ML20149L394
| ML20149L394 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/17/1988 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co, Iowa-Illinois Gas & Electric Co |
| Shared Package | |
| ML20149L398 | List: |
| References | |
| DPR-29-A-105, DPR-30-A-101 NUDOCS 8802240214 | |
| Download: ML20149L394 (8) | |
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g NUCLEAR REGULATORY COMMISSION E
WASHING TON, D. C. 20555
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LOMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET N0. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 105 License No. DPR-29 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Connonwealth Edison Company (the licensee) dated October 16, 1987 as supplemented by November 24, 1987, 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 amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-29 is hereby amended to read as follows:
8802240214 880217 DR ADOCK 050 24
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I B.
Technical Specifications The Technical Specifications contained in Appendix A and B, as revised through Amendment No.105, 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
,^.-
Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications t'
Date of Issuance:
Februa ry 17, 1988 i
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t ATTACHMENT TO LICENSE AMENDMENT NO. 105 FACILITY OPERATING LICENSE N0. OPR-29 DOCKET N0. 50-254 Revise the Appendix A 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 marginal lines indicating the area of change.
REMOVE INSERT 3.2/4.2-15 3.2/4.2-15 i
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i QU A9-CITIE S OPR-29 TalLE 3.2 4 POSTACC10 TNT MONITOR!hG INSTR W(NTaTION REQUIREMENTS (2)
Minimam Instrument Numoer of Readout Oper e
en-Location Numoer Paramatar W
Provided R&ngg 1
Reactor pressure 901-5 1
0-1500 psig 2
0 1200 psig 1
Reactor water level 901-3 2
-243 inches +57 inches 1
Torus water temperature 901-21 2
0-200'F 1
Torus air tagerature 901-21 2
0-600'F forus water level 901-3 1
5 inches +5 indicator inches (narrow range) 2(6)
Torus water level 901-1 2
0-30 feet indicator (wide range) forus water level 1
It inch range sight glass (narrow range) 1 forus presture 901-3 1
-5 inenes Hg to 5 psig 2
Drywell pressure 901-3 1
-5 inches Hg to 5 psig
-10 inches Hg te l
70 psig i
2 0 to 250 ps*g 2
Drywell temperature 901-21 6
0-600'F Neutron monitoring 901-5 4
0.1-108 CPS ti43 forus to drywell 2
0-3 psid differential pressure 1(8)
Drywell Hydrogen 901-55, 56 2
0-41 concentration 2(7)
Dryweil radistien 901-55. 56 2
1 to 108 L/hr monitor Main Steam RV posi-901-21 1 per NA tion, acoustic monitor valve g)
Main Steam RV position, 901-21 I per 0-600'F temerature sonttor valve Main Steam $V 0051-901-21 1 per RA ti acoustic monitor valve 5)
Main Steam SV position, 901-21 1 per 8-600'F tagerature monitor valve 1
0732s 3.2/4.2-15 Amen eent me. 105
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NUCLEAR REGULATORY COMMISSION h.
W ASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY 00CKEi N0. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACli.!TY OPERATING LICENSE Amendment No. 101 License No. DPR-30 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated October 16, 1987, 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 (1) 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 ini::iical to the comon defense and security or to the health and safety of the public; and E.
Tne 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 3.8 of Facility Operating License No. DPR-30 is hereby amended to read as follows:
t o
2 B.
Technical Specifications The Technical Specifications contained in Appendix A and B, as revised through Amendment No.101, are hereby incorporated in this license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of f?s issuance.
FOR THE NUCLEAR REGULATORY C ISSION b
Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 17, 1988
t o
ATTACHMENT TO LICENSE AMENDMENT NO. 101
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FACILITY OPERATING LICENSE NO. DPR-30 DOCKET N0. 50-265 i
Revise the Appendix A 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 marginal lines indicating the area of change.
REMOVE INSERT 3.2/4.2-15 3.4/4.2-15 i
1 1
4 T
CU49-C87!(1 a
0*R-20 TA3Lt 3.2 4 P05' ACCIDENT MONITOR!hG In5TRUMthTAT!0N REQUIREMENTS (2)
Min inum Instrument hunter of Readout Oper e
an-Location Nuater 0111 P,,n am tar ugli.L2 Proyised tanga 1
Reactor pressure 902-5 1
0-1500 psig 2
0-1200 osig 1
Reactor water level 902-3 2
-241 inches +57 inches 1
Torus water tapperature 902 21 2
0-200'F 1
Torus air temperature 902-21 2
0-600'F focus water level 902-3 1
-5 inches +5 indicator inches (narrow range) 2(6)
Torus water level 902-3 2
0-30 feet indicator (wide range)
Torus water level 1
la inch range sight glass (narrow rarge) 1 Torus pressure 902-2 1
-5 inches Ng to 5 psig 2
Orywell pressure 902-3 1
-5 inches Hg to 5 psig
-10 inches Hg to 70 psig 2
C to 250 psig 2
Crywell temperature 902-21 6
0-600'T 2
heutron tunitoring 902-5 4
0.1-108 CPS 2(4) forus to crywell 2
0-3 psid differential pressure 1(83 Orywell Hydro 9en 902 55. 56 2
0-41 concentration 2I73 Orywell radiation 9 t..'- 5 5, 5 6 1
1 to 108 t/hr monitor Main State RV post-902-21 1 per NA ti n. acoustic nontto' valve 5)
Main Steam RV position. 902-21 1 per 0-600'F tagerature monitor valve Main Steam SV posi-9J2-21 1 per NA tion, acoustic vanitor valve l
2/ valve (I}
Main Steam SV position. 902 21 1 per 0-660*F temperature monitor valve 07:2s 3.2/4.2 15 amenement no.
101
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