ML20002C838
| ML20002C838 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/12/1977 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20002C837 | List: |
| References | |
| NUDOCS 8101120141 | |
| Download: ML20002C838 (7) | |
Text
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Surveillance Requirement Limiting Conditions for Operation 11.3.1.4 E!4ERGENCY CORE COOLIrlG SYSTE!4 11.h.l.h E!!ERGENCY CORE COOLING SYSTD4 1
Anplicability :
iloplicability:
Applies to the operating status of the emer-Applies to periodic testing requirements for the emergency core cooling systems.
.gency core cooling system, Objective:
Objective:
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To assure the capability of the emergency To. verify operabi".ity of the emergency core
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core cooling system to cool reactor fuel in cooling systems.
the event of a Loss of Coolant Accident.
Speci fication :
OD*"
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A.
Each month the following shall be per-A.
The two core spray systems (original and formed:
l redundant) shall be operable whenever Leak testing of the core spray heat the plant ~is in a power operation con-dition. The original core spray system exchanger.
shall also be operable during refueling Automatic actuation of both fire pumps.
operations.
B.
The core spray recirculation system Verify the following valve locked or shall be operable whenever the plant sealed in the open position: MO-7069 is in a power operation condition.
.0 Verify the following valve locked or sealed in the shut position: Upstream C.
The core spray recirculation heat ex-manual isolation valve for transformer changer shall not be taken out of ser-vice during power operation for periods deluge valve.
exceeding four (h) hours. The heat exchanger shall be considered inoperable and out of service if tube bundle leak-t age exceeds 0.2 gpm.
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Limiting Conditions for Operation Surveillance, Requirement ll.3.1.h EMERGENCY CORE COOLING SYSTEM (Contd) ll.h l.h EMERGENCY CORE e00 LING SYSTEM (Contd)
D.
Both fire pumps (electric and diesel)
B.
At each major refueling outage _the and the piping system.to the core spray following shall be performed:
system tie-ins shall be operable when-ever the plant is in a power operation Manual and automatic actuation of the condition and refueling.
core spray system valves with water.
flow manually blocked (MO-7051. -7061, E.
If Specifications A, B, C, and D are not
-7070 and -7071).
met, a normal orderly shutdown shall be Manual actuation of valve MO-7066.
initiated within 2h hours and the reactor shall be shut down as described in Sec-Operability check of the Core Spray tion 1.2.5(a) within tweleve (12) hours Recirculation System.
and shut down as described in Section Perform pressure test of backup cooling 1.2 5(a) and (b) within the following supply hose for post-incident heat 2h hours.
No work shall be performed i
hanger.
1 on the reactor or its connected systems when irradiated fuel is in the reactor Calibration of core spray system pres-vessel which could result in lowering sure and flow instrumentation.
he reactor water level below elevation y gf containment isolation check valves are n t stuck shut.
F.
Instrument set points shall be as speci-fled in Table 11 3.1.ha.
Operability of the check valves between 10-7051 and MO-7061 and MO-7070 and MO-707)
Calibration of fire system basket strainer differential pressure switches.
C.
Instruments shall be checked, tested and
'l calibrated at least as frequently as listed in Table 11.h.l.ha.
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.m 132 TABLES 11.1.1.ha AND 11.h.1.ha Instrumentation That Initiates Core Spray 11.3.1.ha Limiting Conditions for operation 11.h.1.ha Surveillance Requirements Trip System Limiting Conditions for Instrument Instrument Parameter Logic Set Point operability Trip Test Calibration Open Core Spray Valves Low Reactor Water One of Two for 2%10'5"Elev Power Operation Quarterly Each Major Level (a)
Each of Two and Refueling Refueling Valves in Series Operations (b)
Primary Pressure One of Two for 3,200 Psig Power Operation Quarterly Each Major Low (a)
Each of Two and Refueling Refueling Valves in Series Operations (b)
Notes for Tables 11.3.1.ha and 11.h.1.ha (a)
Initiation of valve operation requires both low reactor water level coincident with low primary system l
pressure.
The primary core spray system shall be available for use during refueling operations. The backup core (b) spray system shall be inoperable during refueling operations with the valves blocked or otherwise defeated (while the piping section from the valves to the reactor head is dismantled).
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Bases:
f The core spray system consists of two automatically actuated independent double capacity piping headers cap-able 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 cool-For the largest possible pipe break, a flow rate of approximately h00 gpm is required af ter about 20 ing.
seconds.
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Each core spray system has 100% cooling capacity from each spray header and each pump set. Thus, specifying both systems to be fully operational vill assure to a high degree core cooling if the core spray system is required.
In addition, the original core spray is rdquired to be operable during refueling operations to provide fuel cooling in the unlikely event of an inadvertent draining of the reactor vessel.
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. These pumps start automatically on decaying fire system pressure.
If a passive failure of underground fire main piping j.
should occur during the long-term cooling phase, the capability exists to bypass the affected portion of pip-ing 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 (h00 gpm each) and a The pumps take a suction from the lover levels of containment and discharge to the core spray heat exchanger.
The system is actuated manually when the water level in the containment rises to elevation 587 feet.
The 587-foot elevation vill 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 f? :n characteristics of the system can be periodically tested.
One corb spray recirculation pump has adequate capacity to provide fuel cooling at anytime following a Loss of Coolant Accident. Continuous containment spray operation is not required during the Inst-accident recircula-tion phase if only one recirculation pump is available.
m Bases:
(Contd)
Some of The operable status of the various systems and components is to be demonstrated by periodic tests.
If a component is found to these tests will be performed while the reactor is operating in the pcser range.
be inoperable, it will be possible in most cases to effect repairs and restore the system to full operability For a single component to be inoperable does not negate the ability of the within a relatively short time.
system to perform its function, but it reduces the redundancy provided in the reactor design and thereby limits the ability to tolerate additional equipment failures.
If it develops that (a) the inoperable component is not repaired within the specified allowable time period; or (b) a second component in the same or related sys-tem is found to be inoperable, the reactor will initially be removed from service which will provide for a reduction of the decay heat from the fuel and consequential reduction of cooling requirements after a postu-If the malfunction cannot be rapidly corrected, the reactor will be cooled lated Loss of Coolant Accident.
to the shutdown condition using normal cooldown procedures.
In this condition, release of fission products or damage of the fuel elements is not considered possible.
l The plant operating procedures require immediate action to effect repairs of an inoperable component and,The therefore, in most cases, repairs will be completed in less than the specified allowable repair times.
limiting times to repair are intended to:
(1) Assure that operability of the component will be restored promptly and yet, (2) Allow sufficient time to effect repairs using safe and proper procedures.
The leakage rate limit for the core spray recirculation system heat exchanger has been established to assure detection of any degradation of the integrity of the heat exchanger.
By Commission Memorandum and Order dated May 26, 1976, Consumers Power Company was granted a plant life exemp-tion from the requirements of 10 CFR part 50, 50.46 and Appendix K, Paragraph ID1 as applied to a Loss of Coolant Accident (LOCA) caused by a break in a core spray line and a concurrent single failure of a valve in the remaining core spray system. This exemption was based on conditions specified in the Memorandum and Order and supporting documents with which Consumers Power Company has complied. Thus, these Technical Specifications are in part an augmentation of these conditions.
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NRC OlSTRIBUTION POn PART 50 DOCKET MATERIAL A E F uMENT sumers Power Company 8/12/77 Mr. Don K. Davis Jackson, Michigan DATE RECEIVED W. S. Skibitsky 8/15/77 lri.ETTE R ONOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED EORio!NAL BUNCLASSIFIE D Ccorv j pgpg -
otSCCtPTION ENCLOSU RE License No. DPR-6 Appl for Amend: tech specs proposed change concerning Emergency Core q;pt"'.'}
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