ML20209H844
| ML20209H844 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/21/1987 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20209H849 | List: |
| References | |
| NUDOCS 8702060152 | |
| Download: ML20209H844 (14) | |
Text
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e[>RRtOy 'o UNI,TED STATES
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NUCLEAR REGULATORY COMMISSION o
.y WASHINGTON, D. C. 20555
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CCWONWEALTH EDISON C0t/PANY AND TOWA-ILLINGTS GAS AND ELECTRIC C0VPANY DOCKET M0. 50-254
('l'A0 CITTES Nt! CLEAR POWFP STATinN, ttNIT 1 Af'ENOMENT TO FACILITY OPERATING LTCENSE Amendment No. 99 License No. DPR-29 1.
Tha Nuclear Regulatory Commission (the Commissinn) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated iune 28, 1.985 complies with the standards l
and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Conriission's rules and regulations set forth in 10 CFR Chapter I; R.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of tha Commission; t
C.
There is reasonable assurance (i) that the activities authori7ed by this amendment can be conducted without endancering the health and safety of the public, and (ii) that such activities will he 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 i
I E.
The issuance of this amendment is in accordance with 10 CFR Part 51 I
of the Commission's regulations and all applicable requirements
[
have been satisfied.
I' 2.
Accordingly, the license is amended by chances to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.P. of Facility Operating License No. OPR-29 is hereby amended to read as follows:
8702060152 870121 PDR ADOCK 05000254 P
. B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 99, are herrby incorporated in the license. The licensee shall operate the 'ecility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NilCLEAD OFrUl.ATnnh CnkHTSS10t!
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.'nhn A. 7wolinski, Director BWR n.ipct Directorate #1 Division of BWD Licensing
Attachment:
Chances to the Technical Specifications Date of issuance: January 21, 1987 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 99 FACILITY OPFRATING LICENSE NO. DPR-29 DOCKET NO. 50-254 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 amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3.5/4.5-2 3.5/4.5-2 3.5/4.5-3 3.5/4.5-3 3.5/4.5-4 3.5/4.5-4 Bases 3.5/4.5-11a Bases 3.5/4.5-11a
QUAD-CITIES DPR-29 e.
Core spray header a p
..y.
instrumentation
^
check Once/ day
~
calibrate Once/3 months.
test On6/3 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 inocer-made or found to be inoperable able, the operable core spray for any reason, continued reat-subsystem and the LPCI mode of tor operation is permissible the RHR system shall be demonstrated only during the succeeding 7 to be operable immediately. The days unless such subsystem is operable core spray subsystem shall sooner made operable, provided be demonstrated to be operable that during such 7 days all at-daily thereafter.
tive components of the other core spray subsystem and the LPCI mode of the RHR system and the diesel generators required 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.reac, tor 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, and both core spray subsystems able, provided that during such shall be demonstrated to be 30 days the remaining active operable immediately and the' components of the LPCI mode of operable RHR pumps daily there-the RHR, containment cooling after.
3.5/4.5-2 Amendment No. 98, 99
@AD-CITIES DPR-29 continued ctor operation is containment cooling mode of the IHL permissible only & ring the succeeding 7 shall be demonstrated to be operable days unless it is sooner made operable, lamediately and daily thereafter.
provided that during such 7 days all active components of both core spray sesystems, the containment cooling mode of the fut (including two fHt pops),
and the diesel generators required for operation of such coupcrents if no external source of power were available shall be operable.
6.
If the requirements of Specification 3.5.A cannot be set an order 1 shutdown ofthereactorshallbeinitia
, and the reactor shall tw 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 />.
8.
Contaltunent Cooling Mode of the IHt System 8.
Contalrunent Cooling Mode of the IHL system 1.a Soth loops of the contairgent cooling Surveillance of the contaltunent cooling mode ende of the IHt s es, as defined in of the IHL systen shall be perfonned as the bases for ication 3.5.8, shall follows:
be operable whenever irradiated fuel is in the reector vessel and prior to 1.
lHt service water sesysten testing:
reactor startup from a cold condition.
1.b Frun the effective date of this enentent until July 1,1992 the "A" a.
Pop and valve once/3 loop of the contaltunent coo 1Ing sode of operability sonths the IHI system for each reactor may share the Unit 2 "A" and '8" IHL service b.
Flow rate test-After p e p water pumps uslog cross tie line each IHL maintenance 1/2-10124-16"-0. Con tly the service water and every 3 requirements of fi lons,3.5.8.2 po p shall sonths and 3.5.8.3 will the deliver at cor ing surve 11ance testing of least 3500 gun equ puent associated with both reactors against a pressure it ne shared IHt service water pop or of 198 psig pitips, or the cross tie line, are made or found to be inoperable.
c.
A logic system Each functional refueling test.
outage.
2.
From and after the date that one of the 2.
When it is determined that one IHt l
Mt service water pops is made or found service water pump is inoperable, the to be inoperable for any reason remaining components of that loop and c m tinued reactor operation is,
the other containment cooling loop of permissible only during the succeeding the IHL systen shall be demonstrated to 30 days unless such pump is sooner ande be operable immediately and daily operacle, provided that & ring such 30 thereafter, i
days all other active conponents of the contaltunent cooling mode of the fHt systen are operable.
3.5/4.5-3 Amendment No. 78, 99 i
QUAD-CITIES OPR-29 3.
Fran and after the date that one loop of 3.
men one loco of the contalement cooling the containment cooll mode of the IHL ande of the IHL system becomes systen is made or f to be inoperable inoperable, the operable loco shall be for any reason, continued reactor demonstrated to be operable lamediately, operation is pemissible only bring the and daily thereafter.
succeeding 7 days unless such sesysten is sooner made operable, provided that all active components of the other loop of the contalrument cooling mode of the IHL systen both core spray s e systans, andbothdIcsel ators twquirvd for operation of components if no external source of power were available, shall be operable.
4.
Coritainment cooling spray loops are 4.
During each 5-year period, an air test recalred to be operable when the reactor shall be performed on the drywell spray water temperature is gewater than headers and nozzles and a mater spray 212*F anc prior to reector startie test perfomed on the torus spray header from a cold condition. Continued and nozzles.
reactor operation is pemitted provided that a maximum of one drywell soray loop may be inoperable for 30 days when the reactor unter temperature is greater than 212ap, 5.
If the requirements of 3.5.B cannot be met, an orderly shutdown shall be initiated, and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C.
WCI Subsysten C.
IPCI Sesysten Surveillance of IPCI subsysten shall be perfomed as follows:
1.
The IPCI subsystem shall be operable 1.
WCI subsystem testing shall be as whenever the reactor pressure is greater specified in Specification 4.5.A.I.a.b, irradiated fuel is in the c, and d except that the IPCI pump than 90 psig,l, and prior to reactor shall deliver at least 5000 syn against reactor vesse startup from a cold condition.
a system head corresponding to a reactor vessel pressure of 1150 psig to 150 psig and a logic system functional test shaII be perfomed bring each refueling i
i 2.
Fran and after the date that the HPCI 2.
When it is detemined that the HPCI j
wbsystem is made or found to be subsysten is inoperable, the LPCI moda inoperable for any reeson continued of the IHL systas, both core spray reactor operation is pemIssible only subsystmas, the automatic pressure durlog the succeeding 7 days unless such relief sesystem, and the RCIC system subsystem is sooner made operable, shall be demonstrated to be 3.5/4.5 d Amendment No. 99 l
QUAD-CfTIES 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 scecification 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 I provides a quantitative method te estimate allowable repair times, the lack of operating data to succort 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 scray 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 and the LPCI mode of the RHR system are available, they are demonstrated to be operable immediately.
This demonstration includes a manual initiation of the pumps and associated valves.
Based on judgments 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-lla Amendment No.6J,$$, 99
a amarug 4
k UNITED STATES 8
NUCLEAR REGULATORY COMMISSION g
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WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS AFD ELECTRIC COMPANY DOCKET NO. 50-765 00AD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 96 License No. DPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for anendment by Commonwealth Edison Company (the licensee) dated June 28, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended f
(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; 4
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 amended to read as follows:
i
2-B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 96, 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.
FDPTFNilCLEARREGULpTOP Cnvu1SSTON
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j John A. Zwolinski, Director PWR Pro,iect Direc+0 rate #1 Divition of RWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: January 21, 1987 h
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ATTACHMENT TO LICENSE AMEP!DMENT NO. 96 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-765 Revise the Appendix A Technical Specifications by removing the pages identified belew and inserting the attached pages. The revised pages are identified by the captfored amendment number and contain marginal lines indicatina the area of change.
REMOVE INSERT 3.5/4.5-2 3.5/4.5-?
3.5/4.5-3 3.5/4.5-3 3.5/4.5 4 3.5/4.5-4 Bases 3.5/4.5-11 Bases 3.5/4.5-11
QUAD-CITIES DPR-30 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 operable core spray for any reason, continued reat-subsystem and the LPCI mode of tor operation is permissible the RHR system shall be demonstrated only dtfring the succeeding 7 to be operable immediately.
The days unless such subsystem is operable core spray subsystem shall sooner made operable, provided be demonstrated to be operable that during such 7 days all at-daily thereafter.
tive components of the other core spray subsystem and the LPCI mode of the RHR system and the diesel generators required 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.1.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.
l 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 and both core spray subsystems able, provided that during such shall be demonstrated to be l
30 days the remaining active operable immediately and the components of the LPCI mode of operable RHR pumps daily the RHR, containment cooling thereafter.
l 3.5/4.5-2 Amendment No. 94, 96 l
QuMM:ITIES orn-30 continued reactor operation is contalruent cooling mode of the M permissible only during the succeeding 7 shall be dmunnstrates to be operable days unless it is sooner made operable, launediately and daily thereafter.
provided that during such 7 days all active components of both core spray sobsystans, the contaltunent culing mode of the H (including two M pumps,
and the diesel generators required or operation of such components if no external source of power were available shall be operable.
6.
If the requirements of Specification ofthereactorshallanorderlyshutdown 3.5.A cannot be met 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 M System B.
Contalrunent Cooling Mode of the M system 1.a Both loops of the contaltunent cooling Surveillance of the contalrunent cooling mode mode of the H s tem as defined in of the M system shall be performed as the bases for ifica, tion 3.5.8, shall follows:
be operable whenever irradiated fuel is in the reactor vessel and prior to 1.
M service water sabsysten testing:
reactor startap frtun a cold condition.
1.b From the effective date of this amendment until July 1,1982 the "A" a.
Pump and valve once/3 loop of the contaltunent coo 1Ing mode of operability months the M system for each reactor may share the Unit 2 "A" and "B" M service b.
Flow rate test-After pamp water pisos using cross tie line each M maintenance 1/2-10124-16"-0. Con tly, the service water and every 3 irements of Specifi tions 3.5.8.2 pump shall months 3.5.8.3 will tagose the deliver at corresponding surveillance testing of least 3500 gpm equ associated with both reactors against a pressure if shared M service water pamp or of 198 psig pumps, or the cross tie line, are made or found to be inoperable.
c.
A logic system Each functional test. refueling outage.
2.
Fran and after the date that one of the 2.
When it is determined that one M I
i M service water ptmps is made or found service water pump is inoperable, the l
to be inoperable for any reason, remaining components of that loop and continued reactor operation is the other containment cooling loop of permissible only & ring the succeeding the M systen shall be demonstrated to 30 days unless such ptmp is socaer mode be operable immediately and daily operable, provided that during s'uch 30 thereafter.
e days all other active conponents of the containment cooling mode of the M system are operable.
3.5/4.5-3 Amendment No. 68,72, 96
QUAIM:ITIES DPR-30 l
3.
From and after the date that one loop of 3.
When one loop of the containment cooling the contairnent cooling mode of the M mode of the M system becomes system is made or found to be inoperable inoperable, the operable loop shall be for any reason, continued reactor demonstrated to be operable ismediately operation is permissible only during the and daily thereafter.
succeeding 7 days unless such subsysten is sooner made operable, provided that all active components of the other icap of the contaltunent cooling mode of the M system, both core spray subsystems, and both diesel rators regstred for operation of components if no external source of power were available, shall be operable.
During the time period frtum April 17, 1978 through April 30, 1978 while the 2A Contaltunent Cooling Loop of the M exchanger repair, perable for heat System is made ino continued reactor operation is permissible beyond the above 7-day limitation, unless such loop is sooner made operable, provided that during the time the 7-day limit is exceeded, a visual inspection is performed daily to assure that proper in the "B" M loop.grity is t and system inte valve all maintal During each 5-year period,drywell spray an air test 4.
Containment cooling spray loops are 4.
shall be performed on the required to be operable when the reactor water tenperature is greater than headers and nozzles and a water spray 2120F and prior to reactor startup test performed on the torus spray header from a cold condition. Continued and nozzles.
reactor operation is permitted provided that a maxiansa of one drywell spray loop may be inoperable for 30 days when the reactor water tenperature is greater than 2120F.
5.
If the requirements of 3.5.8 cannot be met an orderly shutdown shall be inillated,andthereactorshallbeina cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l l
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i 3.5/4.5-4 Amendment No. 6, 96
QUAIMITIES OPR-30 3.5 LIMITING CONDITIONS FOR OPERATION BASES A.
Core Spray and LPCI Mode of h IHt System lhls specification assures that adequate emergency cooling capability is available.
Based on h 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 h core to dissipate the energy associated with h loss-of-coolant accident, to limit h calculated peak cladding temperature to less than 2200*F, to assure that core geometry remains intact to limit h corewide cladding metal-water reaction to less than 15 and to limit h calculated local metal-water reaction to less than 175.
The allowable repair times are established so h t h everage risk rate for repair would be no greater than h basic risk rate. h method and concept are described in Reference 3.
Using h results developed in this reference, h repair period is found to be less h n half N test interval. This assumes h t h core spray subsystems and LPCI constitute a one-out-of-two system; however, h combined effect of h 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 and this W basic risk considering single failures should be less N n 30 days, Interval is specification is within this period. For multiple failures, a shorter specified; to improve N assurance that h remaining systems will function, a dally test is called for. Although it is recognized ht h information given in Reference 3 provides a quantitative method to estimate allowable repair times, h lack of operating data to support h analytical approach prevents complete acceptance of this method at this time. Therefore, h times stated in the specific items were established with due regard to judynent.
Should one core spray subsystem become Inoperable, the remaining core spray subsystem and the entire LPCI mode of the RHR system are available should h need for core cooling arise. To assure ht h remaining core spray and the LPCI mode of the RHR system are available, h y are denonstrated to be operable Ismediately. This demonstration includes a manual initiation of h pumps and associated valves. Based on judgments of h reliability of h remaining systems, i.e., h core spray and LPCI, a 7-day repair period was obtained.
i Should h loss of one flHR pump occur, a nearly full complement of core and containment cooling equipment is available. Three RlR peps in conjunction with h core spray subsystem will perform h core cooling function. Because of h availability of the majority of W core cooling equipment, which will be demonstrated to be operable, a 30-day repair period is justified, if h LPCI mode of h flHR system is not available, at least two RHR pops must be available to fulfill h containment cooling function. The 7-day repair perio:1 is set on this basis.
8.
lHt Service Water The containment cooling mode of N IHL system is provided to remove heat enerov from the containment in h event of a loss-of-coolant accident. For h flow specifief, h contairunent long-term pressure is limited to less hn 8 psig and is therefore more Nn ample to provide the required heat removal capability (reference SAR Section 5.2.3.2).
The Containment Cooling mode of h RHR5 System consists of two loops. Each loop consists of I Heat Exchanger, 2 RHR Pungs, and the associated valves, piping, electrical equipment, and instrumentation. h "B"' loop on each unit contains 2 RHR Service Water Pumps.
During h period from November 24, 1981, to July 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. After July 1 1982, each "A" loop will contain 2 RHR Service Water Pumps. El h r set of equlpme,nt is capable of performing the containment cooling function. Loss of one IHL service water pune does not seriously jeopardize h contalrunent cooling capability, as any one of the remaining three pumps can satisfy W cooling requirements. Since h re is j
some redundancy left, a 30-day repair period is adequate. Loss of one loop of h containment cooling mode of the RHR system leaves one remaining system to perfonn h containment cooling function. The operable system is demonstrated to be operable each day when the above condition occurs.
3.5/4.5-11 Amendment No. 68,72,96
_