ML20100F809
| ML20100F809 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/14/1984 |
| 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 | |
| ML20100F812 | List: |
| References | |
| DPR-56-A-106 NUDOCS 8412070043 | |
| Download: ML20100F809 (7) | |
Text
_ _ _ _ _ _ _ _ _ - _ _ _ _ _ _.
pn ng UNITED STATES y,.
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g NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555 g
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,o PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA P0h!ER 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.106 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 September 28, 1984, 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 (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 Comission'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.
2.
Accordingly, the license is amended by changes to the TechnicP 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:
1 8412070043 841114 FDR ADOCK 05000278 p
2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Arnendment No.106, are hereby incorporated in the license. PEC0 shall operate the facility in accordance with the Technical Specifications.
3.
This license' amendment is effective as of its date of issuance.
FOR THE NUC K REGU A10RY COMMISSION
(
Joh r F. Stolz, Chief.
O rating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 14, 1984 i
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.,iat-ATTACPPENT TO LICENSE AMENDMENT NO.106 FACILITY OPERATING LICENSE N0. DPR-56 DOCKET NO. 50-778 Replace the following pages of the Appendix "A" Technical Specifications i
with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
Remove Insert 38 38 40 40 61 61 53 63 i
1 1
R Table 3.1.1 (Con t ' d)
E REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT 3
Minimum No.
.~
Modes in which Number of 5
of Operable Function Must be Instrument Instrument Trip Level Operable Channels Action j
Channels Trip Function Setting Provided (1) per Trip Refuel Startup Run by Desgin System (1)
(7)
+
es 2
High Water Level in Scram Discharge
-<50 Gallons X(2)
X X
4 Instrument A
Channels Volume 2
Turbine Condenser
>23 in. Hg.
X(3)
X (3)
X 4 Instrument A or C Low Vacuum Vacuum Channels d,
<3 X Normal Full X
X X(14) 4 Instrument A
y High Radiation Power Background Channels 4
<10% Valve X (3) (6)
X(3) (6)
X(6) 8 Instrument A
Isolation Valve closure' Channels Closure 2
Turbine Control 500<P<850 psig X(4) 4 Instrument A or D Valve Fast Closure Control Oil Pres-Channels i
sure Between Fast Closure Solenoid and Disc Dump t
Valve 4
Turbine Stop
<10% Valve X(4) 8 Instrument A or D Valve Closure Closure Channels i
PBAPS NdTES FOR TABLE 3.1.1 (Cont ' d) 10.
The APRM downscale trip is automatically bypassed when the IRM instrumentation is operable and not high.
' ll.
An' APRM will<be considered operable if there are at least 2 LPRM inputs per level and at least 14 LPRM inputs of the normal complement.
12.
This equation will be used in the event of operation with a maximum fraction of limiting power density (MFLPD) greater than the fraction of rated power (FRP), where FRP = fraction of rated thermal power (3293 MWt).
MFLPD = maximum fraction of limiting power density where the limiting power density is 13.4 KW/ft for all 8 x 8 fuel.
The ratio of PRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.
k=
Loop Recirculation flow in percent of design.
W is 100 for core flow of 102.5 million lb/hr or greater.
Delta W =
the difference between two loop and single loop effective recirculation drive flow rate at the same s
core flow.
During single loop operation, the i
reduction in trip setting (-0.66 delta W) is i
accomplished by correcting the flow input of the flow biased High Flux trip setting to preserve the original (two loop) relationship between APRM High Flux setpoint and recirculation drive flow or by adjusting the APRM Flux trip setting.
Delta W equals zero for two loop operation.
f Trip level setting is in percent of rated power (3293 MWt).
4 13.
See Section 2.1.A.l.
i 14.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full power background radiation level and associated trip setpints may be changed based on a calculated value of the radiation level expected during the test.
The background radiation level and associated trip setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection.
The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels af ter completion of the test program, and within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 20% rated power. Amendment No. ;), H, E, 77, 77, 10G e
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g TABLE 3.2.A g.
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INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION g:
a O
Minimus No.
.l 2; cf Operable Number of Instrument Instrument Instrument Trip Level Setting Channels Provided Action Channels per By Design (2)
Trip System (1) 2 (6)
Reactor Low Water
> 0" Indicated 4 Inst. Channels A
j Level Level (3) i 1
1 Reactor High Pressure
< 75 psig 2 Inst. Channell D
j (Shutdown Cooling i
Isolation)
~
!i 1 2
Reactor Low-Low at or above -49" 4 Inst. Channels A
7 Water Level indicated level (4)
{
2 (6)
High Drywell Pressure
< 2 psig 4 Inst. Channels A
l 2
High Radiation Main
< 3 X Normal Rated Full 4 Inst. Channels B
1 j
Steam Line Tunnel Power Background (8) (10) i 2
Low Pressure Main
> 850 psig (7) 4 Inst. Channels B
~
)
Steam Line 2 (5)
High Flow Main
< 140% of Rated 4 Inst. Channels B
Steam Line 3 team Flow i
}
2 Main Steam Line j:,200 deg. F (9) 4 Inst. Channels a
1 Tunnel Exhaust Duct High j
Temperature i
i I
I 3
l i
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NOTES FOR TABLE 3.2.A 1.
Whenever Primary Containment integrity is required by Section 3.7, there shall be two operable or tripped trip systems for each function.
i l
2.
If the first column cannot be met for one of the trip systems, that trip system shall be tripped or the appropriate action listed below l
shall be taken:
A.
Initiate an orderly shutdown and have the reactor in Cold i
Shutdown Condition in 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br />.
B.
Initiate an orderly load reduction and have Main Steam Lines j
isolated within eight hours.
C.
Isolate Reactor Water Cleanup System.
D.
Isolate Shutdown Cooling.
I j
3.
Instrument netpoint corresponds to 177.7" above top of active fuel.
4.
Instrument setpoint corresponds to 129.7" above top of active fuel.
j 5.
Two required for each steam line.
l 6.
These signals also start SBGTS and initiate secondary containment isolation.
i 7.,only required in Run Mode (interlocked with Mode Switch).
I At a radiation level of 1.5 times the normal rated power background, 8.
an alarm will be tripped in the control room to alert the control l
room operators to an increase in the main steam line tunnel 1
radiation level.
9.
In the event of a loss of ventilation in the main steam line tunnel j
area, the main steam line tunnel exhaust duct high temperature j
setpoint may be raised up to 250 degrees F for a period not to l
exceed 30 minutes to permit restoration of the ventilation flow.
]
During the 30-minute period, an operator shall observe control room j
indications of the duct temperature so in the event of rapid increases (indicative of a steam line break) the operator shall i
promptly close the main steam line isolation valves.
1'
- 10. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection i
test with the reactor power at greater than 20% rated pwer, the
)
normal full power radiation background level and associated trip i
setpoints may be changed based on a calculated value of the radiation level expected during the test.
The background radiation j
level and associated trip setpoints may be adjusted during the' test program based on either calculations or measurements of actual i
i radiation levels resulting from hydrogen injection.
The background 1
radiation level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after completion of the test program, and within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 20% rated power.
i Amendment No. SJ,106 '
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