ML20045F240
| ML20045F240 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/01/1993 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20045F189 | List: |
| References | |
| NUDOCS 9307070124 | |
| Download: ML20045F240 (12) | |
Text
_ _ _ _ _ _ _ _
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AlTACHMENT 1 CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET 50-155 AS PROPOSED PAGES
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9307070124 930701 PDR ADOCK 05000155 P
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a limitino Condition for Operation Surveillance Recuirement 11.3.1.4 EMERGENCY CORE COOLING SYSTEM 11.4.1.4 -EMERGENCY CORE COOLING SYSTEM Applicability:
Applicability:
Applies to the operating status of the Applies to periodic testing requirements emergency core cooling system.
for the emergency core cooling system.
i Ob.iective:
Ob.iective:
To assure the capability of the emergency To verify operability of the emergency core
. core cooling' system to cool reactor fuel cooling systems. of Coolant Accident.
in the event.of a loss of Coolant Accident.
i Specification:
Specification:
A.
The two core spray systems (original and A.
Each month the following shall be performed:
redundant) shall be operable whenever the plant is in a power operation condition.
Verify the operability of M0-7051, -7061 The original core spray system shall also be
-7070, -7071, and -7066 by remote. manual operable during refueling operations.
The fire actuation.
suppression system can be used for routine purposes without declaring the core spray Leak testing of the core spray heat system inoperable provided total flow drawn exchanger.
from the system is limited to.400 gpm'and i
provided such routine uses do not exceed Automatic actuation of both fire pumps and run
/-
30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> / year.
The fire suppression system can the electric for at least 5 minutes and diesel
/
be used for fire fighting or for tests involving for at least 30 minutes.
/
only ' flow through the fire suppression system relief valves without declaring the core spray Verify that valve VPI-19 is locked or sealed system inoperable and without a flow and annual in open position.
time restriction.
Verify' the deluge system automatic isolation B.
The core spray recirculation system shall be valve CV-4101 for the substation transformer operable whenever the plant is in a power area closes on any core spray valve open operation condition.
signal.
Verify T-handle override for valve CV-4101.is sealed in closed / auto position.
~'
C.
The core spray recirculation heat exchanger shall not be taken out of service during power operation Verify that the hose required for backup for periods exceeding four (4) hours.
The heat cooling water;to the core spray recirculation exchanger-shall. be considered inoperable and out of heat exchanger'is installed on a designated service if tube bundle leakage exceeds 0.2 gpm.
rack in'the screenhouse.
II 93 AS PROPOSED
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- L Limitina Condition for Operation Surveillance Reauirement 11.3.1.4 EMERGENCY CORE COOLING SYSTEM (Contd) 11.4.1.4 EMERGENCY CORE COOLING SYSTEM (Contd) a D.
Both fire pumps-(electric and diesel) and B.
At each major refueling outage, the the piping' system to the core spray system following shall be performed:
tie-ins shall be operable whenever the plant is in a power operation condtion and refueling.
Calibration of core spray system actuation and pressure and flow instrumentation.
E.
If Specifications A, B, C, and D are not met, i
a normal orderly shutdown shall be initiated Verify that the two core spray system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the reactor shall be containment isolation check valves are not shut down as described in Section 1.2.5(a) stuck shut.
within twelve (12) hours and shut down as described in Section 1.2.5(a) and (b) within Calibration of fire system basket strainer the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
No work shall be differential pressure switches.
performed on the reactor or its connected systems when irradiated fuel is in the reactor Operability check of the core spray vessel which could result in lowering the recirculation system through the test reactor water level below elevation 610' 5".
tank flow path. During the core spray recirculation system operability check F.
If both core spray systems become inoperable, reduce any leakage to as low as practical the plant shall be brought to shutdown from components outside containment prior condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to the cold to returning system to service.
shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Verify manual and automatic actuation of the core spray system valves M0-7051, -7061, -7070, G.
Instrument set points shall be as specified and -7071 with water flow normally blocked.
in Table 11.3.1.
i!erify manual actuation of MO-7066.
Verify that the hose used for backup cooling water to the core spray recirculation heat exchanger is operable and free of obvious defects.
Perform a leak check and flow check of the backup cooling water hose when connected between the screen house fire water connection and the core spray recirculation heat exchanger.
94 l
AS PROPOSED
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Limitina Condition for Operation Surveillance Recutrement 11.3.1.4 EMERGENCY CORE COOLING SYSTEM (Contd) 11.4.1.4 EMERGENCY CORE COOLING SYSTEM (Contd)
Verify that the electric and diesel fire. pump
/
performance meets the capacity requirements of
- / -
Table ll.3.1.4(b).
-/-
C.
Instruments shall be checked, tested, and calibrated at least as frequently as listed in Table ll.4.1.4(a).
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TABLE 11.3.1.4b Fire Pump Acceptance Criteria 1
200 t
190 3
180 i
170 160 7
~
150 m
l N
s
'4 s
mC) 130
--~
N
~"
m Diesel
'25 120
/
1 mn s
V 11C x
v o
\\
Q 5t s
100 x
u p
N D
s g
Electric NQ x
G)
N%
7o u
60 50 Note: For ECCS acceptance criteria (on or above the curve) the operating range of 40 the electric fire pump is 100-750 gpm and the diesel fire pump operacing range 30 g
is 450-900 gpm.
1C i
g; C
E O
100 200 300 400 500 600 700 800 900 1000 1100 1200 1300 1400 1500 1600 1700 1800 1900 2000 50 150 250 350 450 550 650 750 850 950 1050 1150 1250 1350 1450 1550 1650 1750 1850 1950 M
Flow (gpm)
-r--
s-w,,.,. - -, - -,,,
,.c
.,g--
, _.-,- ---i.
m w
v, w
-.w-.
v.-
Bases:
The core spray system consists of two automatically actuated independent double capacity piping headers capable of cooling reactor fuel for a range of loss of Coolant Accidents.
Either system by itself is capable of providing adequate cooling for postulated large breaks in all locations. When adequate depressurization rates are achieved in the postulated small-break situation, either core spray system provides adequate cooling.
For the largest possible pipe break, a flow rate of approximately 400 gpm is required after about 45 seconds. Adequate core cooling is assured when the primary core spray flow is'
/
2 292 gpm or the back-up core spray flow is 2 296 gpm.
/
Each core spray system has 100% cooling capacity from each spray header and each pump set.
Thus, speci fying both systems to be fully operational will assure, to a high degree, core cooling if the core spray system is required.
In addition, the primary core spray is required to be operable during refueling operations to provide fuel cooling in the unlikely event of an inadvertent draining of the reactor vessel. Water flow from the fire suppression system for fire suppression or for normal uses and testing for which the time and flow are restricted has a negligible effect on availability and is not a cause for declaring the systems inoperable.
The core spray systems receive their water supply from the plant fire system.
The plant fire system supply is_from Lake Michigan via two redundant 1,000 gpm fire pumps, one electric and one diesel driven.
Performance
/
. curves'for the pumps were developed using FLOWNET computer code of the ECCS System.
Evaluation of the most
/
limiting ECCS failures concludes adequate core cooling is achieved under these conditions.
These pumps start
/
automatically on decaying fire system pressure.
If a passive failure of underground fire main piping should occur during the long-term cooling phase, the capability exists to bypass the affected portion of piping utilizing a ' fire hose to ensure the continuation of long-term ECCS cooling.
The core spray recirculation system is provided to prevent excessive water buildup in the containment sphere and to provide for long-term, post-accident cooling.
The system consists of two pumps.(400 gpm each) and a heat exchanger.
The pumps take a suction from the lower levels of containment and discharge.to the core spray headers.
The system is actuated manually when the water level in the containment rises to elevation 587 feet. The 587-foot elevation will be achieved between 6 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> operation of one core spray and one containment spray system.
A test tank and appropriate valving is provided in the core spray recirculation system so the pump suction conditions and the flow characteristics of the system can be periodically tested.
I One core spray recirculation pump has adequate capacity to provide fuel cooling at any time following a Loss of Coolant Accident.
Continuous containment spray operation is not required during the post-accident recirculation phase if only one recirculation pump is available.
.96 AS PROPOSED ~
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i SURVEILLANCE RE_QUIREMENTS l
t 4.7.11.1.1 The FIRE SUPPRESSION WATER SYSTEM shall be demonstrated OPERABLE:
L a.
Once.per 7 days verifying the Intake Bay water level is above i
570' elevation.
b.
At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM-D270-65, i
is within the acceptable limits specified in Table 1 of ASTM-D975-74 with respect to viscosity, water content and sediment.
c.
Once per 18 months:
/
1.
By a system flush and by verifying that each valve in the flow path that is not locked, sealed or otherwise secured in position,-
l is in its correct position.
j 2.
Subjecting the diesel to an inspection in accordance with
/
procedures prepared in connection with its manufacturer's recommendations for the class of service.
d.
Once per 3 years by performing flow tests to meet or exceed the requirements of Section 11, Chapter 5 of the Fire Protection Handbook,14th Edition published by National Fire Protection Association.
r 4.7.11.1.2 The fire pump diesel starting 24-volt battery bank and charger f
shall be demonstrated OPERABLE:
a.
At least once per 7 days by verifying that:
[
1.
The electrolyte level of each battery is above the plates, and i
2.
The overall battery voltage is 2 24 volts.
b.
At least once per 92 days by verifying that the specific gravity is appropriate for continued service of the battery.
c.
At least once per 18 months by verifying that:
]
a-1.
The batteries and battery racks show no visual indication l
of physical damage or abnormal deterioration, and
-l 2.
The battery-to-battery and terminal connections are clean, l
tight, free of corrosion and coated with anti-corrosion j
material.
119 AS PROPOSED-
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1 ATTACHMENT 2 CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET 50-155 EXISTING TECHNICAL SPECIFICATION PAGES 1
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Surveillance Requirement I
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Limiting Condition for Operation f
3.1.4 EMERCENCY CORE COOLING SYSTEM 11.4.1.4 EMERCENCY CORE COOLING SYSTEM Applicability:
Applicability:
Applies to the operating status of the Applies to periodic testing requirements emergency core cooling system.
for the emergency core cooling system.
Objective:
Objective:
To assure the capability of the emergency To verify operability of the emergency core cooling system to cool reactor fuel core cooling systems.
in the event of a Loss of Coolant Accident.
Specification:
Specification:
A.
The two core spray systems (original and A.
Each month the following shall be performed:
redundant) shall be operable whenever the plant is in a power operation condition.
Verify the operability of HO-7051, -7061 The original core spray system shall also be
-7070, -7071, and -7066 by remote manual operable during refueling operations. The fire actuation.
suppression system can be used for routine purposes without declaring the core spray Lesk testing of the core spray heat system inoperable provided total flow drawn exchanger.
from the system is limited to 400 gpm and provided such routine uses do not exceed Automaticgetuaionofboth{irepumps,dkI2/ves 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> / year. The fire suppression system can Qq$ g %%g4 ptyy M be used for fire fighting or for tests involving Verify that valve VPI-19 is locked or ses5ed' only flow through the fire suppression system in open position.
relief valves without declaring the core spray system inoperable and without a flow and annual Verify the deluge system automatic isolation time restriction.
valve CV-4101 for the substation transformer area closes on any core spray valve open B.
The core spray recirculation system shall be signal. Verify T-handle override for valve operable whenever the plant is in a power CV-4101 is sealed in closed / auto position.
operation condition.
Verify that the hose required for backup C.
The core spray recirculation heat exchanger shall cooling water to the core spray recirculation not be taken out of service during power operation heat exchanger is installed on a designated for periode exceeding four (4) hours. The heat rack in the screenhouse.
exchanger shall be considered inoperable and out of service if tube bundle leakage exceeds 0.2 gps.
93 Amendment 107
~ 1.imiting Condition for Operation Surveillance Requirement l
1.1.4 EMERCENCY CORE COOLINC SYSTEM (Contd) 11.4.1.4 EMERCENCY CORE COOLING SYSTEM (Contd)
D.
Both fire pumps (electric and diesel) and B.
At each major refueling outage, the f
the piping system to the core spray system following shall be performed:
tie-ins shall be operable whenever the plant is in a power operation condtion and refueling.
Calibration of core spray system actuation and pressure and flow instrumentation.
l E.
If Specifications A, B, C, and D are not met, a normal orderly shutdown shall be initiated Verify that the two core spray system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the reactor shall be containment isolation check valves are not shut down as described in Section 1.2.5(a) stuck shut.
within twelve (12) hours and shut down as described in Section 1.2.5(a) and (b) within Calibration of fire system basket strainer the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. No work shall be differential pressure switches.
performed on the reactor or its connected systems when irradiated fuel is in the reactor Operability check of the core spray vessel which could result in lowering the recirculation system through the test reactor water level below elevation 610' 5".
tank flow path.
During the core spray recirculation system operability check F.
If both core spray systems become inoperable, reduce any leakage to as low as practical the plant shall be brought to shutdown from components outside containment prior condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to the cold to returning system to service, shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Verify manual and automatic actuation of the core spray system valves MO-7051, -7061, -7070, C.
Instrument set points shall be as specified and -7071 with water flow normally blocked.
in Table 11.3.1.
Verify manual actuation of MO-7066.
Verify that the hose used for backup cooling water to the core spray recirculation heat exchanger is operable and free of obvious defects.
Perform a leak check and flow check of the backup EJL\\
g ge4m O
cooling water hose when connected between the screen house fire water connectaon and the core glgd R /t.ci,.
[A>}D pe#
Nh1 spray recirculation heat exchanger.
%b C P
C.
Instruments shall be checked, tested, and 7*gb
(*g*
- g *q calibrated at least as frequently as listed in Table 11.4.1.4(a).
94 Amendment, 107 p,
e..
,e
,en.
l i
Bases:
The core spray system consists of two automatically actuated independent double capacity piping headers capable of cooling reactor fuel for a range of Loss of Coolant Accidents.
Ei;her system by itself is capable of providing adequate cooling for postulated large breaks in all loca.tions. When adequate depressurization rates are achieved in the postulated small-break situation, either core spray system provides adequate cooling.
For the largest possible pipe break, a flow rate of approximately 400 gpm is required after about 45 seconds. Te "ree Adequate core cooling the primary core spray flow muct be is f
g**"
"~
2 292 gpm or the back-up core spray flow met-be 2 296 gpm.
7s Each core spray system has 1007 cooling capacity from each spray header and each pump set.
Thus, specifying both systems to be fully operational will assure, to a high degree, core cooling if the core spray system is f
required.
In addition, the primary core spray is required to be operable during refueling operations to provide fuel cooling in the unlikely event of an inadvertent draining of the reactor vessel.
Water flow from the fire suppression system for fire suppression or for normal uses and testing for which the time and flow are restricted has a negligible effect on availability and is not a cause for declaring the systems inoperable.
c / pop The core spray systems receive their water sup 1-plant fire system.
The plant fire system supply is from Lake Michigan via two redundant 1,00 pgm ire pumps, one electric and one diesel driven. AThese pumps start automatically on decaying fire system pre sure.
If a passive failure of underground fire main piping N should occur during the long-term cooling phase, the capability exists to bypass the affected portion of piping utilizing a fire hose to ensure the continuation of long-term ECCS cooling.
The core spray recirculation system is provided to prevent excessive water buildup in the containment sphere and to provide for long-term, post-accident cooling.
The system consists of two pumps (400 gpm each) and a heat exchanger. The pumps take a suction from the lower levels of containment and discharge to the core spray headers.
The system is actuated manually when the water level in the containment rises to elevation 587
/
feet. The 587-foot elevation will be achieved between 6 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> operation of one core spray and one containment spray system.
V' A test tank and appropriate valving is provided in the core spray recirculation system so the pump suction y
conditions and the flow characteristics of the system can be periodically tested.
One core spray recirculation pump has adequate capacity to provide fuel cooling at any time' following a loss of Coolant Accident.
Con inuous containment spray operation is not required during the post-accident recirculation phase if only one recirculation pump is available.
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SURVEll. LANCE REQUIREMENTS 4.7.11.1.1 Th3 FIRE SUPPRESSION WATER SYSTEM shall be demonstrated OPERA 8Lgt.
Once per 7 days verifying the Intake Bay water level is-above s
a.
570' elevation.
f f, 6(, (. "(.. A )
i JM ( ~ 504 s
b.
Once per 31 days by start w,
lilroperating the electric driven p east five minutes and the diesel pump.for at minutes.
i c.
At least once per 92 days by verifying that a sample'of diesel feet from the fuel storage tank, obtained in accordance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTH-D975-74 with respect to viscosity, water content and sediment.
d.
Once per 18 monthet 1.
By a system flush and by verifying that each valve. la the flow i
path that is not locked, sealed or otherwise secured in position, is in its correct position.
gfy cd 2.
By performing a syste netWs4-d.' i. ancludes simulated
~
ymath metastimrot the system throughout its operating sequence.
h.
3.
By verifying that e c y ; -;ill L E1Tp a flow of at least
-.100% at a system head of 110 psi.
4.
Subjecting the diesel to an inspection in accordance with procedures prepared in connection with its manufacturer's recommendations for the class of service.
i e.
Once per 3 years by performing flow tests to meet or exceed the requirements of Section 11, Chapter 5 of the Fire Protection Bandbook, 14th Edition published by National Fire Protection l
Association.
4.7.11.1.2 The fire pump diesel starting 24-volt battery bank and charger shall be demonstrated OPERABLg At least once per 7 days by verifying that:
a.
f 1.
The electrolyte level of each battery is above the plates, and l
2.
The overall battery voltage is 2 24 volts.-
b.
At least once per 92 days by verifying that the specific gravity is appropriate for continued service of the battery..
At least once per 18 months by. verifying thatt c.
1.
The batteries and tattery racks show no visual indication of physical damage or abnormal deterioration, and 2.
The battery-to-battery and terminal connections are-clean,-
tight, free of corrosion and coated with anti-corrosion material.
119 Amendment 107 February'19, 1992 TS SFCTION 12 s'
l
l l
Basest The core spray system consists of two automatically actuated independent double capacity piping beaders i
capable of cooling reactor fuel for a range of Loss of Coolant, Accidents. Either system by itself is
}
capable of providing adequate cooling for postulated large breaks in all locations. When adequate l
depressurization rates are achieved in the postulated small-break situation, either core spray system provides adequate cooling. For the largest possible pipe break, a flow rate of approximately 400 gpm is
(.
O C-W CO/e S php required after about 4 seconds. TO MWc..OrpN CNC Tk % ck.-9 We 5 pr b mer 7,gg
, ? (, ppm lw 2 ed c2. g p
=^.
GLn r mdST t
Each core spray system has 100% cooling capacity from each spray header and each pump set.
Thus. specifying both systems to be fully operational will assure, to a high degree, core cooling if the core spray system is required.
In addition, the primary core spray is required to be operable during refueling operations to provide fuel cooling in the unlikely event of an inadvertent draining of the reactor vessel. Water flow from the fire suppression system for fire suppression or for normal uses and testing for which the time and flow are restricted has a negligible effect on availability and is not a cause for declaring the systems inoperable.
The core spray systems receive their water supply from the plant fire system. The plant fire system supply is from Lake Michigan via two redundant 1,000 pgm fire pumps, one electric and one diesel driven. These pumps start automatically on decaying fire system pressure. If a passive failure of underground fire main piping should occur during the long-term cooling phase, the capability exists to bypass the affected portion of piping utilizing a fire hose to ensure the continuation of long-term ECCS cooling.
The core spray recirculation system is provided to prevent excessive water buildup in the containment sphere and to provide for long-term, post-accident cooling. The system consists of two pumps (400 spm each) and a heat exchanger., The pumps take a suction from the lower levels of containment and discharge to the core spray headers. The system is actuated manually when the water level in the containment rises to elevation 587 feet. The 587-foot elevation will be achieved between 6 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> operation of one core spray and one containment spray system.
A test tank and appropriate valving is provided in the core spray recirculation system so the pump suction conditions and the flow charscteristics of the system can be periodically tested.
One core spray recirculation pump has adequate capacity to provide fuel cooling at any time following a Loss of Coolant Accident. Continuous containment spray operation is not required during the post-accident recirculation phase if only one recirculation pump is available.
96 4
Amendment 107 February 19, 1992 WM P W Me
- At e 4 $
.. - - - -. - -