ML20207P670
| ML20207P670 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/06/1987 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207P671 | List: |
| References | |
| NUDOCS 8701200025 | |
| Download: ML20207P670 (12) | |
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION 3
.,E WASHINGTON, D. C. 20555
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COMMONWEALTH EDIS0N COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET N0. 50-?54 OUAD CITIES NUCLEAR POWER STATION, UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 98 License No. DPR-29 I.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated October 22, 1986, 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 endarigering 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 cormon 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 Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-29 is hereby amer;ded to read as follows:
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8701200025 870106 PDR ADOCK 05000254 P
. B.
Technical Specifications I
The Technical Specifications contained in Appendices A and B, as l
. revised through Amendment No. 98, are hereby incorporated in the l
license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REG,ULA"0RY COMMISSION Q,
Joh A. Zwolinski, Director BWR roject Directorate #1 Division of BWP, Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 6, 1987
ATTACHMENT TO LICENSE AMENDMENT NO. 98 FACILITY OPERATING LICENSE NO.' DPR-29 DOCKET NO. 50-254 Revise the Appendix A Technical Specifications by removing the pages identi#ied below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marpiral lines indicating the area of change.
REMOVE INSERT 3.5/4.5-2 3.6/4.5-2 3.5/4.5-2a*
1 Bases 3.5/4.5-11 Bases 3.5/4.5-11 Bases 3.5/4.5-11a*
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- Papination change only
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QUAD-CITIES OPR-29 e.
Core spray header a p instrumentation check Once/ day calibrate Once/3 months test Once/3 months f.
Logic system Once/Each functional refueling test outage 2.
From and after the date that one 2.
When it is determined that one of the core spray subsystems is core spray subsystem is inoper-made or found to be inoperable able, the operabia core spray for any reason, continued reac-subsystem, the LPCI mode of the tor operation is permissible RHR system, and the diesel gen-only during the succeeding 7 erators required for operation days unless such subsystem is of such components if no exter-sooner made operat,ie, provided nal source of power were avail-that during such 7 days all ac-able shall be demonstrated to be tive components of the other operable immediately. The oper-core spray subsystem and the able core spray subsystem shall LPCI mode of the RHR system and be demonstrated to be operable the diesel gener& tors required daily thereafter.
for operation of such components if no external source of power were available shall be operable.
3.
The LPCI mode of the RHR system 3.
LPCI mode of the RHR system shall be operable whenever testing shall be as specified in irradiated fuel is in the Specifications 4.5.A.I.a. b, c, reactor vessel and prior to d, and f, except that each LPCI reactor startup from a cold division (two RHR pumps per condition.
division) shall deliver at least 9000 gpm against a system head corresponding to a reactor ves-sel pressure of 20 psig, with a minimum flow valve open.
4.
From and after the date that one of the RHR pumps is made or 4.
When it is determined that one found to be inoperable for any of the RHR pumps is inoperable, reason, continued reactor opera-the remaining active components tion is permissible only during of the LPCI mode of the RHR, the succeeding 30 days unless containment cooling mode of the such pump is sooner made oper-RHR, both core spray subsystems, able, provided that during such and the diesel generators re-30 days the remaining at.cive quired for operation of such components of the LPCI mode of components if no external source the RHR, containment cooling of power were available shall be demonstrated to be operable immediately and the operable RHR pumps daily thereafter.
3.5/4.5-2 Amendment 5%. 98
r QUAD-CITIES DPR-29 mode of the RHR, all active components of both core spray subsystems, and the diesel generators required for operation of such components if no external source of power were available shall be operable.
5.
From and after the date that the 5.
When it is determined that the LPCI mode of the RHR system is LPCI mode of the RHR system is made or found to be inoperable inoperable, both core spray sub-for any reason, systems, the i
i 3.5/4.5-2a Amendment No. 98
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QUAD-CITIES DPR-29 3.5 LIMITING CONDITION FOR OPERATION BASES A.
Core Spray and LPCI Mode of the RHR System This specification assures that adequate emergency cooling capability is available whenever irradiated fuel is in the reactor vessel.
Based on the loss-of-coolant analytical methods described in General Electric Topical Report NED0-20566 and the specific analysis in Reference 1, core cooling systems provide sufficient cooling to the core to dissipate the energy associated with the loss-of-coolant accident, to limit calculated fuel cladding temperature to less than 22000F, to assure that core geometry remains intact, to limit cladding metal-water reaction to less than 17., and to limit the calculated local metalwater reaction to less than 17%.
The limiting conditions of operation in Specifications 3.5.A.1 through 3.5.A.6 specify the combinations of operable subsystems to assure the availability of the minimum cooling systems noted above. Under these limiting Conditions of operation, increased surveillance testing of the remaining ECCS systems provides assurance that adequate cooling of the core will be provided during a loss-of-coolant accident.
Core spray distribution has been shown, in full-scale tests of systems similar in design to that of Quad-Cities 1 and 2, to exceed the minimum requirements by at least 257..
In addition, cooling effectiveness has been demonstrated at less than half the rated flow in simulated fuel assemblies witp heater rods to duplicate the decay heat characteristics of irradiated fuel.
The accident analysis is additional conservative in that no credit is taken for spray cooling of the reactor core before the internal pressure has fallen to 90 psig.
The LPCI mode of the RHR system is designed to provide emergency cooling to the core by flooding in the event of a loss-of-coolant accident.
This system functions in combination with the core spray system to prevent excessive fuel cladding temperature.
The LPCI mode of the RHR system in combination with the core spray subsystemprovidesagequatecoolingforbreakaregsof up to and including 4.18 ft, the latter approximately 0.2 ft being the double-ended recirculation line break with the equalizer line between the recirculation loops closed without assistance from the high-pressure emergency core cooling subsystems.
The allowable 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 3.5/4.5-11 Amendment No.61, 98 7
l
QUAD-CITIES DPR-29 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 specified in Specification 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 specification is within this period.
For multiple failures, a shorter interval is specified; 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 1 provides a quantitative method to estimate allowable repair times, the lack of operating data to support the analytical approach prevents complete acceptance of this method at this time.
Therefore, the times stated in the specific items were established with due regard to judgment.
Should one core spray subsystem become inoperable, the remaining core spray subsystem and the entire LCPI 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 are demonstrated to be operable immediately.
This demonstration includes a manual initiation of the pumps and associated valves and diesel generators. Based on judgements of the reliability of the remaining systems, i.e., the core spray and LPCI, a 7-day repair period was obtained.
3.5/4.5-11a Amendment No. 98
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o UNITED STATES
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NUCLEAR REGULATOHY COMMISSION
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COMMONWEALTH EDISON COMPANY AND IOWA-ILLINDIS GAS AND ELECTRIC COMPANY DOCKET N0. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDPENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. DPR-30 1.
The Nuclear Regulatory Commission (the Ccmmission) has found that:
A.
The application for amendment by Commonwealth Edison Ccmpany (the licensee) dated October 22, 1986, 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 th'e application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized 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 Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-30 is hereby & mended to read as follows:
+
~8 B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 94, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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- (.
John A. Zwolinski, Director BWR roject Directorate #1 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 6, 1987
ATTACPMENT TO LICENSE AMENDMENT NO.' 94 FACILITY OPERATIMG LICENSE NO. OPR-30 DOCKET NO. 50-265 Revise the Appendix A Technical Specifications by removing the pages identified below and. inserting the attached pages. The revised pages are identified by the captioned amendmer.t number and contain marginal lines indicating the area of change.
REMOVE INSERT 3.5/4.5-2 3.5/4.5 7 3.5/4.5-2a*
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t
- Pagination change only I
i N
~
i QUAD-CITIES o
DPR-30 e.
' c, header A p instrumentation check Once/ day calibrate Once/3 months test Once/3 months f.
Logic system Once/Each functional refueling
/
test outage p
- 2. ~ From and after the date that one 2.
When it is determined that one of'the core spray subsystems is core spray subsystem is inoper-made or found to be inoperable able, the operable core spray for any reason, continued reat-subsystem, the LPCI mode of the tor operation is permissible RHR system, and the diesel gen-only du' ring the succeeding 7 erators required for operation days unless such subsystem is of such components if no eater-sooner made cperable, provided nal source of power were avall-that during such 7 days all ac-able shall be demonstrated to be tive components of the other operable immediately.
The oper-core spray subsystem and the able core spray subsystem shall y.
LPCI mode of the RHR system and be demonstrated to be operable the diesel generators required daily thereafter.
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for operation of such components if no external source of power were available shall be operable.
- 3.
The LPCI mode of the RHR syste:n 3.
LPCI mode of the RHR system testing shall be as specified in shall be operable whenever c
- 3) '
irradiated fuel is in the h
Specifications 4.5.A.I.a. b, c, reactorvesselandpriorito
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d, and f, ex:ept that each LPCI reactor startup from a cold division (two RHR pumps per condition, division) shall deliver at least 9000 gpm against a system head corresponding to a reactor ves-sel pressure of 20 psig, with a minimum flow valve open.
4.
From and after the date that one of the RHR pumps is made or 4.
When it is determined that one found to be inoperable for any of the RHR pumps is inoperable, reason, continued reactor opera-the remaining active components tion is permissible only during of the LPCI mode of the RHR, the succeeding 30 days unless containment cooling mode of the such pump is sooner made oper-RHR, both core spray subsysterns, able, provided that during such and the diesel generators re-30-days the remaining active quired for operation of such components of the LPCI mode of components if no external source the RHR. containment cooling of power were available shall be demonstrated to be operable immediately and the operable RHR pumps daily thereafter.
3.5/4.5-2 Amendment No. 94
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QUAD-CITIES DPR-30 mode of the RHR, all active components of both core spray subsystems, and the diesel generators required for operation of such components if no external source of power were available shall be operable.
5.
From and after the date that the 5.
When it is determined that the LPCI mode of the RHR system is LPCI mode of the RHR system is made or found to be inoperable inoperable, both core spray sub-for any reason, systems, the
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3.5/4.5-2a Amendment No. 94 l
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