ML20080Q085

Proposed Tech Specs Modifying Pump & Valve Surveillance Criteria for LPCI & Core Spray Subsystems,Rhr Svc Water, Hpci,Esw & River Water Supply Systems from Once Every Three Months to Frequency Specified by DAEC ASME Section XI IST

ML20080Q085
Person / Time
Site:	Duane Arnold
Issue date:	03/01/1995
From:	IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML20080Q064	List: ML20080Q085 NG-95-0759, Application for Amend to License DPR-49,to Modify Pump & Valve Surveillance Criteria for LPCI & Core Spray Subsystems,Rhr Svc Water,Hpci,Esw & River Water Supply Systems
References
NUDOCS 9503080240
Download: ML20080Q085 (7)

Text

. . _ - - -- . . . .

. DAEC-1 LIMITING CONDITION FOR OPERATION SURVE!LLANCE REQUIREMENT 1

3.5 C0RE AND CONTAINNENT COOLING 4.5 CORE AND CONTAINMENT COOLING SYSTEMS- SYSTEMS l Acolicability: Aeolicability:

i Applies to the operational Applies to the Surveillance status of the core and Requirements of the core and suppression pool cooling suppression pool cooling subsystems. subsystems which are required-when the corresponding Limiting Condition for Operation is in effect.

Ob.iective: Oldestive:

To assure the operability of To verify the operebility of the core and suppression pool the core and suppression pool cooling subsystems under all cooling subsystems under all conditions for which this conditions for which this cooling capability is an cooling capability is an

~

essential response. essential response to station abnormalities.

Specification: Enecification: -

A. Core Spray and*LPCI Subsystems A. Core Soray and LPCI Subsystems

1. Both core spray subsystens 1. Core Spray Subsystem Testing.

, shall be OPERABLE whenever irradiated fuel is in the J,1g Freouency vessel and prior to reactor startup from a COLD CONDITION, s. Simulated Annual except as specified in 3.5.A.2 Autcastic and 3.5.G.3 below. Actuation i test. .

I

b. Punp -ence/S-mentle l- l Operability Ane4W W 2.5 f b,73 %  ;

c. Motor- Onsel3 months- l Operated 4, .

Valve 2ri f.44u

g. . ,:.. , d =

Operability -

Amendment No. 143.150 3.5-1 .

JR 1 inne 9503000240 950301 PDR ADOCK 05000331 P

_ PDR__

DAEC-1 iLIMITINGCONDITIONSFOR0:ERATION SURVEILLANCE REOUIREMENTS l

3. The LPCI Subsystem snall be 3. LPCI Subsystem Testing shall be as OPERABLE whenever irradiated fuel follows:

is in the reactor vessel, and i prior to reactor startup from a it.gm Freauency COLD CONDITION, except as  ;

l

specified in 3.5. A.4, 3.5. A.5 and a. Simulated Annual l 3.5.G.3 below. Automatic  !

Actuation Test j

m.  ;

b. Pump 02: /3 .T,enth:

Operability As , W A*

25r S *.:A

c. Motor Operated 000/2 ;;.;r.th- .

Valve Operability Avssre@, W A M*-

.y3%

l

]

d. Pump Flow Once/3 months j Rate  ;

i 1

i Three L,~i. pumps  !

shall del, ir 14,400 gpm against a system head corresponding to a vessel pressure of 20 psig based on individual pump tests.

e. Once per shift visually inspect ,

and verify that RHR valve panel  !

lights and instrumentation are l functioning normally.

4. With one RHR (LPCI) pump inoperable, provided the remaining RHR (LPCI) active components, both Core Spray subsystems, the containment spray subsystem, and the diesel generators are verified to be OPERABLE, restore the inoperable RHR (LPCI) pump to CPERABLE status within 30 days.

AMENDMENT NO. ))p,)pp,77f, 200 3.5-3

i 'i  !

i_. '

l

~ DAEC-1 l

- - 4 LIMITING CONDITIONS ~FOR OPERATION SURVEILLANCE REQUIREMENTS _

o . I

C Residual Heat' Removal (RHR)- . C. ' Surveillance of the RHR' Service Service Water System Water System l

1. Surveillance of the RHR service .,

l1.Exceptasspecifiedin3.5.C.2, 3.5.C.3, 3.5.C.4, and 3.5.G.3 water system-shall be as follows

j below, both.RHR service water  ;

subsystem loops shall be operable RHR Service Water Subsystem  !

whenever irradiated fuel is in the Testing:

i reactor vessel and reactor coolant -

j temperature is greater than'212*F. .LtsB Freauency l a : /3 :::th:-

4

a. Pump and Motor .

j operated valve A, if./ A4.

j operability. .ur .ph i

b. Flow Rate after major  !

Test-Each pump  ;

-RHR service maintenance, water pump and every 3- ,

shall deliver months at least 2040 ,

gpa at a TDH of 610 ft. or rore.

2. With one RHRSV outp inoperable, provided the maining active components of both RHRSW subsystems are verified to be ,

OPERABLE, restore the inoperable pump to OPERABLE status within 30

• 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 in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ,

3. With one RHRSW pump in each subsystem inoperable, provided the remaining active components of l both RHRSW subsystems and the i diesel generators are verified to j be OPERABLE, restore at least one  !

inoperable pump to OPERABLE status l within 7 days or-be in at least -

HOT SHUTDOWN within the next 12

~

hours and in COLD SHUTDOWN within

~ -

the following.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

AMENDMENT NO.JS8,739,J79,J74,199 3.5-5

)

. DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS

4. With one RHRSW subsystem inoperable, provided the remaining i RHRSW subsystem and its associated diesel generator are verified to be OPERABLE, restore the . ,

inoperable system to OPERABLE status with at least one OPERABLE pump within 7 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 in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i D. HPCI Subsystem D. HPCI Subsystem-

1. The HPCI Subsystem shall be 1. HPCI Subsystem testing shall be OPERABLE whenever there is performed as follows:

irradiated r~uel in the reactor vessel, reactor pressure is 11gm Freauency greater than 150 psig, and prior to reactor startup from a COLD a. Simulated Annual ,

CONDITION, except as specified in Automatic  !

3.5.0.2 below. Actuation Test

b. Pump Operability ,0,0,:cy. g nt g

c. Motor Operated FVefrs*

03.:/ MentF-Valve Operability As sfump ,1 nr ,

Ar. r s -

d. At rated reactor Once/ Months pressure demonstrate ability-to deliver rated flow at a discharge pressure greater than or equal to that

_ pressure required to --

accomplish vessel injection if vessel pressure were as high as 1040 psig.

AMENDMENT NO. 775.JA3.J88.J7A 199 3.5-6

. DAEC-1 i LIMITING CO M ITION FOR OPERATION SINtVEILLANCE REQUIREMENT

! J. River Water Sunnly System J. River Water sunniv Svstee  ;

j' -

3. Escept as specified in 3.5.J.2 1.. River Water Supply System Testine-l below, at least one pimp in each h Freenency  !

]

river water supply system loop  ;

shall be OPERABLE whenever a. Simulated Once/ operating 1 automatic cycle

! irradiated fuel is in the reactor ***""* ' ***

• j vessel and reactor coolant l l

temperature is greater than 2121. b. Pump and motor 4 nee /3 x . e.; l i operated valve operability.

. g*);, A i

j j5 r77'f"~Pvey 8 ^

c. Flow Rate Test -==

Each river water After major pump

! supply system maintenance and

pump shall once per 4 deliver at least 3 months I 6000 gym at TON j of 46 ft. or Daily when -iver a more. elevation is

! less than 727 1 feet.

i d. Operating Pump l

Flow Rate l Demonstration Each Operating Daily

River Water j Supply System Pump shall deliver j at least 6000 gpe.

j 2. With one river water supply loop ,  ;

i inoperable, provided the other i

river water supply 'oop and its l 3 associated diesel generator are 1 l verified to be OPERABLE, restore I i at least one pump in the l

! inoperable loop to OPERABLE status j within 7 days or be in at least i HOT $HUTDOWN within the next 12 I hours and in COLD SHUTDOWN within i the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i i

l 1

4 j

j .

1 i 3.5-12 Amendment No. 79.735.JA3.J58.174

AUG 121951 i

i I __

IEEC-1 1 I \

5 y 4.5' BASEE t 1 I

Core and Containment Cooling Systems Surveillance Frequencies l

- The testing interval for the core and containment cooling systems is based ::.

industry practics, quantitative reliability analysis, judgement and

! practica)1ty. T'e core cooling systems have not bee #, designed to be fully i

! sestable euring operation. For eaample, in the case of the MpC1, automatic I

initiatise during power operation would result in pumping cold water into the. l l

reactor water vessel which is not desirable. Comp 1ste ADS testing during power

operation causes an undesirable less-of-coolant inventory. To inemase the ,

' availability of the core and containment cooling systems, the components which i t The t 5:: -

theee- 7 2 : -- :ne 'J ii ;;;i21ty.fMWYest intervais are based upsE

5ection KI o M

K5KW A si 1.M sutomatic actuation test once per year :

j combined with frequent tests of the pumps and injection valves is deemed to be adequate testing of these systems. -

i l When components and subsystems are out-of-service, everall core and containment i cooling reliability is maintained by evaluating the operability of the remaining j equipment. The degree of evaluation depends on the nature of the reason for j the out-of-service equipment. For routine out-of-service periods caused by

} preventative maintenance, etc., the evaluation may consist of verifying the l redundant equipment is not known to be inoperable and applicable surveillance i intervals have been satisfied. However, if a failure due to a design deficiency )

caused the outage, then the evaluation of operability should be thereuph enough l to assure that a generic problem does not exist. l The RHR valve power bus is not instrumented. For this reason survelliance j reevirements require once per shift observation and verification of lights and 2

instrumentation operability.

1 I l

! l

! )

i l 4

I i .

,1 i

l j

4

! 3.5-23 Amendment No. 57,43,J$$,174 AUG12 an

4 I i

.* )

4 DAEC-1 )

1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS

.m E. Emeroency Service Water System E. Emeraency Service Water System i 1. Except as required in 1. tmergency Service Water System i Specification-3.8.E.2 below, both surveillance shall be as follows:

Emergency Service Water System loops shall be OPERABLE whenever a. Simulated auto- Once/

i irradiated fuel is in the reactor matic cetuation OPERATING CYCLE l

vessel and reactor coolant test.

j temperature is greater than

212*F. b. Pump and motor ^-r/? r-"-

j Operated valve A, , g gg/ f,4,,, g j

OPERABILITY gg,%,

l c. Flow Rate Test -

l Each Emergency Af ter major pump l Service Water maintenance I

! pump shall and once per-

, deliver at least 3 months, escent i that flow weekly during determined from periods of time Figure 4.8.E-1 the river water l j for the existing temperature 1

river water exceeds 80*F.

temperature.

'}

} 2. With one of the Emergency Service 2. With one Emergency' Service Water l 4 Water System pumps or loops system pump or loop inoperable, I inoperable, REACTOR POWER the OPERABLE pump and loop shall i OPERATION must be limited to be verified to be OPERABLE. In l j

~

seven days unless OPERABILITY of addition, the requirements of that system is restored within specification 4.5.G.1 shall be' l this period. During such seven met. ,

8 days all active components of the I l

i other Emergency Service Water System shall be OPERABLE, provided the requirements of Specification 3.5.G are met.

9 3. If the requirements of j Specification 3.8.E cannot be

! met, 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 in j COLD SHUTDOWN within the 1 following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i  !

2 1

! 1 i l j . 1 4

1 f

1 l

1 3.8-6 l Amendment No.JW,33,J39,M3,l'60,197

_ _ - -.