ML20055H825
| ML20055H825 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 07/25/1990 |
| From: | Wechselberger Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20055H826 | List: |
| References | |
| NUDOCS 9007300146 | |
| Download: ML20055H825 (8) | |
Text
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g UNITED STATES
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NUCLEAR REGULATORY COMMISSION -
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j COMMONWEALTH EDISON COMPANY '
DOCKET NO. 50-237 DRESDEF NUCLEAR POWER STATION. UNIT 2
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- AMENDMENT TO PROVISIONAL OPERATING' LICENSE
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Amendment'No.'111 i
License No. DPR-19:
1.
The Nuclear Regulatory Comission'(the Commission) has'found that:.
-A.
The application for amendment by the Comonwealth Edison Company (thelicensee)datedApril18,1990, conplies 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 o>erate in conformity ~with the application, i
the provisions of t.1e Act and the rules-and regulations of the Commission; C.
Thereisreasonsbleassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health i
and safety of the public, and (ii) that such activities;will be conducted-in compliance with the Comission's regulations; l-D.
The issuance of this amendment will not be inimical to the comon l
defense and security or to the health and safety of-the public; and
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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.B. of Provisional Operating License No. DPR-19~is hereby amended to read as follows:
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B.
Technical Specifications 1
The Technical Specifications contained in A>pendix A, as-revised through Amendment No.111,. are here >y incorporated -
in the license.. The licensee shall operate the facility in accordance with the-Technical Specifications, i
3.
This license amendment is effective no later than 60 days from.
the date of its issuance.
FOR E NUCLEAR REGULATORY COMMISSION l
Jacob F. Wechselberger, Acting Director Project. Directorate III Division of Reactor = Projects -'III, IV, V.and Special Projects
/
Office of' Nuclear Reactor Regulation
Attachment:
Changes to the Techi..a1 Specifications Date of Issuance:
July 25, 1990 i
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.l ATTACHMENT TO LICENSE AMENDMENT NO. 111 PROVISIONAL OPERATING-LICENSE NO. -DPR
DOCKET NO. 50-237 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by a
the captioned amendment number and contain marginal lines indicating the -
area of change.
. REMOVE INSERT 1
3/4.1-2 3/4.1-2
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DRESDEN II DPR-19 Amendment No. Ill--
3.1 _ LIMITING CONDITIONS FOR OPERATION 4.1 SURVEILLANCE REQUIREMENTS (Cont'd.)
(Cont'd.)
a.
Maximum fuel design rod block settings limiting ratio for i
shall be reduced-to centerline melt the-values given by.
(FDLRC).
the equations in 6
Specifications 2.1.A.1 i
and 2.1.B.
This may be accomplished by increasing APRM gains as described therein.
j b.
The power distribution b.
Deleted l
shall be changed such that the fuel design limiting ratio-for centerline melt (FDLRC) for any fuel assembly no longer exceeds 1.0.
i 3.
-Two RPS electric' power
~3.
The RPS power monitoring channels for monitoring system each inservice RPS MG set-instrumentation or alternate source.shall shall be be OPERABLE at all times, determined OPERABLE:
a.
By performance of l
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a CHANNEL--FUNCTIONAL TEST each time the unit is in COLD SHVT-DOWN for a period of 1
more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless performed in the previous 6 months.
3/4.1-2
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UNITED STATES
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i COMMONWEALTH' EDISON COMPANY DOCKET NO. 50-249-DRESDEN NUCLEAR POWER STATION, UNIT 3 AMENDMENT-T0 FACILITY OPERATING LICENSE Amendment No. 107-License No. DPR-25 1.
The Nuclear Regulatory Comission (the Commission):has found that:-
0 A.
The a plication for amendment by the Comonwealth Edison C any (the icensee) dated-April 18,>1990, complies with the.sta rds and requirements of the Atomic Energy Act of 1954, as amended' (the-Act), and-the Comission's rules and regulations set forth l
in 10 CFR Chapter I; B.
The facility will oserate in conformity with the application, the provisions of tile Act and.the rules and regulations of:the Commission; C.
There is reasonable assurance (1) that= the. activities authorized by this amendment can be conducted without endangering the'he.lth and: safety of the-public, and-(ii) that such activities will be r
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 Specifi-cations 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:
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l B.
Technical Specifications l
l The Technical. Specifications. contained in Appendix A, as L
revised through Amendment No.' 107, are hereby incorporated 1
l in the license. The. licensee shall operate the fa',ility in accordance with the Technical Specifications.
1 i
3.
This license amendment =is effective no later than 60 dajs from
-the date of'its issuance.
l.
FOR NUCLEAR REGULATORY COMMISSION h.
= Per Jacob F. Wechselberger,; Acting Director
-Project Directorate III-2 i
Division of Reactor Projects - III, IV, V:and Special Projects Office of Nuclear Reactor Regulation.
Attachment:
i Changes to the Technical-Specifications Date of Issuance: July 25,1990 1
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ATTACHMENT TO LICENSE AMENDMENT-NO. 107 FACILITY OPERATING LICENSE'NO. DPR DOCKET NO. 50-249
- Revise the Appendix A Technical Specifications by removing the pages identified I
below and inserting the attached pages.. The. revised pages are identified by-tale captioned amendment-number and contain marginal lines indicating the area of change.
i REMOVE INSERT 3/4.1-2 3/4.1-2 i
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DRESDEN III DPR-25 Amendment No. 107 3.1 LIMITING CONDITIONS FOR OPERATION 4.1 SURVEILLANCE REQUIREMENTS (Cont'd.)
(Cont'd.)
a.
Maximum fuel design-rod block settings limiting ratio for=
shall be reduced to centerline melt the values given by (FDLRC).
j the equations in Specifications 2.1.A.1 l
and 2.1.B.
This may be accomplished by
' increasing APRM gains i
as described therein.
\\
b.,
The power distribution b.
Deleted.
shall be changed such
-i that the fuel design limiting ratio for centerline melt (FDLRC) for any fuel assembly no longer exceeds 1.0, a
3.
Two RPS electric power 3.
The RPS power monitoring channels'for monitoring system j
each inservice RPS MG set instrumentation or alternate source shall
-shall be deter-be OPERABLE at all times.
mined OPERABLE:
a.
By performance of.
a CHANNEL FUNCTIONAL 3
TEST each time the unit is in COLD SHUTDOWN for a.
period of more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless performed in the previous 6 months; i
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3/4.1-2 m
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