ML20246Q000
| ML20246Q000 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 09/01/1989 |
| From: | Shemanski P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246Q005 | List: |
| References | |
| NUDOCS 8909110305 | |
| Download: ML20246Q000 (10) | |
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555 a
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- ...9 COMMONWEALTH EDIS0N CCMPANY Afp IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY L
DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE 4
Amendment No. 119-License No. DPR-29 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated August 28, 1989, complies with the standards and requirements of the Atomic Energy.Act of 1954, as amended (the Act) and the Comission'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 Comission; 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 Comission'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 Comission'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 amended to read as follows:
8909110305 890901 PDR ADOCK 05000254 P
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. l B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 119, 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 REGULATORY C0HMISSION Paul C. Shemanski, Acting Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: September 1, 1989
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' ATTACHMENT TO LICENSE AMENDMENT NO. 119.
FACILITY OPERATING LICENSE NO. DPR-29 DOCKET-NO. 50-254' l
l_y Revise-the Appendix A': Technical Specifications by removing the. pages i _:
> :1dentified below and inserting the attached pages. The' revised pages are l'
identified by the: captioned amendment number and contain marginal lines indicating _the. area of change.
-REMOVE INSERT 3.5/4.5-4
_3.5/4.5-4 3.F '4. 5-7 3.5/4.5-7.
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b.
From the effective date of b.
Flow rate test -
After pump
-this amendment until Novem-each RHR service maintenance i.
ber 1, 1989, the "B" loop of water pump shall
- and every -
'the containment cooling mode deliver at'least 3 months of the RHR system.for each 3500 gpm against reactor may share the Unit I a pressure of 198 "C" and "D RHR service
'psig i
water pumps using cross tie I
. line 1/2-10509-16"-D.
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A logic system Each Consequently, the require-functional test refueling rents of Specifications outage 3.5.B.2 and 3.5.B.3 will impose the. corresponding surveillance testing of equipment associated with
'both reactors if.the shared RHR service water pump or pumps,:or the cross tie line, are made or found to be inoperable.
2.-
From and after the date that one 2.
When it is determined that one of the RHR service water pumps RHR service water pump is inop-is made or found to be inoper-erable, the remaining components able for"any reason, continued of that loop and the other con-reactor operation is permissible tainment cooling loop of the RHR only during.the succeeding 30 system shall be demonstrated to days unless such pump is sooner be. operable immediately and made operable, provided that daily thereafter.
during such 30 days all other active components of the con-tainment cooling mode of the RHR system are operable.
3.
From and after the date that one 3.
When one loop of the containment loop of the containment cooling cooling mode of the RHR system mode of the RHR system is made becomes inoperable, the operable or found to be inoperable for loop shall be demonstrated to be any reason, continued reactor operable immediately, and daily operation is permissible only thereafter.
during.the succeeding 7 days un-less such subsystem is sooner made operable, provided that all active components of the other loop of the containment cooling mode of the RHR system, both core spray subiystems, and both diesel generators required for' operation of.such components if no external source of power were available, shall be operable.
3.5/4.5-4 Amendment No. 119
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. QUAD-CITIES DPR-29 I
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 "A" loop on each unit contains 2 RHR Service Water Pumps.
Until November 1, 1989, the "B" loop on each unit may utilize the "C" and "D" RHR Ser-vice Water Pumps from' Unit I via a cross-tie line.
After November 1, 1989, each "B" loop will contain 2 RHR Service Water Pumps.
Either set of equipment is' capable,f performing the containment cooling function.
Loss of one r(HR ' service water pump does not seriously.
. jeopardize the conta'nment 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 cooling mode of-the RHR system leaves one remaining system to perform the containment cooling func-tion.
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 modeLof the RHR system or core spray subsystems can protect the core.
The HPCI neets 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 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 The relief valves of the automatic pressure relief subsystem are a backup to the HPCI subsystem.. They. enable the core spray subsystem and 1
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 spray subsystem and LPCI mode of the RHR system.
The core spray subsystem and the LPCI mode of the RHR system provide sufficient flow of coolant to limit fuel cladding temperatures to less 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 17%.
3.5/4.5-17 Amendment No.119
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%....y COMMONWEALTH EDISCN COMPANY AND IOWA-ILLINOIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 115 License No. DPR-30 1.
The. Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated August 28, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended.
(the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; S.
.The facility will operate in conformity with the application, the provisions.of the Act, and.the rules and regulations of the Comission; C.
Thcre 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 Comission'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 Cosmission'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:
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B.-
' Technical Specifications
.The Technical Specifications contained in Appendices A and B, as revised through Amendment'No. 115, are hereby incorporated in the license.. The licensee shall operate the-facility in.accordance with the Technical. Specifications.
- 3.
This l'icense amendment is effective as of the date of its. issuance, j
1 FOR THE NUCLEAR REGULATORY COMMISSION 1
($
Paul C. Shemanski, Acting Director Project Directorate III-2
. Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
Septenber 1,1989 1
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..l 1-L ATTACHMENT TO LICENSE AMENDMENT NO. 115 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-265
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Revise the Appendix' A Technical-Specifications by removing'the pages
-identified below and inserts:ng the attached pages. :The revised pages are
. identified'by the captioned amendment number. and contain marginal lines indicating the area of change.)
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REMOVE INSERT-3.5/4.5-3 3.5/4.5-3~
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~3.5/4.5-11 3.5/4.5-11
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QUAD-CITIES-
,.4 DPR.;p
-4 continued reactor containment cooling mCdf of the operation is permissible RHR shall be demonstrated., be only during the succeeding 7 operaole imediately and daily days unless it is sooner made thereafter.
operable, provided that during
.such 7 days all active compo-nents of both core spray sub-systees, the containment cooling mece of the RHR (including two RHR ppps).- and the diesel pen-i.-
ersters required for operation of sucn components if no ester-nel source of power were avail-able shall be operable.
6.
If the reovirements of Specifi-cation 3.5.A cannot be met, an orderly shutdown of the reactor shall be' initiated, and the re-actor shall be in the cold shut-down 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:
1.
Ea.
'doth loops of the 1.
RHR service water subsystem containment coo'.i ' mode of testing:
the RHR system. 4-defined
.in the bases for Spe-Item f rs quency cification 3.5.8, shall be operable whenever irradiated a
pump and valve Once/3 fuel is in the reactor operability months vessel and prior to reactor startup f rom a coin condition.
1.
b.
From the effective date of b.
Flow rate' test - Af ter pump this amendment until each RHR service maintenance November 1, 1989
' water pump shall and every the "B" loop of the deliver at least
.3 months containment cooling mode of
'3500 gym against l
the RHR system for each a pres re of 196 l-reactor may share the Unit 1 psig "C" and "D" RHR service waterpumpsusink" crosstie Alogicsfstem c.
Each l.
l line 1/2-10509-i D.
functiona test refueling Consequently, the require-outage ments of Specifications 3.5.5.2 and 3.5.B.3 will impose the corresponding surveillance testing of envipment associated with both reacters if the shared
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RHR service water pump er i
pumps, er the cross tie line, are made or found to be inoperable.
2.
From and af ter the date that one 2.
When it is determined that one of the RHR service water pumps RHR service water pump is inop-is mass or found to be inoper-erable, the remaining components at,1e for any reason. continued of that loop and the other con-reactor operation is permissible tainment cooling loop of the RHR only during the succeeding 30 system shall be demonstrated to days unless such pump is sooner be opersole immediately and made operable, provided that daily thereafter.
during such 30 days all other active components of the con-tainment cooling mode of the RHR system are operable.
l 1.
1545B 3.5/4.5-3 Amendment No. 68. 72, %, 115
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DPR-30 3.5 LIMITING CONDITIONS FOR OPERATION BASES
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l A.
Core Spray and LPCI Mode of the RHR System This specification assures that adequate emergency cooling capability is available.
1 Based on the loss-of-coolant analyses included in References i and 2 and in acterdance with 10 CrR 50.46 and appendia K, core cooling systres providt i
s,.dftcient cooling to the core to dissipate the energy associated with the
-)
Icsr.-of-coolant accident, to limit the calculated fuel cladding temperature to less than 2200'F. to assure that core geometry remains intact to limit the corewide cladding metal-water reaction to less than 1% and to limit the calculated 1
local metal-water reaction to less than 171.
The allcwable repair times are established so that the aversos risk rate for repair would be no greater than the basic risk rate. The method and concept are described in Reference 3.
Using the recults developed in this reference.
the repair period is found to be less than ha!' the test interval. This assumes that the core spray subsystems and LPCI constitute a one-out-of-two i
system: however the combined effect of the two systems to limit escessive 4
cladding temperature must also be considered. The test interval specified in l
Specification 4.5 was 3 months. Therefore. an allowable repair period which maintains the basic risk considering single f ailures should be less than 30 days, and this specification is within this period. Fcr multiple failures, a l
shnrter interval is specified; to improve the assurance that the remaining systems will function, a daily test is called for. Although it is recognized
.j that the information given in Reference 3 provides a quantitative method to estimate allowable repair times, the lack of operating data to support the l
analytical approach prevents cu plete acceptanet of this method at this tf>e.
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Therefore, the times stated in the specific items were established with due l
regard to judgment.
Should one core spray subsystse become incuerable, the remaining core spray subsystem and the entire LPCI mode o the RHR system are available 3
should the need for core cooling arise. To assure tM t the remaining core spray and the LPCI moJe of the RHR system are availab'> they are demonstrated l
to be operable inenediately. This demonstration incle. % a manual initiation of the pumps and associated valves. Based on judgmen., 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 tore 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 justified. If the LPCI mode of the RHR system is not available, at least two RHR pumps must be available to fulfill the etntainment cooling function. The 7-day repair i
period is set on this basis.
1 E.
. RHR Service Water l
The containment cooling mode of the RHR system is provided to remove heat energy from the containment in the event of a less-el-coolant accident.
i 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 5ection 5.2.3.2).
l The Containment Cooling mode of the RHR System consists 3f two loops.
Each loop consists of I Heat Exchanger, 2 RHR Pumps, and the associated l
valves. piping, electrical equipment, and instrumentation. The "A" loop on i
each unit contains 2 RHR Service Water Pumps. Until November 1, 1989, the as" loop on each unit may utill:e the "C" and "D" RHR Service Water Pumps from t* nit 1 via a cross-tie line. Af ter Novembar 1,1989, each "S" loop will j
contain 2 RNR Service Water Pumps. Either set of egulpment is capable of performing the containment cooling functie:. Loss of orts RNR service water pump does not seriously jeopardige the c wtainment cooling capability, as any I
one of the remaining three pumps can satiUfy the cooling requirements. Since j
there is some redundancy lef t, a 30-day repair period is adeguate. Loss of I
one loop of the containment cooling mode of the RHR system leaves one i
remaining system to perform the containment cooling function. The operable system is demonstrated to be operable each day when the above condition occurs.
l 0265T:12 3.5/4.5-11 Amendment No. 68, 72 %,115
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