ML20039F881
| ML20039F881 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 12/18/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20039F882 | List: |
| References | |
| NUDOCS 8201140011 | |
| Download: ML20039F881 (10) | |
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((QKiQ UNITED STATES f(,g NUCLEAR REGULATORY COMMISSION s.
WASHINGTON, D. C. 20555 COMMONWEALTH EDISON CO WANY AND IOWA-ILLIN0IS GASD ELECTRIC COMPANY DOCKET NO. 50-254 QUAD CITIES STATION UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.75 License No. DPR-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated December 3,1981, as supplemented December 14, 1981, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic
, and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicateo in the attachment to this license amendment and paragraph 3.8 of Facility License No. DPR-29 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 75, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8201140011 811218 PDR ADOCK 05000254 P
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3.
This license amendment is effective as of the date of its issuance.
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'i FOR THE NUCLEAR REGULATORY COMMISSION 2
M Fg Thoma
. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
i Changes to the Technical Specifications Date of Issuance: December 18, 1981 o
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ATTACHMENT TO !ICENSE AMENDMENT NO. 75 FACILITY OPERATING LICENSE NO. DPR-29 DOCKET NO. 50-254 Revise the Appendix "A" Technical Specifications as follows:
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QUAD-CITIES DPR-29
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l continued reactor operation is permis-containment cooling mode of the j
sibic 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 Cooling Mode of the RHR System System Surveillance of the containment cooling mode of the RHR system shall be performed as follows:
!' I 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.B. shall be operable whenever irradiated fuel is in the reactor frem frequency vessel and prior to reactor startup from a cold condition.
a.
Pump and valve Once/3 operability months 1.b.
From the ef fective date of this amendment b.
Flow rate test -
After Pump until June 1,1982, the "A" loop of the containment cooling mode of the RHR syste, each RHR service maintenance for each reactor may share the Unit 2 "A"
water pump shall and every 3 and "B" RHR service water pumps using dejjver at least months cross tie line 1/2-10124-16"-D.
Consequently, the requirements of 500 gpm against Specifications 3.5.B.2 and 3.5.B.3 will a pressure of 198 Impose the corresponding surveillance psig testing of equipment associateo with botn reactors if the shared RHR service water C.
A logic system Each j
pump or pumps, or the cross tie line, are functional test
--fueling made or found to ce inoper ole.
- 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 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 I
operable.provided that during such 30 and daily thereafter.
j' containment cooling mode ofthe RHR days all other active components of the system are operable.
l Amendment No. 50, 75 3,,,
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QUAD-GTIES DPR-29 i
Should the loss of one RHR pump occur, a nearly full complement of core and containment c equipment is avaitable. %ree RHR pumps in conjunction with the core spray subsystem will perform core cooling function. Because of the availability of the majority of the core coohng equipment, which will be demonstrated to be operable, a 30. day repair period isjustined. If the LPG mode of the RHR system is not available, at least two RHR pumps must be available to fulAll the containment cooling function. he 7. day repair period is set on this basis.
B.
RHR Senice Watee 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 now specined, the containment long. term pressure is limited to less than 8 psig and is therefore more than ample to provide the required beat. 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 I 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 November 2a, 1981, to June 1,1982, the "A" loop on each unit may utilize the "A" and "B" RHR Service Water Pumps from Unit 2 via a a
cross-tie line. After June 1, 1982, each "A" Joop will contain 2 R_HR Service Water Pumps.
Either set of equipment is capable of performing the containment t
cooling function. Loss of one RHR service water pump does not seriouslyjeopardize the containment
. cooling capability, as any one of the remaining three pumps can satisfy the cooling requirem:nts. Since 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.
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 specined.
C.
High. Pressure Coolant Injection l
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 HPG meets this requirement without the use ofoffsite 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 damage 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 He relief valves of the automatic pressure relief subsystem are a backup to the HPG 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 sprey subsystems or LPCI mode of the RHR system. The core spray subsystem and/or the LPG,
mode of the RHR system provide sufficient flow of coolant to hmit 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 loca! metal. water reaction to less than 175 Ims of 1 of the relief valves affects the pressure relieving capability and, therefore, a 7 day repair period is specified. Loss of more than one relief valve significantly reduces the pressure relief capability,thus a 24. hour repair period is specifled 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 feedwater system is not available. Under these condidons the pumping capacity of the RCIC system is sumcient to maintain the water level above the core withou't any cther water system in operation. If the water levelin the reactor vessel decreases to the RCIC initiation level, the system automatically starts. The system may also be manually initiated at any time.
1 Amendment No. 75 3.5/4.5-12
fw%,h, UNITED STATES
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'g NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20555 t
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COMMONWEALTH EDISON COMPANY AND IOWA ILLIN0IS GAS AND ELECTRIC COMPANY DOCr,ET N0. 50-265 QUAD CITIES STATION UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 68 License No. DPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwalth Edison Company 1
(the licensee) dated December 3,1981, as supplemented December 14, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be' inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 3.8 of Facility License No. DPR-30 is hereby amer.ded to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 68, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
2 3.
This license amendment is effective as of the date of its issuance.
t FOR THE NUCLEAR REGULATORY COMISSION Thoma ppolito. Chief Opera ing Reactors Branch #2 1
I Division of Licensing
Attachment:
i Changes to the Technical Specifications Date of Issuance: December 18, 1981 l
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1 ATTACHMENT TO LICENSE AMENDMENT N0.68 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET N0. 50-265 i
Revise the_ Appendix "A" Technical Specifications as follows:
d Remove Replace 3.5/4.5-3 3.5/4.5-3 3.5/4.5-11 3.5/4.5-11 4
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o QUAD-CITIES DPR-30 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 ments 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 thercaner.
pumps), and the diesel generators re-quired for operation of such compo-ments if no eaternal source of power were available shall be operable.
- 6. If the requirements of SpeciAcation 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.
Costelement 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:
/
I1.a. Both loops of the containment cooling mode of the RHR system, as defined in the bases bF7 for Specification 3.5.0, shall be operable whenever irradiated fuel is in the reactor a.
Pump and valve Once/3 vessel and prior to reactor startup from a cold condition.
'Perability months From the effec'ive date of this amendment b.
Flow rate test -
After pump 1.b.
t until June 1,1982, the "A" loop of tne 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"-D.
3500 gpm against Consequently, the requirements of a pressure of 198 Specifications 3.5.B.2 and 3.5.B.3 will impose the corresponding surveillance testing of equipment associated with botn c.
A logic system Each reactors if the shared RHR service water fbnctional icst refuelinE pump or pumps, or the cross tie line, are i
made or found to be inoperaDie.
ouuge
- 2. From and aner 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 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 operabic, provided that during such 30 and daily thereaner.
days all other active components of the
!{
containment cooling mode of the RHR
's system are operable.
Amendment No. 68 3.5 M 5-3
QUAD-CITIES DPR-30 3.5 IJMITING CONDITIONS FOR OPERATION BASES e
A. Core Spray and LPCI Mode of the RHR System This speciAcation assures that adequate emergency cooling capability is available.
Based on the less-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 associated with the loss-of-coolant accident, to limit the calculated peak cladding temperature to less than i
2200
- F, to assure that core geometry remains intact, to limit the corewide cladding metal water reactica to less than 1% and to limit the calculated local metal water reaction to less than 17%
The allowsble repair times are established so that the average risk rate for repair would be no greater than 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 assumes that the core spray subsystems and LPCI constitute a one-out-of two system: however, the combined effect of the two systems to limit excessive cladding temperature must also be considered. The test interval speciAed L'
in Specincation 4.5 was 3 months. Therefore, an allowable repair period which maintains the basic risk considering single failures should be less than 30 days, and this speciAcation is within this period. For a
multiple failures, a shorter interval is specined; to improve the assurance that the remaining systems will 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 W r H !
the analytical approach prevents complete acceptance of this method at this time. Therefore, the times statrd in the specine items were established with due regard to judgment.
5 Should one core spray subsystem become inopciable, the remaining core spray subsystem and the entire 1
)
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 g g are demonstrated to be operable immediately.This demonstration includes a manualinitiation of the 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 containment cooling equipment is availsble. Three RH R 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 j
will be demonstrated to be operable, a 30-day repair period isjustified. If the LPCI mode of the RHR system is not available, at least two RHR pumps must be available to fulAll the containment cooling function. The 7-day repair period is set on this basis.
B.
.E The containment cooling mode of the RHR system is provided to remove heat energy from tha containment in the event of a loss-of coolant accident. For the now specined, the containment long-term
)
pressure is limited to less than 8 psig and is therefore more than ample to provide the required 5
heat removal capability (reference SAR Section 5.2.3.2).
y 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 November 2a,1981, to June 1,1982, the "A" loop on each unit may utilize the "A" and "B" RHR Service water Pumps from Unit 2 via a cross-tie line. Af ter June 1,1982, each "A" loop will contain 2 RHR Service water Pumps.
Either set of equipment is capable of performing the containment
'd, 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 satisfy the cooling requirements. Since there is some redundancy left, a 30-day repair period is adequate. Loss of one loop of the containment l
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.
Amendment No. 68 i
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