ML20055B161
| ML20055B161 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, 05000000 |
| Issue date: | 07/09/1982 |
| From: | Crutchfield D, Vassallo D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co, Iowa Illinois Gas & Electric Company |
| Shared Package | |
| ML20055B162 | List: |
| References | |
| DPR-19-A-073, DPR-25-A-065, DPR-29-A-080, DPR-30-A-074 NUDOCS 8207200427 | |
| Download: ML20055B161 (17) | |
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UNITED STATES g
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C0MMONWEALTH EDISON COMPANY 0
DOCKET NO.50-23Z,.
DRESDEN NUCLEAR ~ POWER STATION UNIT 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 73 License No. DPR -19 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the - *
- licensee) dated April 29, 1982 complies with 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 (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 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 amend-ment, and paragraph 3.B of Provisional Operating License No. DPR-19 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 73, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
9207200427 E20709
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PDR ADOCK 05000237 P
2 3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
.y Dennis M. Crutchfield, ief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 9,1982 i
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e ATTACHMENT TO LICENSE AMENDMENT NO. 73 PROVISIONAL OPERATING LICENSE N'O. DPR-19 DOCKET NO. 50-237 Remove Insert
- p. 77
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- 1.5 1.!AllTING CONDITION FOh OPERATION 4.5 SUllVEILLANCE HEQUIREh1ENT '
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containment coolin'g subsystem, both core spray subsystems and both diesel gencr-
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aturs required fur operattun of such components if no external source of -
' power were avallsble, shall be operabic.
4.
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.
IIPCI &nbsystem C.
Surveillance of IIPCI Subsystem shall be porformed as follows:
1.
Except as specified in 3.5.C.2 below.
1.
IIPCI Subsystem Testing shall be as spect-the IIPCI subsystem shall be operable
' fled:Id 4.5. A. I.a, b, c, d, and f, except whenever the reactor pressure is greater that the IIPCI pump shall deliver at least '
than 90 p*sig and Irradiated fuel is in the 5000 gym against a system head correspond-i Ing to a reactor vessel pressure of 1150 pelg
. reactor vessel.
to 150 psig.
2.
i' rom and after the date that the llPCI subsystem ls made or found to bc Inoper-I.
When it is determined that HPCI subsystes is inoperable, abIc for any reason, reactor operation is the 1.pCI subsystem, both core spray stabayetems, the auto-
.atic prH ure n 11er sub yst.. an4 the.ator opu sted Pcrmissible onty durinE the succeedinE i.1 stix valve and ehe11 ide make-up syste. ror the seven days unless such subsystem is
- i. lation condenser sy.t
. hell b. de.onstrated to be sooner made operabic, provided that dur-operable lamediately. The motor operated isolation valves
- "d 'h*11 'Id' **k*-"P system of the isolation condenser Ing such seven days all active components shall be demonstrated to be operable daily thereafter.
of the Automatic Pressure Relief Sub-cally de.oo tratio. of the automatic pres.ure relier ub-syste= operability is not required provided that two system, the core spray subsystems, LPCI fH dwater pumpe are operating at power levels above 300 subsystem, and Isolation Coollng system Weg and one feedwater pump is operating as normally re-are operable.
,ui,ed.ith o,e addici 1 reed.at,r,u.,o,e,a,ie at power levele less than 300 Wo.
3.
If the requirements of 3.5.t: canno.t be met an orderly shutdown shall be initiated *and the reactor pressure shall be reduced to
- 90 psig within 24 Imurs.
- e Amendment '!.o.
65, 73 77
e, UNITED STATES 8
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDENNUCLEARPOWERSTAbhkUNIT3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. DPR-25 l.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the i
licensee) dated April 29, 1982, as supplemented by letter dated
. May 25,1982 complies with 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 o)erate in conformity with the application, the provisions of t1e 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 Commission's regulatio'ns; 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.
Ac'cordingly, the license is amended by changes <to the Technical Specifications as indicated in the attachment to this license amend-ment, and paragraph 3.B of Facility Operating License No. DPR-25 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 65, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3
t 2
3.
This license amendment is effect.ive as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
?
enic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 9, 1982
ATTACHMENT TO LICENSE AMENDMENT NO. 65 FACILITY OPERATING LICENSE NO. DPR-25 DOCKET NO. 50-249 1
Remove Insert
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~v DPR-25 TABIP-3.1.1 (Cont.)
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\\j Modes in Which Function i
Minimum Must be Operable of Operable Inst.
i Startup/ Hot l
Channels per Trip l
(1) System Trip Function Trip Level Setting Refuel (7)
Standby Run ictione i
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2 Turbine Condenser Low
>23 in. Hg Vacuum X(3)
X(3)
X A or C Vacuum l
2 Main Steam Line High
$3 X Hormal Full Power X(3)
X(3)
X A or C Radiation
Background
4(6)
Main Steam Line Isolation
<10% Valve Closure X(3)
X(3)
X A or C Valve closure 2
Cenerator Load Rejection X(4)
X(4)
X(4)
A or C I
2 Turbine Stop Valve
<10% Valve closure X(4)
X(4)
X(4)
A or C Closure 2
Turbine Control - Loss of >900 psig X
X K
A or C Control Oil Pressure
]
Notes:
There shall be two operable or tripped trip systems for each function.
1.
Permissible to bypass, with control rod block, for reactor protection system reset in refuel and shutdown positions 2.
of the reactor mode switch.
3.
Permissible to bypass when reactor pressure is <.600 psig.
Permissible to bypass when first stage turbine pressure less than that which corresponds to 45% rated steam flow.
4.
IRM's are bypassed when APRM's are onscale and the reactor mode switch is in the run position.
5.
6.
The design permits closure of any one valve without a scram being initiated.
When the reactor is subcritical and the reactor water temperature is less than 212'F, only the following trip 7.
functions need to be operable:
a.
Mode Switch in Shutdown b.
Manual Scram' c.
High Flux 1RM d.
Scram Discharge Volume High Level 8.
Not required to be operable when primary containment integrity is not required.
Not required while performing low power physics tests at atmospheric pressure during or af ter refueling at power 9.
24 levels not to exceed 5 MW(t).
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~ 's.n I.lAllTING CONDITION F(Rt OPEftATION 4.5 SURVEILIANCE REQUELEllENT l
8 containment cooling subsystem, both core.
i spray subsystems and Imth diesel gence-l ators required fur operation of such components if no external source of power were available, shall be operable.
4.
If the requirements of 3.5.8 cannot be met sn 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 />.
i C.
IIPCI thesystem C.
Surveillance of HPCI Subsystem shall be performed as follows:
1.
Except as specified in 3.5.C.2 below, 1.
IlPCI Subsystem Testing shall be as spect-the llPCI subsystem shall be operable
' fled:In 4.5. A.1.s, b, c, d, and f, except whenever the reactor pressure is greater that the llPCI pump shall deliver at least than D0 psig and irradiated fuel is la the 5000 gpm against a system head correspond-Ing to a reactor vessel pressure of 1150 pelg
. reactor vessel.
to 150 psig.
l 2.
From and after the date that the IIPCI subSystein la mado or found to bc Inoper-2.
When it is determined that RPCI subsystem is inoperable, "h* "C1 '"berstem, both core spray agbsystems, the auto-able for anI reason' reactor operation is matic pressure relief subeystem, and the motor o prated permissible only during the succeeding isolation v.1ves and shell side maketup ey. tem for the seven days unIcss such subsystem la isolation condenser system shall be demonstrated to be sooner made operable, provided that dur-operable immediately. The motor operated isolation valves Ing such seven days all active components
- dg*h(1,$,"*[P '7[*yf @*'j"'$" j"
of the Automatic Pressure Ilclief Sub-esity demonstration of the automatic pre.ure relief sub-system, the core spray subsystems, LPCI system operability te not required provided that two feedvater p a pe are operating at power levels above 300 subsystem, and Isolatlob coollng system We; and one feedvater pump is operating as normally re-are operagye' quired with one additional feedvater pump operable at power levels less than 300 W o.
3.
If the requirements of 3.5.c cannot be met an orderly shutdown shall be inittsted and the reactor pressure shall be reduced to 90 pois within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Amendment No. E7, 65 77
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
'u COMMONWEALTH EDISON COMPANY AND IOWA ILLIN0IS GAS M ELECTRIC COMPANY DOCKET NO. 50-254
- a QUAD CITIES STATION UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE
~ ~ ~
Amendment No. 80 License No. DPR-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated April 29, 1982 complies with 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 (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 no't be inimical to the common
~
defense and security or to the health and safety of the public; l
and E.
The issuance of this amendment is in accordance with 10 CFR Part l
51 of the Commission's regulations and all applicable requirements have been satisfied.
2.' Accordingly, the license is amended by changes.co the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. DPR-29 is hereby amended to read as follows:
3.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 80, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
l
=
2 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. 'Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 9, 1982 S
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1 ATTACHMENT TO LICENSE AMENDMENT NO. 80 FACILITY OPERATING LICENSE NO. DPR-29 DOCKET NO. 50-254 Remove Insert t
- p. 3. 5/4. 5-5
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operable immediately. The RCIC primded that dr.ing such 7 days a!!
,y, tem on.23 3e a,,on er g.a e,
active componers of the automatic be operable daily thereafter.
Daily demonstration of the pressure relief absystems, the core automatic pressure relief sub-spray subsysterrn LPCI mode of the system operabilty is not required RHR system.andthe RCIC system are provided that two feedwater pumps
- are operating at levels above 300 operable.
% Wer and one feedwater pump is
- 3. If the niremets of S ecification perating as normally required I
with one additional feedwater 3.5.C cannot be set, an orderly shut-pump operable at power levels down shall be in' dated. and the reaC-less than 300 Mwe.
tor pressun shall'm: reduced to 90 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. Automatic Pressure Relief Subsystems D. Automatic Pressure Relief Subsystems Surveillance of the automatic pressure relief
/
subsysteins shall be performed as follows:
- 1. The automatic pessure relief subsys-1.
The following surveillance shall be carried out on a tem shall be opeable whenefer the six-month surveillance reactor pressureis grenier than 90 interval:
psig, irradiated 6el is in the reactor vasel and prior to reactor startup from a cold condsion.
b a. With' the reactor at I
- 2. From and sihtfedate that one of the Prsseure each relief Ave reliervalves dithe automatic pres-valve shall be manually sure reliersubsysten is made or found opened. Relief valve to be inoperable when the reactor is Opening shall be verified pressurized abovef0 psic with irradi.
7 8 C 2Pensating tur'eine
~
ated fuel in the rector vessel, reactor bypass valve or control operation is P'misib!c only during valve closure.
the succeediog 7 days unless repain 2.
A logic system functional
, are made and prwided that during such time the RCI subsystem is test shall be performed each refueling outage.
2.a Plant operation shall be 3.
A simulated automatic initiation i
in accordance with 3.5.D.2 which opens all pilot valves e performed each refueling I
above except that, for the u age current operating cycle 5, four of the five relief 4
When it is determined that one relier valves of the ADS are valve of the automatic pressure relief required to be operable.
subsystem is inoperable. the 'HPCI In subsequent operating shall be. demonstrated to be operable cycles, operation shall be immediately and weekly theresfter.
in accordance with 3.5.D.2.
3.
If the require =ents of Specifi-((. s.
. cation 3.5.D cannot be met, an l,,
orderly shutdown shall be initiated and the reactor pressure shall be reduced to 90 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
AcendmentNo.g 80 3.5/4.5-5
6
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,S UNITED STATES g
NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20555
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l COMMONWEALTH EDIS0N COMPANY
^
AND IOWA ILLIN0IS GAS AND ELECTRIC COMPANY ~
DOCKET NO. 50-265 ~'a QUAD CITIES STATION UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. DPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commwealth Edison Company (the licensee) dated April 29, 1982 complies with standards and i
requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR i
Chapter I; l
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 endan.gering the health j
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 l
defense and security or to the health and safety of the public; and l
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 licen'se is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. DPR-30 is hereby amended to read as follows:
l B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 74, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
l I
2 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 9,1982 O
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ATTACHMENT TO LICENSE AMENDMENT NO. 74 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-265 Remove Insert
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i QUAD-CITIES DPR-30 (Fr.
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provided that during such 7 days all operable immediately. The acre active components of the automatic system shall be demonstrated to be perable daily thereafter.
Pressure relief subsystems, the core cally demonstration of the spray subsystems. LPCI rnode of the
..; automatic pressure relief sub-RHR system.and the RCIC system are system operabilty is not required operable.
provided that two feedw'ater pumps are operating at levels above 300
- 3. If the requirements of Speci6 cation Wer and one.feedwater pump is 3.5.C cannot be met. an orderl shut.
P**1"9
- " '"*llY 9"Id I
with one additional feedwater down shall be initiated, and the reac-pump operable at power levels for pressure shall be reduced to 90 psig less than 300 Mwe.
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. Automatic Prewure Relief Subsystems D. Automatic Prewure Relief Subsystems
/
Surveillance of the automatic pressure relief sub-systems shall be performed as follows:
.1.
The automatic pressure relief subsys-
- 1. The fo!!owing arveillance shall be carried tem shall be operable whenever the out on a 6 month surrveillance interval:
reactor pressure is greater than 90 psig, irradiated fuel is in the reactor vessel and prior to reactor startup With the reactor at pressure each from a cold condition.
a.
relief valve shall be manually epened.
Relief valve opening shall be verified by a compensating turbine bypass valve or control valve closure.
- 2. A logic system functional test shall be performed each refueling outage.
2.
From and after the date that one of the 3.
A simulated automatic initiation five relief valves of the automatic pres-which opent all pilot. valves t
shall be performed each refueling I
aJte relief subsystem is made or found outage.
to be inoperable.when the reactor is pressurized about 90 psig with irradi-
- 4. When it 1 determined that one relief sted fuel in the reactor vessel. reactor valve of the automatic pressure relief operation is permissible only during the subsystem is inoperable, the HPCI shall succeeding 7' days unless repairs are be demonstrated to be operable im.
made and provided that during such time mediately and weekly thereafter.
the HPCI subsystem is operable.
- 3. If the requirements of Specification 3.5.D cannot be met, an orderly shut-down shall be initiated and the reactor pressure sha!! be reduced to 90 poig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
f.f 3.5/4.5-5 Amendment 2* 5/2l7' 74
-