ML17195A125
| ML17195A125 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, 05000000 |
| Issue date: | 02/24/1984 |
| From: | Crutchfield D, Vassallo D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co, Iowa Illinois Gas & Electric Company |
| Shared Package | |
| ML17195A126 | List: |
| References | |
| DPR-19-A-081, DPR-25-A-073, DPR-29-A-087, DPR-30-A-082 NUDOCS 8402280492 | |
| Download: ML17195A125 (16) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 COMMONWEALTH EDISON COMPANY DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 81 License No. DPR-19
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
Tbe application for amendment by Commonwealth Edison Company (the licensee) dated January 12, 1982, 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 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 saf~ty 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 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. 81, 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.
Attachment:
Changes to the Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION j}. JJt_
~Crutchfield, Operating Re~ctors Bra Division of Licensing Date of Issuance:
February 24, 1984
ATTACHMENT TO LICENSE AMENDMENT NO. 81
- PROVISIONAL OPERATING LICENSE NO. DPR-19 AND AMENDMENT NO. 73 TO FACILITY OPERATING LICENSE NO. DPR-25 DOCKET NOS. 50-237/249 Revise the Technical Specifications by deleting the following page and inserting the enclosed page.
PAGE
. 45
TABLE 4.2.1 (Cont.)
DPR-19 NOTES:
- 7.
Functional tests will be conducted before startup at the end of each refueling outage or after maintenance is performed on a particular Safety/Relief Valve.
- 8.
Jf the number of position indicators is reduced to one indication on one or more valves, continued operation is permissible; however if the reactor is in a cold shutdown condition fQr more than seventy-two hours, it may not be started up until all position indication is restored.
In the event that all positipn indication is lost on one or more valves and such indication cannot be restored in thirty days, an orderly shutdown shall be initiated, and the reactor shall be depressurized to less than 90 psig in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 9.
The functional Test of the Scram Discharge Volume float switch shall include actuation of the switch using a water column.
- 10.
Functional test shall include verification of the second level undervoltage (degraded voltage) timer bypass and shall verify operation of the degraded voltage 5-minute timer and inherent 7-second timer.
45 Amendment No.~, flf,~, 81
- 1.
UNITED STATES e
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 COMMONl4EAL TH EDISON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR P0~
1 ER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 73 License No. DPR-25 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated Ja~uary 12, 1982, 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 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 changes to the Technical Specifications as indicated in the attachment to this license amendment 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. 73, 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.
Attachment:
Changes to the Technical Specifications*
FOR THE NUCLEAR REGULATORY COMMISSION L
"?/! 1,....-"""_u'..V~~
Dennis M. Crute 1e d, Operating Reactors Br Division of Licensing Date of Issuance:
February 24, 1984.
ATTACHMENT TO LICENSE AMENDMENT NO. 81 PROVISIONAL OPERATING LICENSE NO. DPR-19 AND AMENDMENT NO. 73 TO FACILITY OPERATING LICENSE NO. DPR-25 DOCKET NOS. 50-237/249 Revise the Technical Specifications by deleting the following page and inserting the enclosed page.
PAGE 45
TABLE 4.2.1 (Cont.)
DPR-25 NOTES:
- 7.
Functional tests will be conducted before startup at the end of each refueling outage or after maintenance is performed on a particular Safety/Relief Valve.
- 8.
If the number of position indicators is reduced to one indication on one or more valves, continued operation is permissible; however if the reactor is in a cold shutdown condition fQr more than seventy-two hours, it may not be started up until all position indication is restored.
In the event that all position indication is lost on one or more valves and such indication cannot be restored in thirty days, an orderly shutdown shall be initiated, and the reactor shall be depressurized to less than 90 psig in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 9.
The functional Test of the Scram Discharge Volume float switch shall include actuation of the switch using a water column.
- 10.
Functional test shall include verification of the second level undervoltage (degraded voltage) timer bypass and shall verify operation of the degraded voltage 5-minute timer and inherent 7-second timer.
45 Amendment No. 6', 73
It UNITED STATES e
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 QUAD CITIES STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 87 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 January 12, 1982, 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 CFR Chapter I; B.
The facility will operate in conformity with the applic~tion, **
the provisions of the Act and the rules and regulations of.the Commission; C.
There is reasonable assurance (i) that the acti.vitj~s auth_9rized by this amendment can be conducted without endangering the health and safety of the public, and (ii} that such activities will be conducted incompliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the hea 1th 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 appl1cable 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 fo 11 ows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 87, 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
-2Jlf/~
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 24, 1984 Domenic B. Vassallo, Chief Operating Re~ctors Branch #2 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NOS. 87 AND 82 FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 DOCKET NOS. 50-254/265 Revise the Appendix 11A 11 Technical Specifications by deleting the following page and inserting the enclosed page.
PAGE 3.2/4.2-15a
Notes QUAD-CITIES DPR-29
- 1.
Instrument channels required during power operation to monitor postaccident conditions.
- 2.
Provisions are made for local sampling and monitoring of drywell atmosphere.
- 3.
In the event any of the instrumentation becomes inoperable for more than 7 days during reactor operation, initiate an orderly shutdown and 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 />.
- 4.
From and after the date that one of these parameters is reduced to one indication, continued operation is not permissible beyond thirty days unless such instrumentation is sooner made operable.
In the event that all indication of these parameters is disabled and such indication cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition in twenty-four (24) hours.
- 5.
If the number of position indicators is reduced to one indication on one or more valves, continued operation is permissible; however if the reactor is in a cold shutdown condition for more than seventy-two (72) hours, it may not be started up until all position indication is restored.
In the event that all position indication is lost on one or more valves and such indication cannot be restored in thirty days, an orderly shutdown shall be initiated, and the reactor shall be depressurized to less than 90 psig in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Amendment No. Jlf, 87
.3.2/4.2-15a
e UNITED STATES e
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 License No. DPR-30
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated January 12, 1982, 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 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 Cammi ss ion*;
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 publi~; 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:
B.
Technical Specifications The Technical Specifications contained in Appendix A and B, as revised through Amendment No. 82, 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.
Attachment:
Changes to the Technical Specifications Date of Issuance: February 24~ 1984
~~
COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NOS. 87 AND 82 FACiLITY OPERATING LICENSE NOS.
DPR~29 AND DPR-30 DOCKET NOS. 50-254/265 Revise the Appendix 11A 11 Technical Specifications by deleting the following page and inserting the enclosed page.
PAGE 3.2/4.2-15a
Notes QUAD-CITIES DPR-30
- 1.
Instrument channels required during power operation to mo~itor postaccident conditions.
- 2.
Provisions are made for local sampling and monitoring of drywell atmosphere.
- 3.
In the event any of th~ instrumentation becomes inoperable for more than 7 days during reactor operation, initiate an orderly shutdown and 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 />.*
- 4.
From and after the date that one of these parameters is reduced to one indication, continued operation is not permissible beyond thirty days unless such instrumentation is sooner made operable.
In the event that all indication of these parameters is disabled and such indication cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition ih twenty-'four (24) hours.
- 5.
If the number of position indicators is reduced to one indication on one or more valves, continued operation is permissible; however if the reactor is in a cold shutdown condition for more than seventy-two (72) hours, it may not be started up until all position indication is restored.
In the event that all positi6n indication is lost on one or more valves and such indication cannot be restored in thirty days, an orderly shutdown shall :be
.initiated, and the reactor shall be depressurized to less than 90 psig in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Amendment No.;xr; 82 3.2/4.2-lSa