ML20206R816
| ML20206R816 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 05/11/1999 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20206R813 | List: |
| References | |
| NUDOCS 9905200204 | |
| Download: ML20206R816 (10) | |
Text
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5 CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING ,
SYSTEMS SYSTEMS l l
C. HPCl System C. HPCI System
whenever there is irradiated fuel in the reactor vessel, reactor pressure is a. Simulated Once/ l greater than 150 psig., and reactor Automatic Operating I coolant temperature is greater than Actuation Cycle 365*F, except as specified in 3.5.C.2 Test below. 1
- b. Pump When tested !
- 2. From and after the date that the HPCI Operability as specified in i system is made or found to be 3.13, verify that l inoperable for any reason, continued the HPCI pump !
reactor operation is permissible only delivers at least !
during the succeeding 14 days unless 4250 GPM for a J such system is sooner made operable, system head providing that during such 14 days all corresponding to active components of the ADS system, a reactor pressure the RCIC system, the LPCI system and of 1126 psig.
both core spray systems are operable.
- c. Motor As Specified
- 3. If the requirements of 3.5.C cannot be Operated in 3.13 met, an orderly shutdown of the reactor Valve shall be initiated and the reactor shall be Operability in the Cold Shutdown Condition 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/
150 psig, operating cycle, verify that the HPCI pump delivers at least 4250 GPM for a system head l corresponding to l a reactor pressure 1 of 150 psig. This i surveillance may be satisfied by an equivalent test. l
- he HPCI pump shall deliver at least 4250 GPM for a system head corresponding to a reactor i pressure range of 1126 to 150 psig. .
l 9905200204 990511 PDR ADOCK 05000293 P PDR !
Amendment No. 3/4.5-7
LIMITING CONDITIONS FOR OPERATION SURVElLLANCE REQUIREMENTS
( 3.5 CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING
, .g.YSTEMS SYSTEMS l D. Reactor Core isolation Coolina D. Reactor Core Isolation Coolina (RCIC)
(RCIC) System System i
whenever there is irradiated fuel in the j reactor vessel, reactor pressure is a. Simulated Once/ j l greater than 150 psig, and reactor Automatic Operating 1 l coolant temperature is greater than Actuation Test Cycle 365 F, except as specified in 3.5.D.2 1 l below. b. Pump When tested as l Operability specified in j l 2. From and after the date that the RCIC 3.13, verify that l l system is made or found to be the RCIC pump inoperable for any reason, continued delivers at least l reactor operation is permissible only 400 GPM at a l during the succeeding 14 days unless system head such system is sooner made operable, corresponding to l providing that during such 14 days the a reactor pressure HPCIis operable. of 1126 psig.
- 3. If the requirements of 3.5.D cannot be c. Motor As Specified l met, an orderly shutdown of the reactor Operated in 3.13
! shall be initiated and the reactor shall be Valve i l In the Cold Shutdown Condition within Operability l 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/
150 psig. operating cycle
! verify that the l RCIC pump l delivers at least l 400 GPM at a
! system head corresponding to l a reactor pressure l of 150 psig. This surveillance may be satisfied by an l equivalent test The RCIC pump shall deliver at least 400 GPM for a system head corresponding to a reactor pressure range of 1126 to 150 psig.
Amendment No. 3/4.5-8
HPCI Sy;t:m B 3/4.5.C B 3/4.5 CORE AND CONTAINMENT COOLING SYSTEMS 3/4.5.C. High Pressure Coolant injection (HPCI) System BASES 1
BACKGROUND HPCI is provided to assure that the reactor core is adequately cooled to i 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. HPCI permits the reactor to be shut down while maintaining sufficient reactor vessel water level inventory until the vesselis depressurized. HPCI 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 1126 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 HPOl 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.
APPLICABLE The limiting conditions for operating the HPCI System are derived from SAFETY ANALYSIS the Station Nuclear Safety Operational Analysis (FSAR Appendix G) and a detailed functional analysis of the HPCI System (FSAR Section 6).
SPECIFICATION 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.
ACTION 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 offsite AC 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. (continued) l Amendment No. B3/4.5-18
HPCI Syr. tim l B 3/4.5.C f
j B 3/4.5 CORE AND CONTAINMENT COOLING SYSTEMS BASES a
SURVEILLANCES The testing interval for the core and containment cooling systems is l based on industry practice, quantitative reliability analysis, judgment l
and practicality. The core cooling systems have not been designed to be fully testable during operation. For example, in the case of the HPCI, automatic initiation during power operation would result in pumping cold water into the reactor vessel which is not desirable. To increase the availability of the core and containment cooling systems, the components which make up the system; i.e., instrumentation, l pumps, valves, etc., are tested frequently. The pumps and motor j operated valves are tested in accordance with ASME B&PV Code,Section XI (IWP and IWV, except where specific relief is granted) to j assure their operability. The frequency and methods of testing are
- described in the PNPS IST program. The PNPS IST Program is used l to assess the operational readiness of pumps and valves that are safety-related or important to safety. When components are tested and '
found inoperable the impact on system operability is determined, and corrective action or Limiting Conditions of Operation are initiated. A simulated automatic actuation test once each cycle combined with code j inservice testing of the pumps and valves is deemed to be adequate l testing of these systems.
l The HPCI pump test corresponding to a reactor pressure of 150 psig may be performed with the restricting orifice removed from or installed in the return line to the condensate storage tanks. If the restricting orifice is removed the HPCI pump shall deliver 4250 GPM. If the l- restricting orifice is installed, an equivalent test for the HPCI pump is l permissible. The acceptance criteria for the equivalent test is derived l to demonstrate equal or greater level of pump performance in terms of l brake horsepower but at a higher pump head and lower flow rate.
l The surveillance requirements provide adequate assurance that the core and containment cooling systems will be operable when required.
l l
Amendment No. B3/4.5-19 I
RCIC Sy t:m B 3/4.5.D B 3/4.5 CORE AND CONTAINMENT COOLING $lfSTEMS l , 3/4.5.D. Reactor Core Isolation Cooling (RCIC) System l BASES 1
l BACKGROUND The RCIC is designed to provide makeup 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 offsite power in the event that HPCI is unavailable. The pumping capacity of the RCIC system is sufficient to maintain the water level above the core without any other system available to supply water to ;
the reactor core. The RCIC system is designed to pump 400 gpm at reactor pressures between 1126 and 150 psig. In all other postulated accidents and transients, the ADS provides redundancy for the HPCI.
SPECIFICATION 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.
ACTION Based on this and judgments on the reliability of the HPCI system, an allowable repair time of 14 days is specified.
SURVEILLANCES The testing interval for the core and containment cooling systems is based on industry practice, quantitative reliability analysis, judgment and practicality. The core cooling systems have not been designed to be fully testable during operation. To increase the availability of the core and containment cooling systems. ihe components which make up the system; i.e., instrumentation, pumpe,, valves, etc., are tested frequently. The pumps and motor operated valves are tested in accordance with ASME B&PV Code,Section XI 9WP and IWV, except where specific relief is granted) to assure their operability. The frequency and methods of testing are described in the PNPS IST program. The PNPS IST Program is used to assess the operational readiness of pumps and valves that are safety-related or important to safety. When components are tested and found inoperable the impact on system operability is determined, and corrective action or Limiting Conditions of Operation are initiated. A simulated automatic actuation test once each cycle combined with code inservice testing of the pumps and valves is deemed to be adequate testing of these systems.
The RCIC pump test corresponding to a reactor pressure of 150 pounds psig may be performed with the restricting orifice removed from or installed in the return line to the condensate storage tanks. If the restricting orifice is removed, the RCIC pump shall deliver 400 GPM. If the restricting orifice is installed, an equivalent test for the RCIC pump is permissible. The acceptance criteria for the equivalent test is derived to demonstrate equal or greater level of pump performance in terms of brake horsepower but at a higher pump head and lower flow rate. 1 The surveillance requirements provide adequate assurance that the core and containment cooling syster..s will be operable when required.
Amendment No. B3/4.5-20
r- 1 2
ATTACHMENT 3 - BECo LETTER 2.99.041 4 l
MARKED UP PAGES I .
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i j
! I i
i l
i i
i 1
1
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5 CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING SYSTEMS SYSTEMS C.- HPCI System C. HPCI system
]
- 1. The HPCI system shallbe 1. HPCI system testing shall be as i operable whenever there is _ follows:
irradiated fuel in the reactor vessel, L
f reactor pressure is greater than 150 psig., and reactor coolant
- a. Simulated Automatic Once/
Operating
/
temperature is greater than 365'F, Actuation Cycle f except as specified in 3.5.C.2 Test i below. ,
y b. Pump When tested
/ 2. From and after the date that the Operability as specified in f HPCI system is made orfound to 3.13, verify ,
/ be inoperable for any reason, that the HPCI /
[ /
continued reactor operation is permissible only during the pump delivers at least 4250 succeeding 14 days unless such GPM for a / l
/1 system is sooner made operable, system head prt ...iing that during such 14 days corresponding
/ all active components of the ADS to a I system, the RCIC system, the reactor LPCI system and both core spray
{ j systems are operable. Il? b @ pressure sig. of
,/ r 3 . If the requirements of 3.5.C cannot c. Motor As Specified in
/ be met, an order 1y shutdown of the Operated 3.13 / 1
,,e reactor shall be initiated and the Valve '
reactor shall be in the Cold Operability /-
"1 , - Shutdown Condition 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/ y 150 psig. operating cycle, verify - ,
that the HPCI pump delivers l at least {
4250 GPM for j a system head -
[M w M a k coiTesponding /
(#YG "'^" 'b'h,*
The HPCI pump shall deliver at least 4250 GPM for a system head
((
co sponding to a reactor pressure of o 150 psig.
l/26 Amendment No. h 3/4.5-7 l
n l
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5 CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING SYSTEMS SYSTEMS D. Reactor Core isolation Coolina D. Reactor Core isolation Coolina (RCIC) i (RCIC) System System
[
j- 1. The RCIC system shall be 1. HPCl ystem testing shall be as y operable whenever there is foiows:
l
',/ irradiated fuel in the reactor vessel,
) reactor pressure is greater than AC /C a. Simulated Once/ '
// 150 psig, and reactor coolant Automatic Operating ,
, temperature is greater than 365'F, Actuation Test Cycle -
except as specified in 3.5.D.2
, below. b. Pump When tested as Operability specified in ]
f 2. From and after the date that the 3.13, verify that '
/ RCIC system is made or found to the RCIC pump -
be inoperable for any reason, '
delivers at least continued reactor operation is 400 GPM at a l ,
- permissible only during the system head '
/ succeeding 14 days unless such corresponding
/ system is sooner made operable, to a reactor -
' t providing that during such 14 days ;j g g ure siof j the HPCIS is operable. e g.
3 If the requirements of 3.5.D cannot c. Motor As Specified t
, be met, an orderly shutdown of the Operated in 3.13 f, -
/ '
reactor shall be initiated and the Valve reactor shall be in the Cold Operability !,, -
Shutdown Condition within d 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/ j 150 psig, operating cycle verify that the
/
)- 4 l
RCIC pump , j delivers at least
{
400 GPM at a
- system head 7
to r actor gl"%~r" m;g [
e RCIC pump shall deliver at least /
400 GPM for a system head corresponding to a reactor pressure of '
to 150 psig.
//M Amendment No.h 3/4.5-8 l
r HPCl Syttam B 314.5.C B 3/4.5 CORE AND CONTAINMENT COOLING SYSTEMS 3/4.5.C. .
High Pressure Coolant injection (HPCI) System
~
BASES Background HPCI 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. HPCI permits the reactor to be shut down while maintaining sufficient reactor vessel water level inventory until the vessel is depressurized. HPCI continues to operate until reactor vessel pressure is below the pressure at which LPCI opercion or Core Spray System operation maintains core cooling.
The cepacity of the system is selected to provide this required core
! cooling. The HPCI nps designed to pump 4250 gpm at reactor pressures betw_ .7 nd 150 psig. Two sources of water are
// M available. Initially, mineralized 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 i
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.
APPLICABLE The limiting conditions for operating the HPCI System are derived from SAFETY ANALYSIS the Station Nuclear Safety Operational Analysis (FSAR Appendix G) and a detailed functional analysis of the HPCI System (FSAR Section 6).
i SPECIFICATION The requirement that HPCI be operable when reactor coolant 4 l 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 ACTION The analysis in FSAR Appendix G shows that the ADS provides a i single failure proof path for depressurization for postulated transients and accidents. The RCIC is required as an attemnte source of makeup to the HPCI only in the case of loss of all offsite AC 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. (continued)
Amendment No B3/4.5-18
I' D 3/4.5 CORE AND CONTAINMENT COOLING SYSTEMS dASES SURVEILLANCES The testing interval for the core and containment cooling systems is based on industry practice, quantitative reliability analysis, judgment
' and practicality. The core cooling systems have not been designed to I be fully testable during operation. For example, in the case of the HPCI, automatic initiation during power operation would result in pumping cold water into the reactor vessel which is not desirable. To increase the availability of the core and containment cooling systems, the components which make up the system; i.e., instrumentation, l pumps, valves, etc., are tested frequently. The pumps and motor l operated valves are tested in accordance with ASME B&PV Code, l Section XI (lWP and IWV, except where specific relief is granted) to l assure their operability. The frequency and methods of testing are i
described in the PNPS IST program. The PNPS IST Program is used to assess the operational readiness of pumps and valves that are safety-related or important to safety. When components are tested i
and found inoperable the impact on system operability is determined, i
and corrective action or Limiting Conditions of Operation are initiated.
A simulated automatic actuation test once each cycle combined with l code inservice testing of the pumps and valves is deemed to be adequate testing of these systems.
The surveillance requirements provide adequate assurance that the
! core and containment cooling systems will be operable when required.
l r[ ' V r
/ The HPCI pump test corresponding to a reactor pressure of 150 psig may be performed with the restricting orifice removed from or installed
! in the retum line to the condensate storage tanks. If the restricting orifice is removed the HPCI pump shall deliver 4250 GPM. If the I
restricting orifice is installed, an equivalent test for the HPCI pump is l
permissible. The acceptance criteria for the equivalent test is derived to demonstrate equal or greater level of pump performance in terms of brake horsepower but at a higher pump head and lower flow rate.
l T #
l l
Amendment No. B3/4.5-19 l I
, . 0.3/4.5 l CONTAINMENT COOUNG SYSTEMS 3/4.6.D. R i 3clati:n Colling (RCIC) Syst;m
- CASES _/ eg .g l'
- e BAC,KGR RCIC is designed to provide makeup to the nuclear system as o [s rt of the planned operation for periods when the nonnal heat sink is 4 navailable. The Station Nuclear Safety Operational Analysis, FSAR Appendix G, shows that RCIC also serves as redundent makeup S OE'/ /,,/4 /[
.e x p
g system on total loss of all offsite power in the event that HPCI is unavailabluin all other postulated accidents and transients, the ADS provides redundancy for the HPCI.
The requirement that RCIC be operable when reactor coolant l
j temperature is greater than 365'F is included in Specification 3.5.D.1 U
. q. 8 to clarify that RCIC need not be operable during certain testing (e.g.,
p reactor vessel hydro testing at high reactor pressure and low reactor y/W[" coolant temperature). 365'F is approximately equal to the saturation steam temperature at 150 psig.
I Based on this and judgments on the reliability of the HPCI system, an allowable repair time of 14 days is specified.
ILt.ANCES The testing interval for the core and containment cooling systems is I I
based on industry practice, quantitative reliability analysis, judgment
= and pmeticality. The core cooling systems have not been designed to j be fully testable during operation. To increase the availability of the core and containment cooling systems, the components which make
( ~ '" ~ .., r..
e up the system; i.e., instrumentation, pumps, valves, etc., are tested
/j{b t
l t #Rj frequently. The pumps and motor operated valves are tested in gE g accordance with ASME B&PV Code,Section XI (IWP and IWV, f a. a - e except where specific relief is granted) to assure their operability.
8ENO 9 E The frequency and methods of testing are described in the PNPS IST
{.E*h@22 g program. The PNPS IST Program is used to assess the operational E
gT.3gyj!y 3 $ E -- t y a
readiness of pumps and valves that are safety-related or important to safety. When components are tested and found inoperable the impact on system operability is determined, and corrective action or
[
$ l }ii S ri j .2.g ! te Limiting Conditions of Operation are initiated. A simulated automatic 4
b of' " fo O g actuation test once each cycle combined with code inservice testing of the pumps and valves is deemed to be adequate testing of these
}l @'IR. E -lE jd rem systems.
I
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E j g f.R E T
.!gE %m e ea a mtp The surveillance requirements provide adequate assurance that the core and containment cooling systems will be operable when jj jj3 k required. j la " 2 2 @ ,! w b e5 85ee . u.oze s 873 a 3
ili815h !j.$E gI$
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B3/4.5-20 l l8I$sy$M. 128
_ _ . _ _ _