ML20077K953
| ML20077K953 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 08/05/1991 |
| From: | Barrett R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077K957 | List: |
| References | |
| NUDOCS 9108090206 | |
| Download: ML20077K953 (2) | |
Text
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/ '! M i f' 1 UNITED STATES NUCLEAR REGULATORY COMMISSION
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COMMONWEALTH EDISON COMPANY DOCKET NO, 50-249 DRESDEN NUCLEAR POWER STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 110 License No. DPR-25 1.
The Nuclear Regulatory Consnission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated March 6, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Coninission's rules and regulations set forth in 10 CFR Chapter );
B.
Tne facility will operate in conformity with the application, the provisions of the Act and the rules and regulations of the Coninission; 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 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-25 is hereby amended to read as follows:
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B.
Technical Specifications The Technical Specifications contained in Appendix A, as Thelicenseeshal$areherebyincorporated revised through Amendmerit Mc.
110 operate the facility in the license.
in accordance with the Technical Specifications.
3.
This license amendment is effective prior to startup from the next refueling outage (Cycle 13).
FOR THE NUCt. EAR REGULATORY COMMISSION (W
Y' Ri hard J. Barret, D rector Project Directorate 111-2 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of 1ssuance:
August 5. 1991 I
ATTACHMENT TO LICENSE AMENDMENT NO.110 FAC:llTY OPERATING LICENSE NO. DPR-25 DOCKET NO. 50-249 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 1/2.1-1 1/2.1-1 6-19 6-19 l
l l
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DRESDEN lll DPR 2$
Amendment No. 110 1,1 SAFETY LIMll 2.1 LIMITING SAFETY SYSTEM SETTING FUEL CLADDING INTEGRITY GELCLADDINGINTEGRITY Applicability:
Applicability:
The Safety Limits established The Limiting Safety System Set-to preserve the fuel _ cladding tings apply to trip settings of integrity apply to these the instruments and devices which variables which monitor the are provided to prevent the fuel fuel thermal behavior.
cladding integrity Safety Limits from being exceeded.
Objective:
Objective:
The objective of the Safety TheobjectiveoftheLimiting Limits is to establish limits Safety System Settings is to define below which the integrity of the level of the process variables the fuel cladding is pre-at which automatic protective
- served, action is initiated to prevent the fuel cladding integrity Safety Limits from being exceeded.
Specifications:
Specifications:
A.
Reactor Pressure greater than A.
Neutron Flux Trip Settings 500 psig and Core Flow greater Than 10'A of Rated.
The limiting safety system trip settings shall be as The existence of a minimum specified below:
critical power ratio (MCPR) l 1ess than 1.08 shall 1.
APRM Flux Scram Trip constitute a violation Setting (Run Mode) of the MCPR fuel cladding integrity safety limit.
When the reactor mode switch is in the run When in Single Loop Operation, position, the APRM the MCPR safety limit shall be flux scram setting increased by 0.01.
shall be:
S less than or equal to(.58Wn + 62) during Dual Loop Operation or S less than cr equal to[.58Wn + 58.5) dur-ing SingTe Loop Opera-tion with a maximum setpoint of 120% for coreflgwequalto 98 x 10 lb/hr and greater, where:
1 S - setting in percent of rated thermal power.
1/2.1-1
OtESDEN !!!
OPR-f.5 Amandment No. 110 6.0 ADMINISTRATIVEf0NTROLS (Cont'd.)
- 3) The Local Steady State Linear Heat Goeration Ra'.e (LHGR) for Specification 3.5.J.
- 5) The Minimum Critical Power Operating L bit for Specification 3.5.L.
This includes rated and o.'f-rated flow conditions.
b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in the latest approved revision or su)plement of tt.e topical reports describing the methodology.
- or Dresden Unit 3, the topical reports are:
- 1) ANF-1125(P)(A), " Critical Power Correlation - ANFB."
- 2) ANF-524(P)(A), Reactors.""ANF Critical Power Methodology for Boiling Water
- 3) XN-NF-79-71(P)(A),"ExxonNuclearPlantTransient Methodology for Boiling Water Reactors."
- 4) XN-NF-80-19(P)(A),"ExxonNuclearMethodologyfor Boiling Water Reactors."
s
- 5) XNNF-85-67(P)(A),"GenericMechanicalDesignfor Exxon Nuclear Jet Pump Boiling Water Reactors Reload fuel."
- 6) XN-NF-81-22(P)(A), " Generic Statistical Uncertainty Analysis Methodology."
ANF-913(P)(A),"COTRANSA2:
A Computer Pro 7)
Boiling Water Reactor Transient Analyses." gram for c.
The core operating limits shall be determined so that allapplicablelimits(e.g.liclimits,ECCSlimits, fuel thermal-mechanical limits, core thermal-hydrau nuclear limits such as shutdown margin, and transient l
-and accident _ analysis limits) of the safety analysis are met.
d.
The Core Operating Limits Report, including any mid-cycle l
revisions or supplements thereto, shall be provided upon issuance to the NRC Document Control Desk with copies to l
the Regional Administrator and Resident Inspector.
B.
Reportable Events Reportable events will be submitted as rcquired by 10 CFR 50.73.
6-19 l.
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