capacity is not required.

g._ Following each extended cold shutdown (>.30 days in MODE 5), by: j.

~

1. Verifyingthatthereisaflhipathfromeachauxiliaryfeedwater. .

pump to both steam generators by pumping Condensate Storage Tank water with'each pump to both steam generators. The tiow paths.

shall be verified by either steam generator level change or Auxiliary Feedwater Safety Grade Flow Indication. The provisions =

of Specification 4.0.4 are not applicable for. entry into MODE 3. ,

Verification of the Auxiliary Feedwater System's flow capacity is not required.

4.7.1.2.2 The Auxiliary Feed Pump T. dine Inlet steam Pressure Interlocks shall 4

be demonstrated OPERABLE when the steam line pressure is greater than 275 psig,- .

by >erformance of a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHAiNEL CALIBRATION at least once per 18 months. The CHANNEL FUNCTIONAL TEST shall be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding 275 psig during each plant startup, if the test has not been performed within the last 31 days.

• When conducting tests of an auxiliary feedwater train in MODES 1,.2, '

and 3 which require local manual realignment of valves that make the train inoperable, the Motor Driven Feedwater Pump and its associated flow paths shall be OPERABLE per Specification 3.7.1.7 during the performance of this surveillance. If.the Motor Driven Feedwater Pump or an associated flow path is inoperable, a dedicated individual shall be stationed at the realigned auxiliary feedwater train's valves (in communication with the control room) able to restore the valves to normal system OPERABLE status. ,

DAVIS-BESSE, UNIT 1 3/4 7-Sa Amendment No. A6, A44,193 ,

- ..,,n , , - . , - . . . _ , . . . . - . . - ,,

l

.LAR 94-0011

.Page 12 PLANT SYSTEMS CONDENSATE STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.7.1.3 The condensate storage tanks shall be OPERABLE with a minimum contained volume of 250.000 gallons of water.

APPLICABILITY: MODES 1.'2 and 3.

ACTION:

With the condensate storage tanks inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

a. Restore the condensate storage tanks to OPERABLE status or be in HOT SHilTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or

b. [@lf$Q{f@jifsfiWVWriissiij Ocmen:trate the OPERABILITY of the service water s3t~eis'sra'liankup su to the auxiliary feedwater sTfhece and restore the systemReHTylonWF2121@OPERAB[fst condensate stor3?IfianksTo us within 7 days or be in j

HOT SHUTDOWN within the hit @[@ ne*t 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCEIEE0VIREMENTS 4.7.1.3.1 The condensate storage tanks shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the contained water volume to be within its limits when the tanks are the supply source for the auxiliary feedwater pumps.

A ' 1.3.2-The service V ter system shall be demonstrated OPEPABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that at least One service v!ater 100p is oper+ ting and that the service v!ater loop auxiliarj fccilater system 1 clation valves are either caen er OPERAB1-E vehencver the service viater system is the supply 50ur430 for tr auxiliary fec6!ater pumps.

DAVIS-BESSE. UNIT 1 3/4 7-6 Amendment No. I64 l

I i

i I

J

z -

LAR.94-0011 Page 13- ,

PLANT SYSTEMS HOTOR ORIVEN FEEDWATER PUMP SYSTEM-LIMITING CONDITION FOR OPERATION 3.7.1.7 The Motor Driven Feedwater Pum) and associated flow paths to the Auxiliary Feedwater System shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With the Motor Drive Feedwater Pum) or its associated flow paths to the Auxiliary Feedwater System inoperaale, restore to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in 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 />.

. SURVEILLANCE REQUIREMENTS 4.7.1.7 The required Motor Driven Feedwater Pump and flow paths to the Auxiliary Feedwater System shall be demonstrated OPERABLE:

E[EileM

0. At least once per 92 days by:*

1. Verifying the M0 tor Driven Feedwater Pump OPERABLE by starting the Motor Driven Feedwater Pump (if the pump is not'already running) from the control r00m. and by a<n,+<n- -,

vou wuuivo v nr. n, i vn ,

b. At least once per 31 days by:

1. When in MODE 1 with RATED THERMAL POWER greater than 40%,

verifying that each manual valve in the Motor Driven Feedwater Pum) suction and discharge lines that affect the system's capa)ility to deliver water to the steam generators is locked in its proper position.

2. When in MODE 1 with RATED THERMAL POWER greater than 40%,

verifying that each power operated valve in the flow path is in its correct position.

I

• When conduct 4ng tect: Of the Motee Driven Fecdwat-er Pumn System in MODE 1 greater than '0! RATED THERMAL POWER which require 10cai manual realignment

--of valve: that make the system incocrable. both auxiliary feedwater pumps and-t-hcir as:Ociated flow path; chbll bc OPERABLE per Specification 3.7.1.2 ,

dur4wf-the performanec of this surveillance. If one sxiliary feedwater pump or ' low path is inoperable a dedicated individual chall bc stationed

--at the realigned M0ter Driven Feedwater Pump System *: valves (in communica i tien-w4th the control room) able to restore the valves to normal system i

.0PERABLE status-DAVIS BESSE. UNIT 1 3/4 7-12a Amendment No. 103,I93 ,

4 i

l

~~ ' ~ ~ ~ ' *

&?~^

• gg . , .

'LAR 94-00111 (Page 14 ,. ~ lf PLANT $YSTEMS-

' SURVEILLANCE REQUIREMENTS (Continued)

~

y 3 .' When in MODE l'at RATED THERMAL POWER equal to or less than 40% or-when.in MODES 2 or 3. verifying that each valve (manual or >ower 1 operated);in the Motor Driven Feedwater Pump flow path is 'a)le to" 2be positioned locally for delivering flow to the Auxiliary? .

Feedwater System.- 1

- (Ability is; demonstrated by verifying the presence of handwheels for'all -

-manual valves and the presence of either handwheels or available power supply for motor operated valves.) ,

c. At least once per 92 days and prior to entry into MODE 3 from MODE 4 (if not performed in the past 92 days) by:*

1. Verifying proper operation of each power operated and automatic valve in the Motor Driven Feedwater Pump flow path to the Auxiliary Feedwater System.  :

4

$. . Verify}ng proper operation of the~ Motor Driven Feedwater

- Pump.* >

d. "At least once per 18 months by:

1. Verifying that there is a flow path between the' Motor Driven Feedwater Pump System and the Auxiliary Feedwater System by pumping water from the Condensate Storage Tanks to the steam generators. The flow path to the steam generators shall be ,

verified prior to entering MODE 3 from MODE 4 t'y either-steam generator level change or Auxiliary Feedwater Safety Grade Flow Indication. Verification of Motor Driven -

Feedwater Pump System flow capacity is not required.

• If the Motor Driven Feedwater Pump cannot be tested within the time period specified, due to being aligned to the Main Feedwater System, the Surveillance Requirement shall be met within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the Motor i Driven Feedwater Pump has been aligned to the Auxiliary Feedwater System.  !

for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, j

• • When conducting tests of the Motor Driven Feedwater Pump System in MODE'l-greater than 40% RATED THERMAL POWER which require local manual realignment of valves that make the system inoperable, both auxiliary feedwater pumps' l and their associated flow paths shall be OPERABLE per Specification 3.7.1.2 l during the performance of this surveillance. If one auxiliary feedwater L pump or flow path is inoperable, a dedicated individual shall be stationed at the realigned Motor Driven Feedwater Pump System's valves:(in communica- ,

tion with the control room) able to restore the valves to normal system l OPERABLE status. l DAVIS-BESSE. UNIT 1 3/4 7-12b Amendment No. 103.I93

, , , -- .n ,. . . , ~ , _ - . '- . . . . - . . _ _ . _ - . - - . _ . - - - _ . ~ _ _ . - ----

LAR 94-0011 w"

PLANT SYSTEMS INFORMATION ONLY SURVEILLANCE REOUIREMENTS (Continued)

2. Verifying proper operation of the Motor Driv,en Feedwater Pump lube oil interlocks.

3. Verifying proper operation of manual valves by shifting the Motor Driven Feedwater Pump between the Main Feedwater System and the Auxiliary Feedwater System. ,

e. After any modification or repair to the Motor Driven Feedwater Pump l System that could affect the system's capability to deliver water from the Condensate Storage Tanks to the Auxiliary Feedwater System, the affected flow path shall be demonstrated available as follows:* -l

1. If the modification or repair is in the Auxiliary Feedwater flow path downstream of the Motor Driven Feedwater Pump test flow line tie-in, the Motor Driven Feedwater Pump shall pump water from the Condensate Storage Tanks to the Auxiliary Feedwater System and the flow path availability will be varified by either steam generator level change or Auxiliary Feedwater Safety Grade Flow Indication.

2. If'the modification or repair is upstream of the Motor Driven Feedwater Pump test flow line tie-in, the Motor Driven Feedwater Pump shall pump water from the Condensate Storage Tanks to the test flow Motor lineFeedwater Driven and the Pump flow path Safetyavailability Grade Flowwill be verified by l Indication.

f. Following each extended COLD SHUTDOWN (greater than 30 days in l ~

MODE 5), by: ,

1. Verifying that there is a flow path between the Motor Driven Feedwater System and the Auxiliary Feedwater System by pumping water from the Condensate Storage Tanks to the steam generators.

The flow path to the steam generators shall be verified prior to enteririg MODE 3 from MODE 4 by either steam generator level change or Auxiliary Feedwater Safety Grade Flow Indication. l Verification of Motor Driven Feedwater Pump flow capacity is not required.

• This surveillance testina shall be performed prior' to entering MODE 3 from HODE 4 if the modification is made in MODES 4, 5, or 6. Verification of the Motor Driven Feedwater Pump flow capacity is not required. l DAVIS-BESSE, UNIT 1 3/4 7-12c Amendment No.-)VJ,193 1

LAR 94-0011 Page 16, PLANT SYSTEMS BASES 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the Auxiliary Feedwater System ensures that the Reactor Coolant System can be cooled down to less than 280*F from normal operating conditions in the event of a total loss of offsite power. The OPERABILITY of the Auxiliary Feed Pump Turbine Inlet Steam Pressure Interlocks is required only for high energy line break concerns and does not affect Auxiliary Feedwater System OPERABILITY.

Th~e "C6ndenih te ' St'oFsh(~TanEs~#r~e^ thFnon isa fety: Fel a ted' pri ms FK'ou'r'es~6f ^ th'E~sitEQ for the Auxiliary Feedwater System. ' When the auxiliary feedwaters s are needed and either the Condensate Storage Tanks are not>available;or have. emptied b '

the Auxiliary Feedwater System; a safety.related transfer system transfers ths'^ y' suction from the Condensate Storage sTanks to the Service Water System. The Se Water System is the safety related secondary source of the water and must bd ^lf~ics '^

available for, the associated Auxiliary Feedwater System. train to be OPERABLEFThd transfer is finitiated upon detection of a low suction aressure at the suction of th~4 auxiliary feedwater pumps by suction pressure interloceswitches.~ These pressure-switches, upon sensing low suction' pressure, will automatically transfer of the auxiliary feedwater pumps to the Service Water System.~ ined00law a susta,the'suc Jow suction pressure additional Auxiliary Feed Pump Suction Pressure Interlocks ~;

Will operate to close the steam supply valvergto protect the turbine driven" ~ ~

auxiliary feedwater pumps from cavitation. ;iesteamsupply,valveswillreopsd r automatically upon restoration of' suction,pr. isure to the pumps 3 Both thoclow add the low law suction Auxiliary Feed Pump Suctlbn Pressure Interlocks?are requged "~

td bpf1ABLE fon0PEWLIRofjhe asspciatepauxiliary,feedwatedra13nf Each steam driven auxiliary feedwater pump is ca3able of delivering the required feedwater flow at the full open pressure of the Main Steam Safety Valves as assumed in the Updated Safety Analysis Report. This capacity is sufficient to ensure that adequate feedwater flow 1s available to remove decay heat and reduce the Reactor Coolant System temperature to less than 280*F where the Decay Heat Removal System may be placed in operation. ERhitfaT6?bf3Mflibry?fsdWdtsifniU5tTbETEi~sti1EE61l "providi.ng' fee &ste6fllEt6?#achisteamygenerat6rsin50fderitoibs10PERABLE QeMQ theidesigniof%thejsystemidossnpMptqvidModesdingibotMstg;gejemt,s g!m@tapegugiftcgpgedgig WhehMond0ctihFt 5t576f?'5475WilfiFy?fd'sWitEEtisI&M5iMODE5E27Fr33~^WhED re(01reglocaltmanual#ealignmenigoi?valvesjtharimake{the$trainlinoperabl#W _

dec tin]comunicatioWitMthL 1 cated ;1 ndi vidualishal h bej sta tioned (atsthelvalves;temj 0PERABLEsstatuCHowev controltroom;#able:tofrestorettheWalves:1tojnormal:sys it j'ssnot' required to;have thisFdedicated individual /stationeddfithelotheMtrainsp"f ~

the' Auxiliary Sys tem; Feedwater;rsuantito i s t 0PERABLE1pu Systemj Techni 11s10PERABLEdndithe:MotoriDrivenlfeedWateNPbmp"60 cal ? Speci ficati ont3/4Mit becauseXtsod bf auxiHary feedwaterstoithefsteamfgenerators34re10PERABLEO.).Inseitherfsitdationf thetAuk111ary FeedwaterJSystem train withithe:Llocaltmanuals realign'edWalves inoperableJndtheilimijjpgtConditionfferi0peration2CT10[mustibeMqlhey@ f Closure of valve AF 599 or AF 608 will render both trains of the Auxiliary Feedwater System and the Motor Driven Feedwater Pump System inoperable. This is because closure of these valves would result in a complete loss of auxiliary feedwater to the steam generators for certain postulated feedwater line and steam line breaks.

(3/4.7.1.2 is continued on page B 3/4 7-2.)

DAVIS-BESSE. UNIT 1 B 3/4 7-lb Amendment No. II7.I22,I3I.

IB2.I93 Next page is B 3/4 7-2

P 4

E'N " INFORMATION ONLY PLANT SYSTEMS BASES 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (Continued) l Following any modifications or repairs to the Auxiliary Feedwater System piping from the Condensate Storage Tank through auxiliary feed pumps to the steam generators that could affect the system's capability to deliver water to the steam generators, following extended cold shutdown, a flow path verification test shall be performed. This test may be conducted in MODES 4, 5 or 6 using auxiliary steam to drive the auxiliary feed pumps turbine to demonstrate that the flow path exists from the Condensate Storage Tank to the steam generators via auxiliary feed pumps.

Verification of the turbine plant cooling water valves (CW 196 and CW 197),

the startup feedwater pump suction valves (FW 32 and FW 91), and the startup feedwater pump discharge valve (FW 106) in the closed position is required to address the concerns associated with potential pipe failwes in the auxiliary feedwater pump rooms, that could occur during operation of the startup feedwater pump.

3/4.7.1.3 CONDENSATE STORAGE TANKS Th6 OPERABILITY of the Condensate Storage Tanks with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> with steam discharge to atmosphere and to cooldown the Reactor Coolant System to less than 280* under normal conditions (i.e., no loss of offsite power). The contained water volume limit includes an allowance for water not usable because of tank discharge line location o.-

other physical characteristics.

3/4.7.1.4 AC'TIVITY The limitations on secondary system specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR 1 Part 100 limits in the event of a steam line rupture. This dose includes the I effects of a coincident 1.0 GPM primary to secondary tube leak in the steam l generator of the affected steam line. These values are consistent with the l assumptions used in the safety analyses.

3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture.

This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line rupture occurs.within containment. The OPERABILITY of the main steam isolation valves DAVIS-BESSE, UNIT 1 B 3/4 7-2 Amendment No. M ,H ,ll7,122, Ltr. 5/1/91,19,193

LAR 94-0011 PZg] 18 PLANT SYSTEMS BASES l within the closure times of the surveillance requirements are consistent with l the assumptions used in the safety analyses.

I 3/4.7.1.6 SECONDARY WATER CHEMISTRY - Deleted ,

1 3/4.7.1.7 MOTOR DRIVEN FEEDWATER PUMP SYSTEM The OPERABILITY of the Motor Driven Feedwater Pump System ensures that the Reactor Coolant System can be cooled down from normal operating conditions in the event of the total loss of Main Feedwater and Auxiliary Feedwater Pumps.

The Motor Driven Feedwater Pump System must be capable of aroviding  !

feedwater flow to each steam generator in order to be OPERABLE.  !

The Motor Driven Feedwater Pump flow capability ensures that adequate feedwater flow is available to remove Decay Heat and reduce the Reactor Coolant System temperature to where the Decay Heat System may be placed into operation, tests T _ Yrf EM hambpBta 16nsd i $$t ves jq eg gyhg TablMt#j ~Qsl s ' i

~hna

{ipl ye Ei fpt . . . .g !g.

2 '^*

Teth dhl#S tQdst MDi$$i

({1qlhtjfMglCAnMyinM

. E T@lWi!6EION@ss we heH. lM.Idgire When at 40% RATED THERMAL POWER or less and in MODES 1, 2, or 3 the Motor Driven Feedwater Pump System may be aligned to provide a flow path from the Deaerator Storage Tank through the Motor Driven Feedwater Pump to the Main Feedwater System. During this Motor Driven Feedwater Pump mode of operation, a flow path from the Condensate Storage Tanks through the Motor Driven Feedwater Pump to the Auxiliary Feedwater System shall be maintained with the ability for manual positioning of valves such that i

DAVIS-BESSE. UNIT 1 B 3/4 7-3 Amendment No. IO3.I25.

I93

LAR 94-0011

. INFORMATION ONI.Y PLANT SYSTEMS BASES the flow path can be established. The ability for local, manual operation is demonstrated by verifying the presence of the handvheels for all manual valves and the presence of either handwheels or available power supply for motor operated valves.

3/4.7.2 STEAM CENERATOR PRESSURE /TEMPERATLTE LIMITATION

- The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations of 110*F and 237 psig are based on a steam generator RTNDT of 40*F and are sufficient to prevent brittle fracture.

3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITI of tha component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal end accident conditions. The redundant cooling capacity of this sys'.em, assuming a single failure, is consistent with the assumptions used in the safety analyses.

3/4.7.4 S'LVICE WATER SYSTEM The OPERABILITY of:the service water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal'and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.

3/4.7.5 ULTIMATE HEAT SINK The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either 1) provide normal cooldown of- the facility, or 2) to mitigate the effects of '

accident conditions within acceptable limits.

The limitations on minimum water level and maximum temperature are based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature and is consistent with the recon =endations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants" March 1974.

3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the control room emergency ventilation system ensures that 1) the ambient air temperature does not exceed the allovable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room vill remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 of Appendix "A",

10 CFR 50.

DAVIS-BESSE, UNIT I B 3/4 7-4 Amendment No.103

. _ _ _ _ _ _ _ _ _ _ _ _ _