ML19296B139
| ML19296B139 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 02/01/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19296B140 | List: |
| References | |
| NUDOCS 8002200139 | |
| Download: ML19296B139 (12) | |
Text
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UNITED STATES f
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NUCLEAR REGULATORY COMMISSION E
WASHINGTON. D. C. 20555 t
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'49.... +,o COMMONWEALTH EDISON COMPANY DOCKET NO. 50-237 DRESDEN STATION UNIT NO. 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 46 License No. DPR-19 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated January 24, 1980, as supplemented January 28, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rule: snd regulations set forth in 10 CFR Chapter I; B.
The facility will operate in cc,nfamity 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, anc (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 comon defense and se::urity 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:
(1) Changing paragraph 3.B as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A.
as revised through Amendment No. 46, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(2) Adding paragraph 3.J.
3.G. Operating MAPLHGR limit for all fuel types shall be restricted to 86.8% of those given in Section 3.5 of the Technical Specifications. This restriction shall apply until all five ADS valves are operable.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
- b. b f & Thomas A. Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 1, 1980
ATTACHMENT TO LICENSE AMENDM'ENT NO. 46 PROVISIONAL OPERATING LICENSE NO. DPR-19 DOCKET NO. 50-237 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.
Remove Insert 78 78
r 3.5 LittITING CONDITION FOR OPERATI0tl 4.S SURVEII.1.ANCE REQUIREMEfff D.
Auto:natic Pressure Rollof Subsystems D.
Surveillance of the Automatic Pressure Relief Subsystem shall be performed as follows:
1.
Except as specified in 3.5.D.2 and 3 below, 1.
During each operating cycle the following the Automatic Prtssure Relief Subsystem shall be performed:
shall be operab'.i whencver the reactor pressure is great.or than 90_psig and irradiated A.
A simulated automatic initiation fuel is in the re. actor vessel.
which opens all pilot valv:s, and b.
With the reactor at pressure each 2.
From and after the date that one of the i
relief valve shall be manually opened.
five relief valves :6ft.the automatic pressure i
Relief valve opening shall be verified by relief subsystem is cade or found to be a compensating turbine bypass valve or inoperabic when the reactor is pressurized control valve closure.
abo 3c D0 psig with irradiated fuel in the redctor vessel, reactor operation is permissible c.
A logic system functional test shall be only during the succeeding seven days unless performed each refueling outage.
repairs are made and provided that during such tirte the llPCI Subsystem is operabic.
- 22. When it is determined that one relief valve of the automatic pressure relief subsystem 3.
From and cfter the date.that more than one l
is inoperable, the llPCI shall be demonstrated of five.rclief valves of the autematic to be operable imediately and weekly thereaften pressure relief subsystem made or found to be inoperabic i. hen the reactor is pressuti:ed above 90 psig with irradiated fuel in the reactor vessel, ~ reactor operation is permissible only during the succeeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless repairs are made and provided that during such timo the HPCI Subsystem 3.
When it is determined that more than one is operablo.
l relief valve of the at.tomatic pressure relief subsystem is inoperable, the liPCI subsystem 3.a.
Plant operation shall be in accordance with shall be demonstrated to be operable imediato!)
3.5.D. 2 and 3.5.D. 3 above except that for the current operating cycle 7, four of the five relief valves of the ADS are required to be operable.
In subsequent operating cycles, operation shall be in accordance with 3.5.D.2 and 3.5.D.3.
Amendment No. 2$, 46 78
[,pa maeoq'o, UNITED STATES 8'
-~j NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555 t
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDEN STATION UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 License No. DPR-25 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated January 24, 1980, as supplemented January 28, 1980, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic
, 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by:
(1) Changing paragraph 3.B as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 40, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(2) Adding peragraph 3.I.
3.G Operating MAPLHGR limit for all fuel types shall be restricted to 95.4% of those given in Section 3.5 of the Technical Specifications. This restriction shall apply until all five ADS valves are operable.
3.
This license amendment is dffective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION N, &
W==
yN Thomas A. Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 1, 1980
ATTACHMENT TO LICENSE AMENDMENT NO. 40 FACILITY OPERATING LICENSE NO. DPR-25 DOCKET NO. 50-249 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.
Remove Insert 78 78
3.S 2.IttITING CONDITION FOR OPEPATION 4.S SURVEILI.ANCE REQUIREHENT D.
Auto:natic Pressure Re11of Subsystems D.
Surveillance of the Automatic Pressure Rolief Subsystem shall bo performed as follows:
1.
Except as specified in 3.5.D.2 and 3 below, 1.
During each operating cycle the following the Automatic Pressure Relief Subsystem shall be performed:
shall be operable whenever the reactor pressure is greater than 90 psig and irradiated A.
A simulated automatic initiation fuel is in the reactor vessel.
which opens all pilot valv:s, and b.
With the reactor at pressure each 2.
From and after the,date that one of the j
relief valve shall bo manually opened.
five relief valves.bftthe automatic pressure i
Relief valve opening shall be verified by relief subsystem is cade or found to be a compensating turbine bypass valve or inoperable when the reactor is pressurized control valve closure, abo 3c 00 psig with irradiated fuel in the redctor vessel, reactor operation is permissible c.
A logic systen functional test shall be only during the succeeding seven days unless performed each refueling outage, repairs are made and provided that during such tinto the llPCI Subsystem is operable.
- 22. When it is determined that one relief valve of the automatic pressure relief subsystco is inoperable, the llPCI shall be demonstrated 3.
From and after the date.that more than onc of five.rclief valves of the autematic to be operablo imediately and weekly thereafter pressure relief subsystem made or found to be inoperabic i. hen the reactor is pressur-iaed above 90 psig with irradiated fuct in the reactor vessel,' reactor operation es permissible only during the succeeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless repairs are made and provided that during such time the HPCI Subsystem 3.
When it is detensined that more than one is operablo.
relief valve of the at.tomatic pressure relief subsystem is inoperable, the HPCI subsystem 3.a.
Plant operation shall be in accordance with shall be demonstrated to be operable imediatch 3.5.D. 2 and 3.5.D. 3 above except that for the current operating cycle 6, four of the five relief valves of the ADS are required to be operable.
In subsequent operating cycles, operation shall be in accordance with 3.5.D.2 and 3.5.D.3.
Amendment No. 28, 40 78
+f UNITED STATES Eb#(3 h NUCLEAR REGULATORY COMMISSION
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E WASHINGTON, D. C. 20656 9, %
4., %
COMMONWEALTH EDISON COMPANY _
AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 QUAD CITIES STATION UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 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 January 24, 1980, as supplemented January 28, 1980, 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 comon 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 amnded by:
(1) Changing paragraph 3.B as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendme,nt No. 55. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(2) Adding paragraph 3.G.
3.G. Operating MAPLHGR limit for all fuel types shall be restricted to 86.8% of those given in Section 3.5 of the Technical Specifications. This restriction shall apply until all five ADS valves are operable.
3.
This license amendment is iffective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION E.O.h p Thomas A. Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 1,1980
ATTACHMENT TO LICENSE AMENDMENT NO. 55 FACILITY OPERATING LICENSE N0. OPR-29 DOCKET NO. 50-254 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.
Remove Insert 3.5/4.5-5 3.5/4.5-5
QUAD-CITIES DPR-29 provided that dring such 7 days all operable immediately. The automatic active compop:ss of the automatic pressure relief and RCIC systems shall pressure relief ubsystems, the core be demonstrated to be operab!c daily spray subsystems, LPCI mode of the thereafter.
RHR system.andthe RCIC system are operable.
- 3. If the requiremets of Specification 3.5.C cannot be set, an orderly shut.
down shall be intiated, and the reac.
tor pressure shallie 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 Re;idSubsystems 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 tem shall be opeable whenever the shall be carried out on a reactor pressureis greater than 90 six-month surveillance psig, irradiated fiel is in the reactor interval:
vessel and pnor to reactor startuP a.
A simulated automatic initiation from a cold condsion.
which opens all pilot valves.
b.
With the reactor at 2.
From and after thedate that one of the five relief valves o'ithe automatic pres.
pressure each relief sure relief subsysten is made or found valve shall be manually to be inoperable when the reactor is Pened.
Relief valve pressurized above 10 psig with irradi.
Pening shall be verified ated fuel in the resctor vessel. reactor by a compensating turbine bypass valve or control operation is pennssible only during va ve closure, the succeeding 7 days unless repairs are made and provided that during 2.
A logic system functional such time the IPCI subsystem is test shall be performed operable.
each refueling outage.
3.
When it is determined that one relief 2.a Plant operation shall be in accord.mce with 3.5.D.2 valve of the automatic pressure relief above except that, for the subsystem is inoperable. the HPCI gg current operating cycle 5, i
j four of the five relief mmediately and weekly thereafter.
valves of the ADS are required to be operable.
In subsequent operating cycles, operation shall be in accordance with 3.5.D.2.
3.
If the requirements of Specifi-cation 3.5.D cannot be met, an orderly shutdown shall be initiated and the reactor preseure 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 />.
Amendment No.,46',
55 3.5/4.5-5