ML20135F857

Amend 114 to License DPR-56,revising Tech Specs to Permit Reactor Operation W/Reload 6 (Cycle 7)

ML20135F857
Person / Time
Site:	Peach Bottom
Issue date:	08/23/1985
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Atlantic City Electric Co, Delmarva Power & Light Co, Philadelphia Electric Co, Public Service Electric & Gas Co
Shared Package
ML20135F859	List: ML20135F857 ML20135F861
References
DPR-56-A-114 NUDOCS 8509170448
Download: ML20135F857 (9)

Text

{{#Wiki_filter:. ) [ I'o UNITED STATES NUCLEAR REGULATORY COMMISSION o E WASHINGTON, D. C. 20555 %,...../ PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.114 License No. DPR-56 1. The Nuclear Regulatory Comission (the Comission) has found that: A. The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated January 7,1985, as amended by letter dated April 1, 1985, 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 2.C.(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows: h h P

2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.114, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications. 3. This license amendment is effective as of its date of issuance. I R THE NUCLEAR REGULATORY COMMISSION f, ,7 { { Jo h. Stolz, Chief erating Reactors Branch #4 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: August 23, 1985 l 4 e ,,-,--..,,.r --w-

ATTACHMENT TO LICENSE AMENDMENT NO. 114 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change. Remove Insert iv iv 133d 133d 133e 133e 142 142 142a 142a 142e 142h 142h 1421 1421 t i - -,, =.. m-,---._-. =-- ~

PBAPS UNIT 3 LIST OF FIGURES Figure Title Page 1.1-1 APRM Flow Blas Scram Relationship To Normal 16 Operating conditions 4.1.1 Instrument Test Interval Determination Curves 55 j 4.2.2 Probability of System Unavailability vs. Test 98 Interval 3.4.1 Required Volume and Concentration of 122 Standby Liquid Control System Solution 3.4.2 Required Temperature vs. Concentration for 123 Standby Liquid Control System Solution 3.5.K.1 MCPR Operating Limit vs. Tau, LTA 142 3.5.K.2 MCPR Operating Limit vs. Tau, BP/P8X8R Fuel 142a 3.5.1.A DELETED 3.5.1.B DELETED 3.5.1.C DELETED 3.5.1.D DELETED 3.5.1.E Kf Factor vs. Core Flow 142d 3.5.1.F DELETED l 3.5.1.G DELETED 3.5.1.H MAPLUGR vs. Planar Average Exposure, Unit 3 1429 P8X8R Fuel (P8DRB284H) 3.5.1.I MAPLHGR vs. Planar Average Exposure, Unit 3 142h P8X8R and BP8X8R Fuel (P8DRB299 and BP8DRB299) 3.5.1.J MAPLHGR vs. Planar Average Exposure, Unit 3 1421 BP8X8R Fuel (BP8DRB299H) 3.5.1.K MAPLHGR vs. Planar Average Exposure, Unit 3 142j P8X8Q LTA (P8DQB326) 3.6.1 Minimum Temperature for Pressure Tests 164 such as required by Section XI l 3.6.2 Minimum Temperature for Mechanical Heatup or 164a Cooldown following Nuclear Shutdown 3.6.3 Minimum Temperature for core Operation 164b (Criticality) 3.6.4 Transition Temperature Shift vs. Fluence 164c 3.6.5 Thermal Power Limits of Specifications 164d

3. 6.F. 3, 3. 6.F. 4, 3. 6.F. 5, 3. 6.F. 6 and 3. 6.F. 7 3.8.1 Site Boundary and Effluent Release Points 216e i

6.2-1 Management Organization Chart 244 6.2-2 Organization for Conduct of Plant Operation 245 i -iv-i Amendment No. 74, #7, 6, $$, 52,77, l

97. JSA,197 114

PBAPS UNIT 3 TABLE 3.5.K.2 OPERATING LIMIT MCPR VALUES FOR VARIOUS CORE EXPOSURES

• I I

MCPR Operating Limit Fuel Type For Incremental Cycle Core Average Exposure ** BOC to 2000 MWD /t 2000 MWD /t before EOC Before EOC To EOC BP/P8X8R l'*27 1.28 LTA 1.27 1.28 If requirement 4.5.K.2.a is met. These values shall be increased by 0.01 for single loop operation. -133d-Amendment No. #7, #1, //, 7), SE, 77, 797. 114

=. _ PBAPS UNIT 3 TABLE 3.5.K.3 OPERATING LIMIT MCPR VALUES FOR VARIOUS CORE EXPOSURES

• MCPR Operating Limit 4

Fuel Type For Incremental Cycle Core Average Exposure ** BOC to 2000 MWD /t 2000 MWD /t before EOC Before EOC To EOC BP/P8X8R l'.'3 3 1.40 LTA 1.33 1.40 1 1 I If surveillance requirement 4.5.K.2 is not performed. These values shall be increased by 0.01 for single loop operation. -133e-Amendment flo. 77,85,92,197,114 -n =-n,, , - ~,. ., = - -

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