ML20114D181
| ML20114D181 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 08/27/1992 |
| From: | Barrett R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20114D183 | List: |
| References | |
| NUDOCS 9209080016 | |
| Download: ML20114D181 (10) | |
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3' UNITED STATES 3
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WASHINGTON. D C. 20555
@MMONWEALTH EDIS0N COMPANY MQ IOWA-IllIN0IS GAS ARD ELECMIC COMPANY DOCKET NO. 50-254 QF @ CITIES NUCLEAR POWE' STATION. UNIT 1 7
$MENDMENT TO FACll]TY OPBATING llCEME Amendment No. 137 License No. OPR-29 1.
The Nuclear Regulatory Comr.ission (the Commission) has found that:
s A.
The application,*or amendment by Commoawealth Edison Company (tha licensee) dated January 21, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules atid regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applicatior, the provisions of the /f_t, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorizeo 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 rq ulations; 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 cf this amendment is in accordance witt 10 CFR l
Part 51 of the Commission's regulations and all apr cable 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 L. cense No. DPR-29 is hereby amended to read as follows:
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. B.
Technical Specifications lhe Technical Specifications contained in Appendices A and B, as revised through Amendment No.137, 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 pN.
- P.ichard J. Barrett, Director Projact Directorate 111-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 2/, 1992
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m ATTACHMENT TO LICENSi AMENDMENT N0. 137
-FACILITY OPERATING LICENSE NO. DPR-29 DOCKET N0. 50-254 Revise the AppendixLA 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 marainal lines indicating the area of change.
BEMQEE INSERT 3.5/4.5-5 3.5/4.5-5 3.5/4.5-7 3.5/4.5-7 i
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QUAD-CITIES DPR-29 4.
Containment cooling spray loops 4.
During each 5 year meriod, an are required to be operable when air test shall be performed on the reactor water temperature is the drywell spray headers and greater than 212 F and prior to nozzles and a water spray test reactor startup from a cold con-performed on the toras spray d: tion.
Continued reacter oper-header and nozzles, ation is permitted provided that a ma> imum of one drywell spray loop may be inoperable for 30 days when the reactor water tem-perature is greater than 212'F.
5.
If the requirements of 3.5.B cannot be met, an orderly shut-S down shall be initiated, ar.d the reactor shall be in a' 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 />, n
C.
HPCI Subs 3 stem C.
HPCI Subsystem P
1.
The HPCI subsystem shall be Surveillance of HPCI subsystem shall operable whenever the reactor be performed as specified below with pressure;is greater than 150 the following limitations.
For item psig and fuel is in the 4.5.C.3, the piant is allowed 1/ hours reactor vessel.
in which to successfully complete the test once reactor vesse pressure is 2.
Durir.g startup following a refuel adequate to perforni each test.
In outage or an outage in which work addition, the testing required by item was performed that directly affects 4.5,C.3.a shall be completed prior to HPCI system operability, if the exceeding 325 psig reactor vessel testing requirements of 4.5.C.3.a l
pressure.
If HPCI is made inoperable canact be met, continued reactor to perform ovarspeed testing, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> startup is not permitted.
The is allowed to complete the tests before HPCI subsystem shall be declared exceeding 325 psig.
inoperable, and the provisions of Specification 3.5 C.4 chall be Item Frequency implemented.
1, Valve Position Every 31 days 3.
Except fcr the limitations of 3.5.C.2, if the HPCI subsystem 2.
Flow Rate Test-Every 92 days is made or found to be inoperabic, HPCI Pump shall continued reactor operation is deliver at least permissible only during the suc-5000 gpm against ceeding 14 days unless such sub-a system head cor-system is sooner made operable, responding to a provioed that during such 14 days reactor vessel the automatic pressure relief pressure of > 1150 subsystems, the core spray sub-psig when steam 1s systems, LPCI mode of the RHR being supplied to system, and the RCIC system are the turbine at 920 operable.
Otherwise, the pro-to 1005 psig.
visions of Specification 3.5.C.4 shall be implemented.
3.5/4.5-5 Amendment No. 137
QUAD-CITIES DPR-29 when the reac'.ar is pressurized above 90 psig with irradiated fuel in the reactor vessel, reactor operation is permissible only during the succeeding 7 days unless repairs are made and provided that during such time the HPCI subsystem is opers.ble.
3.
If the requirements of Specifi-3.
A simulated automatic initiation cation 3.5.0 cannot be met, an which opens all pilot valves orderly shutdown shall be initi-shall be performed each re-ated and the reactor pressure fueling outage.
shall be reduced to 90 psig within 24 hers 4.
When it is det9rmined that two e
valves of the oJtomatic pressure relief subsystem are inoperable, the HPCI shall be demonstrated to be operable immediately.
E.
Reactor Core Isolation Cooling System E.
Reactcr Core Isolation Cooling System 1.
The RCIC system will be operable Surveillance of the RCIC syr Am shall whenever the reactor pressure is be performed as specified below with greater than 150 psig and fuel is the following limitations.
For item in the reactor vessel.
4.5.E.3, the plant is allowed 12 hot s in which to successfully complete the 2.
During startup following a refuel test once reactor vessel pressure is outage oc an outage in which work adequate to perform each test.
In was performed that directly affects addition, the testing required by itu the RCIC system operability, if the 4.5.E.3.a shall be completed prior to testing requirements of 4.5.E.3.a l
exceeding 325 psig reactor vessel cannot be met, continued reactor pressure.
If RCIC is made inoperable startup is not permitted.
The to perform overtaeed testing, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> RCIC system shall be declared is allowed to complete the tests before inoperable, ana the provisiens of exceeding 325 psig.
Spec'fication 3.5.E.4 shall be implemented.
Item Frequency 3;
Except for the limitations of 1.
Valve Position Every T1 day 9
3.5.E.2, if the RCIC system is made or found to be inoperable, 2.
Flow Rate Test -
Every 92 days continued reactor operation is RCIC Pump shall permissible only during the suc-deliver at least coeding 14 days unless such sys-400 gpm against tem is sooner made operaole, a system head provided that during such 14 days corresponding to the HPCI system is operable.
a reactor vessel Otherwise, the provisions of pressure of > 1150 Specification 3.5.E.4 shall be psig when steam is implemented.
3.5/4.5-7 Amend.ent No. 137 l
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.CDfiMONWEALTH EDISDN COMPANY aliQ IOWA-ILLIN0IS GAS ANDlLECTRIC COMPANY POCKET NO. 50-265 OVA 0 CITIES NUf. LEAR POWER STATION. UNIT 2 AMENDMENT TO F8CILITY OPERATING LICENSL Amendment No. 133 License No. DPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for a.nendment by Commonwealth Edison Company (the licensee) dated January 21, 1992, 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 CFD. Chapter I; B.
The facility will operate in conformity with the applicatico, 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, aid (ii) thi.t such activities will be condt:cted 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 f.onenission'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 Operatirg License rio. DPR-30 is hereby amended to read as follows:
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B.
Technical Soecifications The Technical Specifications contained in Appendices A and B, 6s revised through Amendment No.133, 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 i'UCLEAR RESULATORY COMMISSION
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gy Richard JT Barrett, Director Project Directorate III-2 Division of Reactor Projects - Ill/IV/V Office of Ibcisar Reactor Regulation
Attachment:
Changt to the Technical
-Specifications Date of Issuance: August 17, 1992
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ATTACHMENT TO LICENSE AMENDMENT NO. 133 FACILITY OPERATING LICENSE NO. DFR DOCKET NO. 50-265 Revise the' Appendix A Technical Specifications by removing the pages TJentified 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 3.5/4.5-4a 3.5/4,5-4a 3.5/4.5-6 1.5/4,5-6 q
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DPR.30 C.
HN1 Subsystem Surveillance of the HPCI subsystem shall be perfomed as specified below with the f ollowing lie;'stions. For item 4.5.C.3. the plant is allowed 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, in which to successfully complete the test once reactor pressure is adequate to pertr.rm each test. In addition, the testing required by item 4.5.C.3.a shall be completed prior to excecilng 325 psig l
reactor vessel pressure. If HPCI is made' inoperable to ferform overspeed testing, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is allowed to complete the tests before exceeding 325 psig, l'.n fItauency 1.
The HPCI subsystem shall be 1.
Valve Position Every 31 days operable whenever the reactor pressure is greater than 150 psig ano fuel is in the reactor vessel.
2.
During star'sp f ollowing a 2
Flow Rate Test -
Every 92 days ref uel outage or an outage in HrC1 pump shall which work was performed that deliver at lewst direct 1v affects HPCI system 5000 gpm against operabliity if the testing a system head requi+ements of 4.5.C.3.a cannot i o rresponding be met, sontinued reactor to a reactor startup is not permitteJ. The vessel pressure HPC? subsystem shall be declste:.
of 11150 psig when inoperable, and the provisiens steam is being of Specification 3.5 C.4 shall supplied to the be implemented, turbine at 920 tt, 1005 psig.
3.
Except for the limitations of 3.
Flow Rate Test -
During 3.5.C.2, if the HPCI subsystee HPCI pump shall startur is made or found to be delive at least following inoperable, continued reactor 5000 pn against a refuel operation is permissikle only a system head outage during the succeedinD 14 days corresponding to er an outage unless such subsystem is sooner a reactor vessel in which work made operable, provided that pressure of:
was performed during such 14 days the
- a. 1 300 psig that directly automatic pressure relief when steam is affects HPCI subsystem, the core spray be8ng supplied system subsystees, LPCI mode of the RHR to the turbine operability.
system, and the RCIC system are at 250 to 325 operable. Otherwise, the psig, and provisions of 5pecification
- b. 1 1150 psig when 3.5.C.4 shall be implemented.
steam is being supplied to the turbine a'. 920 to 1005 psig 4.
If the rsquirements of 4
Simulated Each refueling Specification 3.5.C.1, 3.5.C.2 Automatic outage or 3.5.C..I cannot be met, an Actuation Test orderly shutdown shall be init$ated, and the reactor 5.
Logic System Each refueling pressure shell be revluced to functional outage
<l50 rsig within L4 hours.
test 3.5/4.5 4a Amendment No. 133
QUAD-CITIES DPP.-30 E.
Reactor Core Isolation Cooling System E.
Reactor Core Isolation Cooling System Surveillance of the RCIC system shall be performed as specified below with the following limitations. For item 4.5.E.3. the plant is allowed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in which to successfully complete the test once reactor vessel pres >ure is adequate to perfor*- ea*h test. In addition, the testino required by item 4 C.E.3.a shall be completed prior tc =<ceeding 325 psig reactor vessel presaure. If RCIC is made inoperable to perform overspeed testing, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is allowed to complete the tests before exceeding 325 psig.
lies treauency 1.
The RCIC system will be operable 1
Valve Position Every ;41 days whenever the reactor pressure is greater than 150 psig and fuel is in the reactor vessel.
2.
During startup following a 2.
Flow Rate Test -
Every 92 days refuel outage or en outage in RCIC pump shall which work was performed that deliver at least directly affects RCIC system 400 gpm against operability, if the testing a system head requirements of 4.5.E.3.a cannot l
corresponding be met, continued reactor to a reactor startup is not permitted. The vessel pressure RCIC system shall be declared of 11150 psig when inoperable, and the provisions steam is being of Specification 3.5.E.4 shall supplied to the be implemented.
turbine at 920 to 1005 psig.
3.
Except for the limitations of 3.
Flow Rate Test -
During 3.5.E.2, if the RCIC system is RCIC pump shall startup made or found to be inoperable, deliver at least in11owing continued reactor operation is 400 gem against a refuel permitted only during the a system head outage succeeding 14 days unless such corresponding to or an outage system is sooner made operable, a reactor vessel in which work provided that during such 14 prcssure of:
was performed deys the HPCI system is
- a. 1 300 psig that directly operable. Otherwise, the when steam is affects RCIC provisions of Specification being supplied system 3.5.E.4 shall be implemented.
to the turbine operability.
at 250 to 325 psig, and.
- b. 1 1150 psig when steam is being supplied to the turbine at 920 to 1005 psig.
4.
If the requirements of 4.
Simulated Each refueling specification 3.5.C.1, 3.5.E.2 Automatic outage or 3.5.E.3 cannot be met, an Actuation Test orderly shutdown shall be initiated and the reactor 5.
Logic $ystem Esch refueling pressure shall be reduced to functional outage (150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Teet 3.5/4.5-6 Amendment No. 133