ML19331C044
| ML19331C044 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 07/31/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19331C045 | List: |
| References | |
| NUDOCS 8008140084 | |
| Download: ML19331C044 (7) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION 8%
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IOWA ELECTRIC LIGHT AND POWER COWANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET N0. 50-331 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 License No. DPR-49 The Nuclear Regulatory Commission (the Commission) has found that:
1.
A.
The application for amendment by Iowa Electric Light and Power Company, Central Iowa Power Cooperative, and Corn Belt Power Cooperative (the licensees) dated July 7,1980, 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 facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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.
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2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-49 is hereby amended to read as follows:
l (2) Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 62, are hereby incorporated in the license. The licensee shall operate the facility in l
accordance with the Technical Specifications.
i 9008140OS9
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This license amendment is effective from July 7,1980 to July 14, 1980.
FOR THE NUCLEAR REGULATORY COMMISSION
&c% :Md Thomas A/ Ippolito, Chief 1
Operating Reactors Branch #2 Division of Licensing Attacivnent:
Changes to the Technical Specifications Date of Issuance: July 31,1980 1
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ATTACHMENT TO LICENSE AMENDMENT NO. 62 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET N0. 50-331 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment l
number and contain vertical lines indicating the area of change.
Remove Replace 1.1-2 1.1-2 1.1-3 1.1-3 3.2-16 3.2-16 3.6-7 3.6-7 t
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DAEC-1 LIMITING SAFETY 5,Y_ STEM _ _ SETTING SAFETY LIMIT Where: 5 = Setting in percent of 16.C Power Transient _
rated power (1,593 IGt)
Yo ensure that the Safety W = Recirculation loop flow imits established in Speci-in percent of rated flow.
fication 1.1.A and 1.1.8 are Rated recirculation loop not exceeded, each required flow is that recirculation scram shall be initiated by loop flow which corresponds its primary source signal.
to 49x108 lb/hr core flow.
A Safety Limit shall be assumed to be exceeded when scram is accomplished by a means other than the Primary Source Signal.
D.
With irradiated fuel in the reactor vessel, the water level shall not be less than 12 in.
For a MFLPD greater than FRP, the above the top of the nomal APRM scram setpoint. hall be:
active fuel zone. Top of the active fuel zone is defined to S < (0.66W + 54) d tor two be 344.5 inches above recirculation loop operation and vessel zero (See Bases 3.2)
FRP for onT 5 < (0.66W + 50.7)_ FLPD M
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recirculation loop operation.
NOTE: These settings assume operation within the basic thermal design criteria.
These criteria are LilGR < 18.5 KW/ f t (7x7 array) or 13.4 KW/ft (8x8 array)
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and MCPR > values as indicated in Table 3.12!2 times K, where Kf is de-fined by Figure 3.12f1.
Therefore, at full power, operation is not allowed with MFLPD greater than unity even if the scram setting is reduced.
If it is determined that either of tt.ese design criteria is being violated during operation, action must be taken imediately to return to operation within these criteria.
- 2. APRM High Flux Scram When in the REFUEL or STARTUP and tiOT STANDBY MODE. The APRit scram shall be set at less than or equal to 15 percent of rated power.
- Effective July 7 through July 14, 1980 I I-2 Amendent No.
6, 61 62
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DAEC-1 LIMITING SAFETY SYSTEM SETTING SAFETY LIMIT 3.
APRM Rod Block When in Run Mode.
for operation with MFLPD less than or equal to FRP the APRM Control Rod Block setpoint shall be.as shown on Fig. 7.1-1 and shall be:
S < (0.66W + 42)
.I fhe definitions used above for the APN4 scram trip apply.
For a MILFD greater than FRP, the APRM Control Rod Block set-point shall be:
"P or S f (0.66W + 42) 7q pD two recirculation loop operation, and FRP for S < (0.66W + 38.7)
'MFLPD one recirculation loop operation.
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4.
IRM - the IRM scram shall be set at less than or equal to 120/125 of full scale.
B.
Scram and Iso-
~ 513.5 inches lation on reac-above vessel tor low water zero (+12" on level icvel instru-nents)
C.
Scram - turbine i 10 percent stop valve valve closure closure D,
Turbine control valve fast closure shall occur within 30 milliseconds of the start of turbine control valve fast closure.
- Effective July 7 through July 14, 1980
[, 62 1.1-3 A e.d ent No.
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TABLE 3.2-C Minimum No.
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of Operable Instrument Number of Channels Per Provided by Design Action Instrument Channels Trip System Instrument Trip Level Setting 2
APRM Upscale (Flow Biased) for 2 recirc loop operation S(0.66W + 42) FRP (2) 6 Inst. Channels (1)
MFLPD for 1 recirc loop operation
$(0.66W + 38.7) FRP (2)
MFLPD 2
APRM Upscale (Not in Run Mode)
$,12 indicated on scale 6 Inst. Channels (1) l 2
APRM Downscale 15 indicated on scale 6 Inst. Channels (1)
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1 (7)
Rod Block Monitor for 2 recirc loop operation (Flow Biased)
$(0.66W + 39)
FRP 2 Inst. Channels (1) l 2)
MFLPD 5,
for 1 recirc loop operation j
$(0.66W + 35.7)
FRP (2)
MFLPD 1 (7)
Rod Block Monitor 15 indicated on scale 2 Inst. Channcis (1) 1 Downscale Ng 2
IRM Downscale (3) 15/125 full scale 6 Inst. Channels (1) al 2
IRM Detector not in (8) 6 Inst. Channels (1)
Startup Position 2
P 2
IRM Upscalc
<108/125 6 inst. Channels (1)
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2 (5)
SRM Detector not 1..'
(4) 4 Inst. Channels (1)
Startup Position 5
2(5)(6)
SRM Upscale
<10 counts /sec.
4 Inst. Channels (1).
- Effective July 7 through July 14, 1980
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LIMITING CONDITIONS FOR CPERATION SORVEILLANCs ste.Uva rwru,....
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Tha indicated valua of core (U
flow rate varies f rons the value derived f rom loop
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flow measurements by snore than 10%.
The dif fuser t.o lower plenum c.
differential pressure read '
ing on an individual jet pump varies from the raean of all jet pump dif ferential pressures by more than 10%.
Whenever there is recircu-2.
lation flow with the reactor in the Startup or Run mode,
and one recirculation pump is operating, the dif fuser to lower plenum dif ferential pressure shall' he checked daily and the dif ferential pressure of an individual jet pump in a loop shall not vary f rom the mean of all jet pump dif ferential pres-sures in that loop by more
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than 10%.
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Jet Pump' Flow Mismatch' F.
Jet Pump Flow Mismatch F.
1.
When both recirculation-1.
Recirculation pump speeds shall be checked and logged pumps are in steady state at least once per day.
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operation, the speed of the faster pump may not exceed 122% of the speed of the slower pump when core power is 80% or more of rated power or 135% of the speed of the slower pump when core power is below 80% of rated power.
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- 2.
If specification 3.6.F.1 cannot
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be met, one recirculation pump shall be tripped. The reactor I
A may be started and nnerated with,'
a one recirculation loop out of ser-g vice provided that:
a.
A MAPLHGR multiplier of l
Y' 0.65 is applied.
b.
The power level is limited to l
a maximum of 50% of license,d power.
c.
The idle loop is isolated (suction valve closed ar.d electrically disconnecte:I
- Effective July 7 through July 14, 1980 3.6-7
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