ML20053C629
| ML20053C629 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/20/1982 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20053C622 | List: |
| References | |
| 4159N, NUDOCS 8206020404 | |
| Download: ML20053C629 (6) | |
Text
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Quad Cities Unit 1 Proposed Amendment to DPR-29 Technical Specifications Revised Pages:
3.5/4.5-3 3.5/4.5-12
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4159N 8206020404 820520 PDR ADOCK 05000254 P
g QUAD-CITIES DPR-29 Should the loss of one RHR pump occur, a nearly full complement of core and containment cooling equipment is available. Three RHR pumps in conjunction with the core spray subsystem will perform the core cooling function. Because of the availability of the majority of the core cooling equipment, which will be demonstrated to be operable, a 30-day repair period is jusdfied. If the LPCI mode of the RHR system is not available, at least two RHR pumps must be available to fulfill the containment cooling function. The 7-day repair period is set on this basis.
B.
RHR Senice Water The containraent cooling mode of the RHR system is provided to remove heat energy from the containment in the event of a loss-of-coolant accident. For the flow specified, the containment long-term pressure is limited to less than 8 psig and is therefore more than ample to provide the required heat-removal capability (reference SAR Section 12.3.2).
The Containment Cooling mode of the RHR System consists of two loops.
L Each loop consists of 1 Heat Exchanger, 2 RHR Pumps, and the associated valves, piping, elect:. cal equipment, and instrumentation. The "B" loop on each unit containc 2 RHR Service Water Pumps. During the period from November 24, 1981, tt. July 1,1982, the " A" loop on each unit may utilize the " A" ano "d" RHR Service Water Pumps from Unit 2 via a cross-tie line. Af te; July 1, 1982, each "A" loop will contain 2 RHR Service Water Pumps.
Either set of equipment is capable of performing the containment cooling fianction. Loss of one RHR service water pump does not seriously jeopardize the containment cooling capability, as any one of the remaining three pumps can satisfy the cooling requirements. Since there is some redundancy left, a 30-day repair period is adequate. Loss of one loop of the containment
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cooling mode of the RHR system leaves one remaining system to perform the containment cooling function. The operable system is demonstrated to be operable each day when the above condition occurs.
Based on the fact that when one loop of the containment cooling mode of the RHR system becomes inoperable, only one system remains, which is tested daily, a 7-day repair period was specified.
C High-Pressure Coolant Injection The high-pressure coolant injection subsystem is provided to adequately cool the core for all pipe breaks smaller than those for which the LPCI mode of the RHR system or core spray subsystems can protect the core.
The HPCI meets this requirement without the use of offsite electrical power. For the pipe breaks for which the HPCI is intended to function, the core never uncovers and is continuously cooled, thus no cladding demage occurs (reference SAR Section 6.2.5.3). The repair times for the limiting conditions of operation were set considering the use of the HPCI as part of the isolation cooling system.
D. Automatic Pressure Relief The relief valves of the automatic pressure relief subsystem are a backup to the HPCI subsystem. They enable the core spray subsystem or LPCI mode of the RHR system to provide protection against the small pipe break in the event of HPCI failure by depressurizing the reactor vessel rapidly enough to actuate the core spr:y subsystems or LPCI mode of the RHR system. The core spray subsystem and/or the LPCI _
mode of the RHP, system provide sufficient flow of coolant tolimit fuelcladding temperaturestoless than 2200*F, to assure that core geometry remains intact, to limit the core wide clad metal-water reaction to less than 1%, and to limit the calculated local metal water reaction to less than 175 a
1 loss of 1 of the relief valves affects the pressure relieving capability and, therefore, s 7 day repair period is k
specified. Loss of more than one relief valve significantly reduces the pressure relief capability,thus a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
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repair period is specified based on the HPCI system availability during this period.
E ROC The RCIC system is provided to supply continuous makeup water to the reactor core when the reactor is isolated from the turbine and when the feetwater system is not available. Under these conditions the
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pumping capacity of the RCit' system is sufficient to maintain the water level above the core without any other water system in operation. If the water level in the reactor vessel decreases to the RCIC initiation level, the system automatically starts. The system may also be manually initiated at any time.
3.5/4.5-12
QUAD-CITIES DPR-29
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continued reactor operation is permis-containment cooling mode of the sible only during the succeeding 7 days RHR, and the diesel generators re-unless it is sooner made operable, pro-quired for operation of such compo-vided that during such 7 days all active nents if no external source of power components of both core spray subsys-were available shall be demonstrated tems, the containment cooling mode of to be eperable immediately and daily the RHR (includir.d two RHR thereafter.
pumps), and the diesel generators re-quired for operation of such compo-nents if no external source of power were available shall be operable.
6.
If the requirements of Specification 3.5.A cannot be met, an orderly shut-down of the reactor shall be initiated, and the reactor shall be 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 />.
B.
Containment Cooling Mode of the RHR B.
Containment Cooling Mode of the RHR System System Surveillance of the containment cooling mode of the RHR system shall be performed as follows:
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1.a.
Both loops of the containment cooling mode 1.
RHR service water subsystem testing:
of the RHR system, as defined in the bases for Specification 3.5.0, shall be operable whenever irradiated fuel is in the reactor llem frequency vessel and prior to reactor startup from a cold condition, a.
Pump and valve Once/3 operability months 1.b.
From the effective date of this amendment b.
Flow rate test -
After pump until July 1,1982, the "A" loop of the each RHR service maintenance containment cooling mode of the RHR system for each reactor may share the Unit 2 "A" water pump shall and every 3 i
and "B" RHR service water pumps using de}jver at least months cross tie line 1/2-10124-16"-D.
3500 gpm against Consequently, the requirements of Specifications 3.5.B.2 and 3.5.B.3 will a pressure of 198 impose the corresponding surveillance psig testing of equipment associated with both reactors if the shared RHR service water c.
A logic system Each pump or pumps, or the cross tie line, are functional test refueling made or found to De inoperable.
outage
- 2. From and after the date that one of the
- 2. When it is determined that one RHR RHR service water pumps is made or service water pump is inoperable, the found to be inoperable for any reason, remaining components of that loop continued reactor operation is permis-and the other containment coc'ing sible only during the succeeding 30 loop of the RHR system shall be dem-days unless such pump is sooner made onstrated to be operable immediately operable, provided that during such 30 and daily thereafter.
days all other active cornponents of the i
containment cooling mode of the RHR system are operable.
3.5/45-3 1
3 Quad Cities Unit 2 Proposed Amendment to DPR-30 Technical Specifications Revised Pages:
- 3. 5 /4. 5-3 3.5/4.5-11 l
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4159N
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QUAD-CITIES DPR-30 continued reactor operation is permis-containment cooling mode of the 4
sible only during the succeeding 7 days RHR, and the diesel generators re-unless it is sooner made operable, pro-quired for operation of such compo -
vided that during such 7 days all active nents if no external source of power components of both core spray subsys-were available shall be demonstrated tems, the containment cooling mode of to be operable immediately and daily the RHR (including two RHR thereafter.
pumps), and the diesel generators re-quired for operation of such compo-nents if no external source of power were available shall be operable.
- 6. If the requirements of Specification 3.5.A cannot be met, an orderly shut-down of the reactor shall be initiated, and the reactor shall be 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 />.
B.
Containment Cooling Mode of the RHR B.
Containment "ooling Mode of the RHR System System Surveillance of the containment cooling mode of the RHR system shall be performed as follows:
1.a.
Both loops of the containment cooling hiode of the RHR system, as defined in the bases U"
N'P'9 for Specification 3.5.0, shall be operable whenever irradiated fuel is in the reactor a.
PumE and valve Once/3 vessel and prior to reactor strartup from a operability months cold condit!on.
1.b.
From the effective date of this amendment b.
Flow rate test -
After pump until Juu 1,1982, the "A"
loop of the each RHR service maintenance containment cooling mode of the RHR system water pump shall and every 3 for each reactor may share the Unit 2 "A" deliver at least months and "B" RHR service water pumps using cross tie line 1/2-10124-16"-0.
3500 gpm against Consequently, the requirements of a pressure of 198 Specifications 3.5.B.2 and 3.5.B.3 will pgjg impose the corresponding surveillance testing of equipment associated with botn e.
A logic system Each reactors if the shared RHR service water functional test refuelinE pump or pumps, or the cross tie line, are made or found to De inoperable.
Outage
- 2. From and after the date that one of the
- 2. When it is determined that one RHR RHR service water pumps is made or service water pump is inoperable. the found to be inoperable for any reason, remaining components of that loop continued reactor operation is permis-and the other containment cooling i
i sible only during the succeeding 30 loep of the RIIR system shall be dem-days unless such pump is sooner made onstrated to be operable immediatel) operable.provided that during such 30 and daily thereafter.
l days all other active components of the containment cooling mode of the RHR l g [\\
system are operable.
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QUAD-CITIES DP.2-30 3.5 LIMITING CONDITIONS FOR OPERATION BASES A.
Core Spray and LPCI Mode of the RHR System This specification assures that adequate emergency cooling capability is available.
M Based on the loss-of-coolant analyses included in References I and 2 and in accordance with 10 CFR 50.46 and Appendix K, core cooling systems provide sufficient cooling to the core to dissipate the energy 3
associated with the loss-of-coolant accident, to limit the calculated peak cladding temperature to less than
,fd' y
2200
- F, to assure that core geometry remains intact, to limit the corewide cladding metal-water reaction to less tha. 1%, and to limit the calculated local metal-water reaction to less than 17%
7 The allowable repair times are established so that the average risk rate for repair would be no greater than
$ y the basic risk rate. The method and concept are described in Reference 3. Using the results developed in this reference, the repair period is found to be less than half the test interval. This ass.imes that the core spray subsystems and 1 PCI constitute a one-out-of-two system; however, the combined effect of the Q '
two systems to limit excessive cladding temperature must also be considered. The test interval specified in Specification 4.5 was 3 months. Therefore, an allowable repair period which maintains the basic risk y
considering single failures should be less than 30 days, and this specification is within this period. For
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multiple failures, a shorter intervalis specified; to improve the assurance that the remaining systems will
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function, a daily test is called for. Although it is recognized that the information given in Reference 3 provides a quantitative method to estimate allowable repair times, the lack of operating data to support y
7 the analytical approach prevents complete acceptance of this method at this time. Therefore, the times statrd in the specific items were established with due regard to judgment.
p Should one core spray subsystem become inoperable, the remaining core spray subsystem and the entire LPCI mode of the RHR system are available should the need for core cooling arise. To assure that the remaining core spray, the LPCI mode of the RHR system, and the diesel generators are available, they y
are demorstrated to be operable immediately. This demonstration includes a manualinitiation of the 3
i pumps and associated valves and diesel generators. Based on judgments of the reliability of the remaining systems,i.e., the core spray and LPCI, a 7-day repair period was obtained.
Should the loss of one RHR pump occur, a nearly full complement of core and contaiiment cooling equipment is available. Three RHP. pumps in conjunction with the core spray subsystem will perform the core cooling function. Because of the availability of the majority of the core cooling equipment, which y
will be demonstrated to be operable, a 30-day repair period is justified. If the LPCI mode of the RHR system is not available, at least two RHR pumps must be available to fulfill the containrrent cooling function. The 7-day repair period is set on this basis.
B.
RHR Service Water The containment cooling mode of the RHR system is provided to remove heat energy from the containment in the event of a loss-of-coolant accident. For the flow specified, the containment long-term pressure is limited to less than 8 psig and is therefore more than ample to provide the required heat removal capability (reference SAR Section 5.2.3.2).
The Containment Cooling mode of the RHR System consists of two loops.
Each loop consists of 1 Heat Exchanger, 2 RHR Pumps, and the associated valves, piping, electrical equipment, and instrumentation. The "B" loop on each unit contains 2 RHR Service Water Pumps. During the period from M
November 24, 1981, t o July 1, 1982, the "A" loop on each unit may utilize g
the "A" and "B" RHR Service Water Pumps from Unit 2 via a cross-tie 8
line.
Af te r July 1,1982, each "A" loop will contain 2 RHR Service Water Pumps.
Either set of equipment is capsble of performing the containment F
cooling function. Loss of one RHR service water pump does not seriously jeopardize the containment cooling capability, as any one of the remaining three pumps can satary the cooling requirements. Since m
there is some redundancy left, a 30-day repair period is adequate. Loss of one loop of the containment cooling mode of the RHR system leaves one remaining system to perform the containment cooling function. The operable system is demonstrated to be operable each day when the above condition occurs.
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