ML20069M331

Proposed Tech Specs,Increasing Allowed out-of-service Time from 7 Days to 14 Days for Ads,Hpci & RCIC Sys,Including Section 4.5.H, Maint of Filled Discharged Pipe

ML20069M331
Person / Time
Site:	Pilgrim
Issue date:	06/09/1994
From:	BOSTON EDISON CO.
To:
Shared Package
ML20069M321	List: ML20069M318 ML20069M331
References
NUDOCS 9406210293
Download: ML20069M331 (16)

Text

l 1

l I

Attachment B to BEco Letter 94-068

{

l Amended Technical Specification Pages:

Paae 107 108 ,

109 111 116 117 118 i

l 9406210293 940609 PDR ADOCK 05000293 P PDR

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT C. HPCI System C. HPCI System

1. The HPCI system shall be operable 1. HPCI system testing shall be whenever there is irradiated fuel performed as follows:

in the reactor vessel, reactor pressure is greater than 150 psig, a. Simulated Once/ operating and reactor coolant temperature is Automatic cycle greater than 365 F; except as Actuation specified in 3.5.C.2 below. Test

2. From and after the date that the b. Pump Oper- When tested HPCI system is made or found to be ability as specified inoperable for any reason, in 3.13 verify continued reactor operation is that the HPCI permissible only during the pump delivers succeeding 14 days unless such l at least 4250 system is sooner made operable, GPM for a providing that during such 14 l system head days all active components of the corresponding ADS system, the RCIC system, the to a reactor LPCI system and both core spray pressure of systems are operable. 1000 psig

3. If the requirements of 3.5.C c. Motor Operated As specified cannot be met, an orderly shutdown Valve Oper- in 3.13 shall be initiated and the reactor ability pressure shall be reduced to or below 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. d. Flow Rate at Once/ operating 150 psig cycle verify that the HPCI pump delivers at least 4250 GPM for a system head corresponding to a reactor pressure of 150 psig The HPCI pump shall deliver at least 4250 gpm for a system head corresponding to a reactor pressure of 1000 to 150 psig.

Amendment No. 38;-42,-44;-198,-1991 -1141 -135; 149 107

LIMITING CONDITION FOR OPERATION SURVEILLANCE RE0VIREMENT 3.5.D Reactor Core Isolation Coolina 4.5.D Reactor Core Isolation Coolina (RCIC) System (RCIC) System

1. The RCIC system shall be operable 1. RCIC system testing shall be whenever there is irradiated fuel performed as follows:

in the reactor vessel, reactor pressure is greater than 150 psig, a. Simulated Once/ operating and reactor coolant temperature is Automatic cycle greater than 365 F; except as Actuation specified in 3.5.D.2 below. Test

2. From and after the date that the b. Pump When tested RCICS is made or found to be Operability as specified inoperable for any reason, in 3.13 verify continued reactor power operation that the RCIC is permissible only during the pump delivers succeeding 14 days provided that at least 400 during such 14 days the HPCIS is GPM at a operable. system head corresponding

3. If the requirements of 3.5.0 cannot to a reactor be met, an orderly shutdown shall pressure of be initiated and the reactor 1000 psig pressure shall be reduced to or below 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. c. Motor As specified Operated in 3.13 Valve Operability

d. Flow Rate at Once/ operating 150 psig cycle verify that the RCIC pump delivers at least 400 GPM at a system head corresponding to a reactor pressure of 150 psig

" The RCIC pump shall deliver at least 400 gpm for a system head corresponding to a reactor pressure of 1000 to 150 psig.

l l

)

Amendment No. 425-1991 -1141 -135,-149 108

LIMITING CONDITION FOR OPERATION SURVEILLANCE RE0VIREMENT 3.5.E Automatic Depressurization 4.5.E Automatic Depressurization Sv' stem (ADS) System (ADS)

1. The Automatic Depressurization 1. During each operating cycle the

. System shall be operable following tests shall be whenever there is irradiated performed on the ADS:

fuel in the reactor vessel and

the reactor pressure is greater a. A simulated automatic than 104 psig and prior to a actuation test shall be startup from a Cold Condition, performed prior to startup except as specified in 3.5.E.2 after each refueling outage.

below. The ADS manual inhibit switch will be included in this

2. From and after the date that one test.

valve in the Automatic Depressurization System is made b. With the reactor at pressure, 2

or found to be inoperable for each relief valve shall be any reason, continued reactor manually opened until a operation is permissible only corresponding change in i during the succeeding 14 days reactor pressure or main unless such valve is sooner made turbine bypass valve operable, provided that during positions indicate that steam l such 14 days the HPCI system is is flowing from the valve.

operabl e .

3. If the requirements of 3.5.E cannot be met, an orderly shutdown shall be initiated and the reactor pressure shall be reduced to at least 104 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4 4

l l

Amendment No. 22, 42, 106, 109, 114, 139 109

, '.L IMITING CONDITION FOR OPERATION , SURVEILLANCE RE0VIREMENT 3.5.F Minimum Low Pressure Coolina

! and Diesel Generator l' Availability a) No work on the reactor )

vessel, in addition to CRD removal, will be l performed which has the l potential for exceededing i

the maximum leak rate from a single control blade seal if it became unseated.

b) i) the core spray systems are operable and aligned with a suction path from

the condensate storage

! tanks. ii) the

condensate storage tanks l shall contain at least 200,000 gallons of usable water and the refueling cavity and dryer / separator pool l shall be flooded to a l least elevation 114'-0" 3.5.G l

(Intentionally left blank) 3.5.H Maintenance of Filled 4.5.H Maintenance of Filled l Discharoe Pioe Discharae Pipe Whenever core spray systems, LPCI The following surveillance l- system, HPCI or RCIC are required to requirements shall be adhered to be operable, the discharge piping assure that the discharge piping of from the pump discharge of these the core spray systems, LPCI system, systems to the last block valve HPCI and RCIC are filled:

shall be filled.

1. Every month the LPCI system and l l core spray system discharge I i piping shall be vented from the i l high point and water flow I observed. l

2. Following any period where the LPCI system or core spray systems have not been required to be operable, the discharge piping of the inoperable system shall be vented from the high point prior to the return of the system to service.

l Amendment No. 39, 4-36 111

BASES:

'3.5.C HPCI The limiting conditions for operating the HPCI System are derived from the Station Nuclear Safety Operational Analysis (FSAR Appendix G) and a detailed functional analysis of the HPCI System (FSAR Section 6).

The HPCIS is provided to assure that the reactor core is adequately cooled to limit fuel clad temperature in the event of a small break in the nuclear system and loss-of-coolant which does not result in rapid depressurization of the reactor vessel. The HPCIS permits the reactor to be shut down while maintaining sufficient reactor vessel water level inventory until the vessel is depressurized. The HPCIS continues to operate until reactor vessel pressure is below the pressure at which LPCI operation or Core Spray System operation maintains core cooling.

The capacity of the system is selected to provide this required core cooling.

The HPCI pump is designed to pump 4250 gpm at reactor pressures between 1100 and 150 psig. Two sources of water are available. Initially, demineralized water from the condensate storage tank is used instead of injecting water from the suppression pool into the reactor.

When the HPCI System begins operation, the reactor depressurizes more rapidly than would occur if HPCI was not initiated due to the condensation of steam by the cold fluid pumped into the reactor vessel by the HPCI System. As the reactor vessel pressure continues to decrease, the HPCI flow momentarily reached equilibrium with the flow through the break. Continued depressurization causes the break flow to decrease below the HPCI flow and the liquid inventory begins to rise. This type of response is typical of the small breaks. The core never uncovers and is continuously cooled throughout the transient so that no core damage of any kind occurs for breaks that lie within the capacity range of the HPCI.

The analysis in FSAR Appendix G shows that the ADS provides a single failure proof path for depressurization for postulated transients and accidents. The RCIC is required as an alternate source of makeup to the HPCI only in the case of loss of all offset A-C power. Considering the HPCI and the ADS plus RCIC as redundant paths, and considering judgments of the reliability of the ADS and RCIC systems, a 14-day allowable repair time is specified. l The requirement that HPCI be operable when reactor coolant temperature is greater that 365 F is included in Specification 3.5.C.1 to clarify that HPCI need not be operable during certain testing (e.g., reactor vessel hydro testing at high reactor pressure and low reactor coolant temperature). 365"F is approximately equal to the saturation steam temperature at 150 psig.  ;

i l

Amendment No. MG- 116

BASES:

3.5.0 RCIC System The RCIC is designed to provide makeup coolant to the nuclear system as part of the planned operation for periods when the normal heat sink is unavailable.

The Station Nuclear Safety Operational Analysis, FSAR Appendix G, shows that RCIC also serves as redundant makeup system on total loss of all offset power in the event that HPCI is unavailable. In all other postulated accidents and transients, the ADS provides redundancy for the HPCI. Based on this and judgments on the reliability of the HPCI system, an allowable repair time of 14 days is specified. l The requirement that RCIC be operable when reactor coolant temperature is l greater than 365 F is included in Specification 3.5.0.1 to clarify that RCIC 1 need not be operable during certain testing (e.g., reactor vessel hydro testing at high reactor pressure and low reactor coolant temperature). 365 F is approximately equal to the saturation steam temperature at 150 psig.

4 i

d d

4

\

\ l e

l J

4 Amendment No. 109, 135, kO4 117 1

4

BASES:

3. 5s ( Automatic Depressurization System (ADS)

The limiting conditions for operating the ADS are derived from the Station Nuclear Safety Operational Analysis (FSAR Appendix G) and a detailed functional analysis of the ADS (FSAR Section 6).

This specification ensures the operability of the ADS under all conditions for which the automatic or manual depressurization of the nuclear system is an essential response to station abnormalities.

The nuclear system pressure relief system provides automatic nuclear system depressurization for small breaks in the nuclear system so that the low pressure coolant injection (LPCI) and the core spray systems can operate to protect the fuel barrier.

Because the Automatic Depressurization System does not provide makeup to the reactor primary vessel, no credit is taken for the steam cooling of the core caused by the system actuation to provide further conservatism to the CSCS.

Performance analysis of the Automatic Depressurization System is considered only with respect to its depressurizing effect in conjunction with LPCI or Core Spray. There are four valves provided and each has a capacity of 800,000 lb/hr at a reactor pressure of 1125 psig.

The allowable out of service time for one ADS valve is determined as 14 days l because of the redundancy and because of HPCIS operability; therefore, redundant protection for the core with a small break in the nuclear system is still available.

The ADS test circuit permits continued surveillance on the operable relief valves to assure that they will be available if required.

l l

l l

l Amendment No. 15, 135, b44 118 l

l

l 1

4 l

i Attachment C to BECo Letter 94-068 l

Marked up Technical Specification Pages j l

i l

l l

s' LIMITING CONDITION FOR OPERATION SURVEILLANCE RE0VIREMENT C. HPCI System C. HPCI System

1. The HPCI system shall be operable 1. HPCI system testing shall be whenever there is irradiated fuel performed as follows:

in the reactor vessel, reactor pressure is greater than 150 psig, a. Simulated Once/ operating and reactor coolant temperature is Automatic cycle greater than 365 F; except as Actuation specified in 3.5.C.2 below. Test

2. From and after the date that the b. Pump Oper- When tested ,

HPCI system is made or found to be ability as specified inoperable for any reason, in 3.13 verify /

continued reactor operation is that the HPCI permissible only during the -jg pump delivers succeeding mycKdays unless such at least 4250 - f system is sooner made operable, GPM for a y providing that during such seven. system head ,',

days all active components of the corresponding /

ADS system, the RCIC system, the to r. reactor , /

LPCI system and both core spray pressure of ,.

systems are operable. 1000 psig -

s

3. If the requirements of 3.5.C c. Motor Operated As cpecified '

cannot be met, an orderly shutdown Valve Oper- in 3.13 ,

shall be initiated and the reactor ability * ,;

pressure shall be reduced to or /

below 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. d. Flow Rate at Once/ operating /

150 psig cycle verify y that the HPCI pump delivers '

at least 4250 /

GPM for a ,

system head corresponding f to a reactor ,

/

pressure of 150 psig

(

The HPCI pump shall deliver at least 4250 gpm for a system head corresponding to a reactor pressure of 1000 to 150 psig.

n _z__ ,cn o Amendment No. 381 -425-44r-198;-1991 -114;-135, 107

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.5.D Reactor Core Isolation Coolina 4.5.D Reactor Core Isolation Coolina (RCIC) System (RCIC) System

1. The RCIC system shall be operable 1. RCIC system testing shall be whenever there is irradiated fuel performed as follows:

in the reactor vessel, reactor pressure is greater than 150 psig, a. Simulated Once/ operating and reactor coolant temperature is Automatic cycle greater than 365 F; except as Actuation specified in 3.5.D.2 below. Test

2. From and after the date that the b. Pump When tested RCICS is made or found to be Operability as specified inoperable for any reason, in 3.13 verify (

continued reactor power operation is permissible only during the that the RCIC pump delivers 4, h ,

succeeding seven days provided that at least 400  :

during such seven days the HPCIS is GPM at a I ,

operable. system head '

corresponding I

3. If the requirements of 3.5.0 cannot to a reactor /, -

be met, an orderly shutdown shall pressure of - -

be initiated and the reactor 1000 psig -

pressure shall be reduced to or below 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. c. Motor As specified ,

Operated in 3.13 ,

Valve '

Operability -

s

d. Flow Rate at Once/ operating L. -

150 psig cycle verify j .

that the RCIC -

pump delivers '

at least 400 ' ,,)

f GPM at a / , l system head corresponding p))

to a reactor /

pressure of ;d 150 psig d D

The RCIC pump shall deliver at least 400 gpm for a system head corresponding to a reactor pressure of 1000 to 150 psig.

"- - - i on Cap Amendmerit No. 42,-109;-ll4 -135,h 1 108

s bg LIMITING CONDITION FOR OPERATION SURVEILLANCE RE0VIREHENT

~.

3.5.E Automatic Deoressurization 4.5.E Automatic Deoressurization System (ADS) System (ADS)

1. The Automatic Depressurization 1. During each operating cycle the Q System shall be operable whenever following tests shall be performed there is irradiated fuel in the on the ADS:

reactor vessel and the reactor pressure is greater than 104 psig a. A simulated automatic actuation and prior to a startup from a test shall be performed prior Cold Condition, except as to startup after each refueling specified in 3.5.E.2 below. outage. The ADS manual inhibit switch will be included in this

2. From and after the date that one test.

rp valve in the Automatic Depressurization System is made b. With the reactor at pressure, or found to be inoperable for any each relief valve shall be reason, continued reactor manually opened until a operation is permissible onl corresponding change in reactor 7 4 _durina the succeedinggfedays %y pressure or main turbine bypass unless such valve is sooner made valve positions indicate that 3 operable, provided that during steam is flowing from the valve.

j ch the HPCI system

>4 r

3. If the requirements of 3.5.E M r- ) cannot be met, an orderly fj shutdown shall be initiated and 6

~

the reactor pressure shall be h reduced to at least 104 psig within 24 h0Jrs, h

lj l

l l

l

.1  !

1

(_E5 vision 14M y Amendment No. 22, 42, 706, 709, 774, 109

9 LIM'ITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT 3.5.F Minimum Low Pressure Coolina and Diesel Generator Availability 1

a) No work on the reactor ves-sel, in addition to CRD re-moval, will be performed t which has the potential for I exceededing the maximum I leak rate from a single control blade seal if it became unseated.

b) i) the core spray systems are operable and aligned with a suction path from l

l the condensate storage j tanks. ii) the condensate l storage tanks shall contain at least 200,000 gallons of ,

usable water and the '

refueling cavity and dryer / l separator pool shall be 1 flooded to a least l elevation 114'-0" l 3.5.G (Intentionally left blank) 3.5.H Haintenance of Filled Discharae 4.5.H Haintenance of Filled Discharae PlDa f.ip_tt

') Whenever core spray systems , LPCI The following surveillance requirements n system, HPCI or RCIC are required to shall be adhered to to assure that the be operable, the discharge piping from discharge piping of the core spray the pump discharge of these systems to systems, LPCI system, HPCI and RCIC are the last block valve shall be filled. filled:

1. Every month 6 er t6 th testing et the LPCI syste s discharge stem andpiping core spray3[J

@....____... shall be vented from the high point and water flow observed.

2. Following any period where the LPCI system or core spray systems have not been required to be operable, the discharge piping of the inoperable system shall be vented from the high point prior to the return of the system to service.

hiAmendmentr, 14 No. @ 29, Ill

fLASfJi:

3.5.C ILPG, The limiting conditions for operating the HPCI System are derived from the Station Nuclear Safety Operational Analysis (FSAR Appendix G) and a detailed l

functional analysis of the HPCI System (FSAR Section 6). I The HPCIS is provided to assure that the reactor core is adequately cooled to j limit fuel clad temperature in the event of a small break in the nuclear i system and loss-of-coolant which does not result in rapid depressurization of the reactor vessel. The HPCIS permits the reactor to be shut down while l maintaining sufficient reactor vessel water level inventory until the vessel l is depressurized. The HPCIS continues to operate until reactor vessel l

I pressure is below the pressure at which LPCI operation or Core Spray System operation maintains core cooling.

The capacity of the system is selected to provide this required core cooling. I The HPCI pump is designed to pump 4250 gpm at reactor pressures between 1100 and 150 psig. Two sources of water are available. Initially, demineralized water from the condensate storage tank is used instead of injecting water from the suppression pool into the reactor.

When the HPCI System begins operation, the reactor depressurizes more rapidly than would occur if HPCI was not initiated due to the condensation of steam by the cold fluid pumped into the reactor vessel by the HPCI System. As the reactor vessel pressure continues to decrease, the HPCI flow momentarily reached equilibrium with the flow through the break. Continued f3

! V depressurization causes the break flow to decrease below the HPCI flow and the liquid inventory begins to rise. This type of response is typical of the small breaks. The core never uncovers and is continuously cooled throughout the transient so that no core damage of any kind occurs for breaks that lie within the capacity range of the HPCI.

The analysis in FSAR Appendix G shows that the ADS provides a single failure proof path for depressurization for postulated transients and accidents. The h V

RCIC is required as an alternate source of makeup to the HPCI only in the case of loss of all offsite A-C power. Considering the HPCI and the ADS plus RCIC as redundant paths, and considering judgments of the reliability of the ADS and RCIC systems, a allowable repair time is specified.

The requirement that HPCI be operable when reactor coolant temperature is greater that 365*F is included in Specification 3.5.C.1 to clarify that HPCI need not be operable during certain testing (e.g., reactor vessel hydro testing at high reactor pressure and low reactor coolant temperature). 365'F is approximately equal to the saturation steam temperature at 150 psig.

l

]

~

heMMn AmendmentNo.g) 116

i '.

i' I

i BASES:

3.5.D RCIC System . _

) < c t-c d..

ua The RCIC is designed to provide makeup'to the nuclear system as part of the I planned operation for periods when the normal heat sink is unavailable. The

} Station Nuclear Safety Operational Analysis, FSAR Appendix G, shows that RCIC C also serves as redundant makeup system on total loss of all offsite power in I the event that HPCI is unavailable. In all other postulated accidents and 5 transients, the ADS provides redundancy for the HPCI. Based on this and judgments on the reliability of the HPCI system, an allowable repair time of g days is specified.

The requirement that RCIC be operable when reactor coolant temperature is greater than 365*F is included in Specification 3.5.D.1 to clarify that RCIC need not be operable during certain testing (e.g., reactor vessel hydro testing at high reactor pressure and low reactor coolant temperature). 365'F

! is approximately equal to the saturation steam temperature at 150 psig.

f: g d \

l i

~.

diev+s4cn 157?_ 117 Amendment No. 109,125,@-)

BASES:

- 3.5.E Automatic Deoressurization System (ADS) l The limiting conditions for operating the ADS are derived from the Station Nuclear Safety Operational Analysis (FSAR Appendix G) and a detailed

! functional analysis of the ADS (FSAR Section 6). a i

i 1 l '

i This specification ensures the operability of the ADS under all conditions for '

which the automatic or manual depressurization of the nuclear system is an l

essential response to station abnormalities.

The nuclear system pressure relief system provides automatic nuclear system depressurization for small breaks in the nuclear system so that the low ,

l pressure coolant injection (LPCI) and the core spray systems can operate to '

protect the fuel barrier.

l Because the Automatic Depressurization System does not provide makeup to the i reactor primary vessel, no credit is taken ~for the steam cooling of the core caused by the system actuation to provide further conservatism to the CSCS.

Performance analysis of the Automatic Depressurization System is considered only with respect to its depressurizing effect in conjunction with LPCI or Core Spray. There are four valves provided and each has a capacity of 800,000 lb/hr at a reactor pressure of 1125 psig.

f The allowable out of service time for one ADS valve is determined asdev'errj+-/f l days because of the redundancy and because of HPCIS operability; therefoN ,

redundant protection for the core with a small break in the nuclear system is

!N

,v still available.

l The ADS test circuit permits continued surveillance on the operable relief l

valves to assure that they will be available if required.

i

.1)

• Jc u.unGr.? $,  % 118 Amendment No. 75, 725, AD x

{ ----- ___. +