ML19224D449
| ML19224D449 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/06/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19224D450 | List: |
| References | |
| NUDOCS 7907120190 | |
| Download: ML19224D449 (8) | |
Text
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UNITED STATES r
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,OS NUCLEAR REGULATORY COMMISSION
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W ASHINGTON, D. C. 20555 3 ?.
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%..m. / y PHILADELPHIA ELECTPIC COMPANY PUBLIC SERV!CL ELECTRIC ANO GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATL ANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTCM ATCHIC P0'.iER STATION, UNIT NO. 2 ANENDMENT TO FACILITY CPERATING LICENSE Amendment No. 54 License No. OPR-44 1.
The Nuclear Regulatory Cennission ( the Commission) has found that:
A.
The application for am ndment by Philadelphia Electric Company, et al., (the licensee) dated April 30, 1979, complies with the staridards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules ard ragulations set forth in 10 CFR Chapter I; B.
The f 3cility eiii coerate in confamity with the application, the provisions of the Act, and the rules and regulations of the Connission; C.
There is reasonaole assurance (1) that the ac tivities authorized by thi s amendment can De conduc ted wi thcut endangering the heal th and safety of the public, and (ii) that such activities will be condu.:ted in compliance with the Conmission's regulations; D.
The issuance of tni s amendment will not be inimical to the common defense 3r.d security or to the health and safety of the puDlic; and E.
The i ssuance of tni s amendment i s in accordance with 10 CFR Part 51 of the Corni ssion's regul ations and all appl icabl e requi remen ts have been sati sfied.
790712019o 3'6 E'l.
2 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-44 is hereby amended to read as follows:
(2) Technical Specificatiors The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
lhis license amendment is effec cive as of the v.3te of its i",suance.
FOR THE NUCLEAR REGULATORY CGriMISSION d' ' L 4..
Thomag('. Ippolito, Chief Coerating Reactors Branch #3' Division of Operating Reactors Attachnent:
Changes to the Technical Specifications Oate of Issuance:
June 6,1979 326 327
ATTACilMI.fil 10 LICENSE AMENDMErlT f40. 54
_ FACILITY OPERATING LICENSL_fl0. DPR-44 DOCKET fi0. 50-277 Replace the following page of the Appendix A Technical Specificatio'is with tne enclosed page.
The revistd page is identified by Amendment number and contains vertical lines indic<iting the area of change.
Remove Insert 6
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PBAPS 1.0 DEFINITIONS (Cont 'd )
1.
At least one door in each access opening is closed.
2.
The standby gas treatment system is operable.
3.
All Reactor Building ventilation system automatic isolation valves are operable or deactivated in the isolation pocition.
Shutdown - The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed.
Shutdown Mode - Placing the mode switch to the shutdown position initiates a reactor scram and power to the control rod drives is removed.
After a short time period (about 10 sec), the scram signal is removed allowing a scram reset and restoring the normal valve lineup in the control rod drive hydraulic system; also, the main steam line isolation scram and ma i n condenser low vacuum scram are by p a s s e d if reactor vessel pressure is be low 1055 psig.
Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit in question.
Startul/ Hot Standbv Mode - In this mode the reactor protection scram trips, initiated by condenser low vacuum and main steam line isolation valve closure, are bypassed when reactor pressure is less than 1055 psig, the reactor protection system is energized with IRM neutron monitoring system trip, the A?RM 15%
h i p,h flux trip, and control rod withdrawal interlocks in service.
This is often referred to as just Startur Mode.
This i= intended to imply the Startup/ Hot Standby pasition of the mode switch.
Surveillance Frequency - Periodic surveillance tests, checks, calibrations, and examinations shall be per orned within the specified surveillance inter-c The operating cycle interval as pertaining to instrument and electrical vals.
surveillance shall not exceed 18 months.
These specified time intervals may be exceeded by 25?
In cases where the elapsed interval has exceeded 100"l of the speci fied interval, the next surveillance irterval shall commence at the end of the original specified interval.
Surveil.ance tests are not required on systems or parts of the ;ystems that are not required to be operable or are tripped.
If tm ts are missed on parts not required to be Amendment flo. JE, #, 54 3 (((
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/pa atcgb UNITED ST ATES g
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,'S NUCLE AR REGULATORY COMMISSION 3,I
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W ASHING TON, D. C. 20555 h4 8
gm*....f PHILADELPHIA ELECTRIC C0FPANY PUBLIC 5ERVILE ELECTR'C AND GAS COMPANI DELMAPV A 00nER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DCCKET NO. 50-2 78 PEACH "0TT?d ATOMIC POWER STATION, UNIT NO. 3 AMENDPENT TO FACILITY OPERATING LICENSE Amendment No. 54 License ha. DPR-56 1.
The Nuclear Regulatory Cconi ssion ( the Conmission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al, (the licensee) dated April 30, 1979, com-plies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Concissiori's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will ocerate in conformity with the application, the provisions of Ine a t, and tne rules and regulations of c
the Commission; C.
There is reasonable issurance (i) tnat tre activities authorized by thi s amendment can De conduc ted wi thout endangering the health and safety of the cuDlic, and (ii) that such activities will be conducted in ccmpliance wi th the Commission's regulations; D.
The issuance of tnis amendment will not be ininical to the common defense and security or to tne nealth and safety of the public; and E.
The issuance of thi s amencment is in accorcance wi th 10 CFR 03rt 51 of tne :cnai ssion's regulations and all applicaole requirenents have Deen sa ti ;f i ed.
326 330
+
. 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:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54, are hereby incorporated in the license.
The licensee shall operate the facility ir, accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAP. REGULATORY COMMISSION
/
e fas t T omas A/ Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: June 6, i979
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ATTACHMENT TO LICENSE AM'NDMENT N0 51 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following page of the Appendix A Technical Specifications with the enciased page.
The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
Remove Insert 6
6 w
g,
PBAPS 1.0 DEFINITIONS (Cont'd) 1.
At least one door in each access opening is closed.
2.
The standby gas treatment system is operable.
3.
All Reactor Building ventilation system automatic isolation vi!ves are operable or deactivated in the isolation position.
Shutdown - The reactor is in a shutdown condition wnen the reactor mode switch is in the shutdown mode position and no core alterations are being performed.
_ Shutdown Mode - Placing the mode switch to the shutdown position initiates a reactor scram and power to the control rod drives is removed.
After a short time period (about 10 sec), the scram signal is removed allowing a scram reset and restoring the normal valve lineup in the control rod drive hydraulic system; also, the main steam line isolation scram and main condenser low vacuun scram a re bypassed if reactor vessel pressure is be low 1055 psig.
Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit in question.
Startup/ Hot Standby Mode _ - In this mode the reactor protection scram trips, initiated by condenser low vacuum and ma i n steam line isolation valve closure, are bypassea when reactor pressure is less than 1055 psig, the reactor protection system is energized with IRM neutron monitoring system trip, the APRM 15%
hidh flux trip, and control rod withdrawal interlocks in service.
This is often referred to as just Startup Mode.
This is intended to imply the S t a r t u r./ H o t Standby position of the mode switch.
Surveillance Frequency - Periodic surveillance tests, checks, calibrations, and examinations shall be performed within the specified surveillance inter-vals.
The operating cycle interval as pertaining to instrument and electrical surveillance shall not exceed 18 months.
These specified time intervals may be exceeded by 25%.
In cases where the elapsed interval has exceeded 100% of the specified interval, the next surveillance interval shall commence at the end of the original specified interval.
Surveillance tests are not required on systems or parts of the systems that are not required to be operable or are tripped.
If tests are missed on parts not required to be 9'
7-Amendment No. L5, U, S4 D: LU Ja,