ML20023C784

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Amend 92 to License DPR-56,permitting Reactor Operation W/Reload 5 Core During Cycle 6
ML20023C784
Person / Time
Site: Peach Bottom Constellation icon.png
Issue date: 05/04/1983
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
ML20023C785 List:
References
DPR-56-A-092 NUDOCS 8305180008
Download: ML20023C784 (12)
v • d • e


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  1. o UNITED STATES

'g 8 NUCLEAR REGULATORY COMMISSION o ,{ ..,I wasHusarow, n. c.acess j/ PHILADELPHIA ELECTRIC COWANY PUBLIC SERVICE ELECTRIC AND GA5 CO W ANY DELMARVA POWER AND LIGHT COWANY ATLANTIC CITY ELEGIRIC CONANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3- ~ AENDMENT'TO FACILITY OPERATING LICENSE Amendment No. 92 License No. DPR-56 1. The Nuclear Regulatory Comission (the Commission) has found that: A. The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated December 30, 1982, as supplemented April 6,1983, complies with the standards and requirements of the Atomic. Energy Act of 1954, as amended (the Act),.and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facil'ity will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commissiori; l 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 i The issuance of this amendment is in accordance with 10 CFR Part E. 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated'ir the attachment to this license amendment and paragraph 2.c.(2) of Faci-lity Operating License No. DPR-56 is hereby amended to read as follows: i (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 92, are hereby incorporated in the license. The licensee shall operate the 'acility in accordance with the Technical Specifications. 8305180008 830504 PDR ADOCK 05000278 P PDR .s i.

2-3. This license amendment is effective as of the date of its issuance. FOR THE NUCLEAR REGULATORY Co m ISSION D, n \\ 'fr[lll ,Y / JoHif F. Stolz, Chief 1 ( Op4 rating Reactors Branch No. 4 ' Division of Licensing

Attachment:

Changes to the Yechnical Specifications Date of Issuance: May 4,1983 ~; ~

A_TTACHMENT TO LICENSE AMENDMENT NO. 92_ FACILITY OPERATING LICENSE NO. DPR-5), 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 i.' number and contain vertical lines indicating the area of change. Remove Pages Insert Pages

(

iv iv 119 119 133a 133a ' ~ 133d-133d 133e 133e

142,

-142 142a 142a 142b 142c 142e 142e 142f 142j 241 241 g )

j Unit 3 l PBAPS LIST OF FIGURES Figure Title Page 1.1-1 APRM Flow Bias Scram Relationship To 16 Normal Operating Conditions 4.1.1 Instrument Test Interval Determination 55 Curves 4.2.2 Probability of System Unavailability 98 vs. Test Interval 3.4.1 Required Volume and Concentration of 122 Standby Liquid control System Solution 3.4.2 Required Temperature vs. Concentration 123 for 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, PTA & P8X8R 142a Fuel 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 MAPLEGR vs. Planar Average Exposure, 142e Unit 3, 8X8 PTA Fuel 3.5.1.G Deleted 3.5.1.H MAPLEGR vs. Planar Average Exposure, 142g Unit 3, P8X8R Fuel (P8DRB2845) 3.5.1.I MAPLEGR vs. Planar Average Exposure, 142h Unit 3, P8X8R Fuel (P8DRB299) l 3.5.1.J MAPLHGR vs. Planar Average Exposure, 1421 Unit 3, P8X8R Fuel (Generic) 3.5.1.K MAPLHGR vs. Planar Average Exposure, 142j Unit 3, P8X8Q LTA (P8DQB326) 3.6.1 Minimum Temperature for Pressure Tests 164 such as required by Section XI 3.6.2 Minimum Temperature for Mechanical Heatup 164a or Cooldown following Nuclear Shutdown 3.6.3 Minimum Temperature for Core operation 164b (Criticality) 3.6.4 Transition Temperature Shift vs. Pluence 164c 6.2-1 Management Organization Chart 244 6.2-2 Organization for Conduct of Plant Operation 245 l l -iv-l Amendment No. JA, 41, 45, 46, 52, 79, 92 .--..,,k-----, .~-,.,.,...-..----.,.----,a... -.., -,,. - ~. J.

l PBAPS I, 3'.4 BASES STANDBY LIQUID CONTROL SYSTEM i. A. The conditions under uhich the Standby Liquid Control System must provide shutdown capability are identified via the Plant Nuclear Safety Operational Analysis (Appendix G). If no more than one operable control rod is withdrawn, the basic shutdown reactivity requirement for the core is satisfied and the Standby Liquid Control System is not required. Thus, the basic reactivity requirement for the core is'the primary determinant of when the liquid control system is required. The purpose of the liquid control system is to provide the capability of bringing the reactor from full power to a cold, xenon-free shutdown condition assuming that none of the withdrawn control rods can be inserted. -To meet this objective, the liquid control system is designed to inject.a quantity of boron that produces a concentration of 660 ppm of boron in the reactor core in less than 125 minutes. The 660 ppm concentration in the reactor core will bring the reactor 1 from full power to a subcritical condition, considering the hot to cold reactivity difference,, xenon poisoning, etc. The time requirement for inserting the boron solution was selected to' override the rate of reactivity insertion caused by cooldown of the reactor following the xenon poison peak. The minimum limitation on the relief valve setting is intended to prevent the recycling of liquid control solution via the lifting of a relief valve at too low a pressure. The upper limit on the relief valve setting provides system protection from overpressure. B. Only one of the two standby liquid control pumping loops is needed for operating the system. One inoperable pumping cuit does not immediately threaten shutdown capability, ( and reactor operation can continue wVile the circuit is being repaired. Assurance that the rer'in't.g system will perform its intended function and that ?h long rerm average availability of the syste's is n 4 6 ficed is obtained for a .one out of two system by an aitowaune equipment out of service time of one third of the normal surveillance. frequency. This method determines an equipment out of service time of ten days. Additional conservatism is introduced by reducing the allowable out of service time to seven days, and by increased testing of the operable redundant component. -119-Amendment No. 33, 62, 92 e -..D a.------ ,r T u-

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PBAPS Unit 3 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.I Average Planar LHGR 4.5.I Average Planar LHGR During power operation, the APLHGR The APLHGR for each type of fuel for each type of fuel as a function as a function of average planar of average planar exposure shall not exposure shall be checked daily exceed the limiting value shown in during reactor operation at the applicable figures during two >254 rated thermal power / recirculation loop operation. 3 During single loop operation, the j , APLHGR for each fuel type shall not exceed the above~ values multiplied by the following reduction factors: 0.71 for 7X7 fuel;.0.83 for 8X8 fuel; 0.81 for PTA, 8X8R, P8X8R, and LTA fuel. If at any time during opera-tion it is determined by normal sur-veillance that the limiting value of APLHGR is being exceeded, action shall be initiated within one (1) hour to restore APLEGR to within pre-scribed limits. If the APLNGR is not returned to within prescribed limits within five (5) hours reactor power shall b'e decreased at a rate which would bring the reactor to the cold shutdown condition within 36 hours unless APLEGR is returned to within limits during this period.' Surveill-ance and corresponding action shall continue until reactor operation is within the prescribed limits. 3.5.J Local LEGR 4.5.J Local LHGR During power operation, the linear The LHGR as a function of core heat generation rate (LEGR) of any height shall be checked daily-rod in any fuel assembly at any during reactor operation at axial location shall not exceed >254 rated thermal power. design LHGR. LHGR < LEGRd LHGRd = Design LHGR 13.4 kW/ft for all 8X8 fuel -133a-Amendment No. 33, A7, $2, 77, 73, 92 l* =

PBAPS Unit 3 Table 3.5.K.2 OPERATING LIMIT MCPR VALUES FOR VARIOUS CORE EXPOSURES * \\ MCPR Operating Limit Fuel Type For Incremental Cycle Core Average Exposure ** BOC to 2000 MWD /t 2000 MWD /t before EOC Before EOC To BOC PTA EP 8X83 1.26 1.27 LTA 1.26 1.28 If requirement 4.5.K.2.a is set. These values shall be increased by 0.01 for single loop operation. f I -133d-I Amendment No. 42, 62, 77, 79, 85, 92 e O 9 w"' 6 %O O

l P!APS Unit 3 Table 3.5.K.3 OPERATING LIMIT MCPR' VALUES FOR VARIOUS CORE EXPOSURES

  • 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 PTA EP 8X8R 1.33 1.39 LTA 1.33 1.40 .. ~ If surveillance requirement of section 4.5.K.2 is not performed. These values shall be increased by 0.01 for single loop operation. -133e-Amendment No. 79, 85, 92 S

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unit a PBAPS 5.0 MAJOR DESIGN FEATURES 5.1 SITE FEATURES The site is located partly in Peach Botton Township, York County, partly in Drumore Township, Lancaster County, and partly in Fulton Township, Lancaster County, in southeastern Pennsylvania on the westerly shore of Conowingo Pond at the mouth of Rock Run Creek. It is about 38 miles north-northeast of Baltimore, Maryland, and 63 miles west-southwest of Philadelphia, Pennsylvania. Figures 2.2.1 through 2.2.4 of the FSAR show the site location with respect to surrounding communities. 5.2 REACTOR A. The core shill consist of not more than 764 fuel assemblies. B. One Pressurized Test Assembly and four Le'ad Test Assemblies may be inse,rted in the core. C. The reactor core shall contain 185 cruciform-shaped control rods. 5.3 REACTOR VESSEL

  • The reactor vessel shall be as described in Table 4.2.2 of the FSAR.

The applicable design codes shall be as described in Table 4.2.1 of the FSAR. 5.4 CONTAINMENT A. The principal design parameters for the primary containment shall be as given in Table 5.2.1 of the FSAR. The applicable design codes shall be as described in Appendix M of the FSAR. B. The secondary containment shall be as described in Section l 5.3 of the FSAR. C. Penetrations to the primary containment and piping passing through such penetrations shall be designed in accordance with standards set forth in Section 5.2.3.4 of the FSAR. 1 -2 41-- Amendment No. 33, AJ, $2. 79,92 W ..e-v , - _ _ _ _ _ _ _ _ _ _ _}}

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