ML19343B548
| ML19343B548 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/10/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19343B549 | List: |
| References | |
| NUDOCS 8012240202 | |
| Download: ML19343B548 (7) | |
Text
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UNITED STATES l' ; s q ?,j NUCLEAR REGULATORY COfIMlSSION
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PHILADELPHIA ELECTRIC Ct1MPANY PUBLIC SERVICE 2LECTRIC AND GTJMPANY D_ELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DCCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 License No. OPR-44 1.
The Nuclear Regulatory Comission (the Commission) has found that; A-The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated September 30, 1980, 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 confamity with the application, the provisions of the Act, and the rules and regulations of the Ccmmission; 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.
I 2.
Accordingly, the license is amended by changes to the Technical Spec-1 ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No..DPR-44 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 76, are hereby incorporated in the license.
PEC0 shall operate the facility in ~
accordance with the Technical Specifications.
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1 ATTACHMENT T0 LICENSE AMEfGENT NO. 76 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 1
l Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOLIREMENTS 3.1 REACTOR PROTECTION SYSTEM 4.1 REACTOR PROTECTION SYSTEM Applicability:
Applicability:
Applies to the instrumentation and Applies to the surveillance associated devices which initiate of the instrucentation and a reactor scram.
associated devices which initiate reactor scram.
Objective Objective To assure the operability To specify the type and of the reactor protection frequency of surveillance system.
to be applied to the protection instrumentation.
Specification:
Specification:
A. When there is fuel in the vessel A.
Instrumentation syste=s the setpoint, minimum number shall be functionally of trip systems, and minimum tested and calibrated number of instrument channels as indicated in Tables that must be operable for 4.1.1 and 4.1.2 each position of the reactor respectively.
mode switch shall be as given in Table 3.1.1.
B.
The designed system response B.
Daily, during reactor power times from the opening of the operation, the maximum fraction sensor contact up to and of limiting power density including the opening of the shall be checked and the l
trip actuator contacts shall scram and APRM rod block not exceed 50 millisecondc.
settings given by equations I
Otherwise, the affected trip in Specification 2.1.A.1 system shall be placed in and 2.1.B shall be e,ticu-the tripped condition, or laced if the maximum the action listed in Table fraction of the limiting 3.1.1 for the specific trip power density exceeds the function shall be taken.
fraction of rated power.
AmendmentNo.J8,pY,g,76 35
o PBAPS UNIT 2 TASLZ 3.5-2 OPERATING LIMIT MCPR VALUES AS DETERMINED FOR VARIOUS CORE EXPOSURES MCPR Operating Limit Fuel Type For Incremental Cycle 5 Core Average Exposure BOC to 1000 MWD /t 1000 MWD /t Before EOC Cefore EOC to EOC 8X8 1.28 1.28 BXSR & LTA 1.28 1.28 P8X8R 1.30 1.30 i
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Amendment.No. g 76
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PHILADELPHIA ELECTRIC COMPAW PUBLIC SERVICE ELECTRIC AND GA5 CO WANY l
DELMARVA P0hER AND LIGHT COMPANY
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ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 l
PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 1
l AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 75 License No. DPR.56 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A-The application for anendment by Philadelphia Electric Conpany, et al. (the licensee) dated Septerter 30. 1980, complies with the standards and requirements of the Atomic Energy Act or 1954, as ance.ded (the Act),
and the Comission's rules and regulations set forth in 10 CFB Chapter It B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Ccemission; 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 activicies 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 Comission's regulations and all applicable requirements have been satisfied.
l 2.
Accordingly, the license is amended by changes to the Technical Spec-l ifications as indicated in the attachment to this license amendment /
and paragraph 2.C.(2) of Facility Operating License No. DPR-56 is l
hereby amended to re:d as follows:
I l
l (2) Technical Soecifications s
The Technical Specifications contained in Apoendices A and B, as revised through Amendment No. 75, are hereby incorporated in the license. PsCO's' hall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 5'Y.
s Robert W. Reid, Chief l
Operating Reactors Branch #4 Division of Licensing i
attachment:
Changes to the Technical Specifications Date of Issuance: Dccember 10, 1980 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 7s FACILITY OPERATING LICENSE N0. DPR-56 DOCKET NO. 50-278 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by amendment number and contains a vertical line indicating the area of change.
Remove Page Insert Page 35 35 l
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PBAPS LIMITINC CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
- 3. 1 REACTOR PROTICTION SYSTEM 4.1 REACTOR PROTECTION SYSTEM Applicability:
Applicability:
Applies to the instru=entation and Applies to the surveillance associated devices which initiate of the instrumentation and i
e reactor scra=.
associated devices which
)
icitiate reactor scra=.
Objective Objective To assure the operability To specify the type and of the reactor p ctecticn frequency of surveillance syste=.
to be applied to the protection instru=entation.
Specification:
Specification:
A.
When there is fuel in the vessel A.
Instrumentation syste=s the setpoint, =ini=u nu=ber s ha ll be functionally of trip systems, and =ini=u=
tested and calibrated nu=ber of instru=ent channels as indicated in Tables that =ust be operable for 4.1.1 and 4.1.2 each position of the reactor respectively.
^
= ode switch shall be as given in Table 3.1.1.
3.
The designed syste: response L.
Daily, during reactor power ti=es fro = the opening of the operation, the maxi =u= fraction sensor contact up to and of limiting power density including the opening of the shall be checked and the trip actuator contacts shall scra= and APRM rod block not exceed 50 =il11 seconds.
settings given by equations Otherwise, the affected trip in Specification 2.1.A.".
syste= shall be placed in and 2.1.B shall be calcu-the tripped condition, or lated if the =axi=u=
the action listed in Table fraction of the limiting 3.1.1 for the specific trip power density exceeds the function shall be taken.
fraction of rated power.
Amendment No g, M 75-. - -,
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