ML19347E947
| ML19347E947 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 04/24/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19347E948 | List: |
| References | |
| NUDOCS 8105140395 | |
| Download: ML19347E947 (4) | |
Text
-_ ______-__
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o UNITED STATES b
E' NUCLEAR REGULATORY COMMISSION
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.E WASHINGTON D. C. 20$55
....f COMMONWEALTH EDISON COMPANY _
AND IOWA-ILLINOIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. DPR-29
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1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated May 22, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regu-lations 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 Comission'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 Specifi-cations 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:
3.8 Technical Scecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 69. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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j 3.
This license amendment is effective as of the date of its is'suance.
F FOR THE NUCLEAR REGULATORY COMMISSION tr 4
polito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 24,1981 5
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ATTACHMENT TO LICENSE AMENDMENT NO. 69
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FACILITY OPERATING LICENSE NO. DPR-29 DOCKET NO. 50-254 Revise the Appendix "A" Technical Specifications as follows:
Remove Replace 3.7/4.7-21 3.7/4.7-21 n
a 3
f 4
-QUAD-CITIES 0
P00R ORIG NAL TA8LE 3.7-1 (Cont'd)
Valve senter et Matkaan Member sur Peeer-Sparstlag 1:ormal Lett::s as Isotaties Inits Operated Yafves Thee Operatbg init:.w troup vatie identtreaties Isad2 Intars Outboard bec) realthe signal andvesse 2
Orywes Soor dran decharg'e A0-20013 I
s 20 0
GC 2
Drywen Scar dran dsenarse A0-2001-4 1
s 20 0
GC 2
Drywel equernent dran dscharge A0-2001 15 1
s 20 0
GC 2
DryweR em;: ment dran dscharge A0-2001-16 1
s 20 0
GC com va, can te i e
efter moiatan Ier sometag) h7:ee Aan'frer 2
Orygen anatyrer valve A0-8301 A, 4
4 s 10 0
GC 8.C.D
~
2 Oryten anayzer vahe A0-8802 A.
4 s 10 0
GC 8,C,0 2
Oryten anayzer vane A0-8803A 1
s 10 0
GC 2
Orygen anayzer vane A0-88038 1
sID 0
GC 1 ravening lacers Prene 2
On achten scal, the TF detector TF Bal
' wP.hdrawn d b use: Sve bal Vake s
wakes aa.1 ene artregen purge are 700-733 i
cbsed.
ilP Purge Vake Assemtty 700-743 B6 actor Water Cleanup 3
Pump sucton souton va!ve MO-12012 I
s 30 0
GC 3
Pump sucton sou:en vake MO-1201-5 1
s 30 0
GC urci 4
Steam schtion vane MO-23014 1
s 50 0
GC 4
Steam souton vane MO-23015 1
s 50 0
GC aCr 5
Turbne stem supply MO-1301 16 1
s 25 0
GC 5
Turtne steam suppty MO 130117 1
s 25 0
GC Amendment No. 69 3.7/4.7 21
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UNITED STATES
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- ,h NUCLEAR REGULATORY COMMISSION
.p WASHINGTON. D. C. 20656 o,
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COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS AND ELECTRIC COMPANY _
DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 63 License No. DPR-30 1.
The Nuclear Regulaiory~Comission (the Comission) has found that:
A.
The applications for amendment by the Commonwealth Edison Company (the licensee) dated May 22, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regu-lations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the applications, 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 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 Specifi-cations 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-1 3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 63, 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 i? /-
Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 24, 1981
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ATTACHMENT TO LICENSE AMENDMENT NO. 63 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50- 265 Revise the Appendix "A" Technical Specifications as follows:
Remove Replace 3.7/4.7-21 3.7/4.7-21 4
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, QUAD-CITIES DPR-30 TABLE 3.71 (Cont'd)
Vahe numer of Maximum namest ter Pseer-Operating ustmal Actise as heisties tests Operated Valvas Thes Opsraths isttatsg stamp vano ussiensaties 1 and 2 lanaard cuttnert bec)
Posities sissai tassee 2
Orywet scar drain discharg'e A0-2001-3 1
s 20 0
GC 2
Orywel Soor dram decnarge A0-2001-4 1
s 20 0
GC 2
Orywel equernent drasi dacharge A0-2001-15 1
s 20 0
GC 2
Drywes egaprnent dras dscharge A0-2001-16 1
s 20 0
GC com vaan cm ne w ener m.mma in ennp aryses anstyrer 7
Orygen anaWe valve A0-8801 A, 4
5 s 10 0
GO 8,C,0 t
2 Orygen anaWe vake A0-8802-A, 4
slo O
GC 8,C,0 2
Orygen anaWer vane A0-8803A 1
s 10 0
GC 2
Orygen anaWer valve A0-88038 1
s 10 0
GC i,svarWag isesre Prets 2
On isolation signal, the TIP detector TlP BaR
' wrthdrawn d ' use: Sve bal Valve s
n valves and one nitrogen purge are 700-733 closed.
TIP Purge Valve Asserrth 700 743 toester water ossnes 3
Pung section ischten valve M0-12012 1
s 30 0
GC 3
Pump sucton ischtion valve E 1201 5 1
s30 0
GC urt!
4 Steam ischtien vane MO-2301-4 1
s 50 0
GC 4
Steam ischtion valve MO-23015 1
s 50 0
GC act MO-1301 16 1
s 25 0
GC 5
Twbme steam suppy M0-1301 17 1
s 25 0
GC 5
Turtne steam suppy 3
.