ML19305E550
| ML19305E550 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  (DPR-49-A-060, DPR-49-A-60) |
| Issue date: | 05/06/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19305E551 | List: |
| References | |
| NUDOCS 8005200046 | |
| Download: ML19305E550 (8) | |
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UNITED STATES
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8 NUCLEAR REGULATORY COMMISSION o
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IOWA ELECTRIC LIGHT AND POWER CO W ANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331-AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No. DPR-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Iowa Electric Light and Power Company, Central Iowa Power Cooperative, and Corn Belt Power l
Cooperative (the licensees) dated May 2,1980, 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 conformity with the application,
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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
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have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and pcragraph 2.C.(2) of Facility Operating License No. DPR-49 is hereby amended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 60, are hereby incorporated in the license. The licensee shall operate the facilit.y 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 n
Thomas
. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Speci fications Date of Issuance:
May 6,.1980 i
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4 ATTACHMENT TO LICENSE AMENDMENT N0. 60 FACILITY OPERATING LICENSE NO. DPR-49 DOCK ; NO. 50-331 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.
Remove Replace 1.1-2 1.1-2 1.1-3 1.1-3 3.2-16 3.2-16 3.2-17 3.2-17 3.6-7 3.6-7 1
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DAEC-1 l !
LIMITING SAFETY SYSTEM SETTING SAFETY LIMIT 16.C Power Transient Where: S = Setting in percent of rated power (1,593 MWt)
To ensure that the Safety Limits established in Speci-W = Recirculation loop flow fication 1.1. A and 1.1.B are in percent of rated flow.
not exceeded, each required Rated recirculation loop scram shall be initiated by flow is that recirculation its primary source signal.
loop flow which corresponds 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, above the top of the nonnal For a MFLPD greater than FRP, the active fuel zone. Top of the APRM scram 5etpoint shall be:
active fuel zone is defined to y
tor two be 344.5 inches above S $ (0.66W + 54) pg._19 vessel zero (See Bases 3.2) recirculation loop operation and FRP f r one S 3 (0.66W + 50.7) p pD recirculation loop operation.
NOTE: These settings assume operation within the basic thermal design criteria.
These criteria are LHGR e 18.5 KW/ft (7x7 array) or 13.4 KW/ft (8x8 array)
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and MCPR > values as indicated in 1
Table 3.1272 times K, where Kf is.de-fined by Figure 3.12f1.
Therefore,.at f
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 these design criteria is being violated during operation, action must be taken ininediately to return to operation within these criteria.
- 2. APRM High Flux Scram When in the REFUEL or STARTUP and HOT STANDBY MODE. The APRM scram shall be set at less than or equal to 15 percent of rated power.
Amendment No.
, 60 1.1-2
DAEC-1 SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING 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. 2.1-1 and shall be:
S,f(0.66W+42) l i
l The definitions used above for the APmiseram trip apply.
For a MFLPD greater than FRP, the APRM Control Rod Block set-point shall be:
FRP S f (0,66W + 42) g for two recirculation oop operation, and S < (0.66W + 38.7) FRP for
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'MFLPD one recirculation loop operation.
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
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lation on reac-above vessel tor low water zero (+12" on level level instru-nents)
C.
Scram - turbine
$ 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.
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Amendment No, ps, 60 1.1-3
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.u TABLE 3.2-C Minimum No.
of Operable Instrument Number of Channels Per Instrument Channels Trip System Instrument Trip Level Setting Provided by Design Action 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 5(0.66W + 38.7) FRP (2)
MFLPD 2
APRM Upscale (Not in Run Mode)
$12 indicated on scale 6 Inst. Channels (1) 2 APRM Downscale
>5 indicated on scale 6 Inst. Channels (1) 1 (7)
Rod Block Monitor for 2 recirc loop operation (Flow Biased)
$(0.66W + 39)
FRP 2 Inst. Channels (1)
(2)
MFLPD w
na 1,
for 1 recirc loop operation
<(0.66W + 35.7)
Rod Block Monitor 2,5 indicated on scale 2 Inst. Channels (1)
Downscale f
2 IRM Downscale (3)
- >5/125 full scale 6 Inst. Channels (1) o.l 2
IRM Detector not in (8) 6 Inst. Channels (1)
Startup Position r*
2 P
2 IRM Upscale
<1 D8/125 6 Inst. Channels (1) 2 (5)
SRM Detector not in' (4) 4 Inst. Channels (1)
Startup Position a,
5 2(5)(6)
SRM Upscale
$10 counts /sec.
4 Inst. Channels (1)
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DAEC-1 NOTES FOR TABLE 3.2-C 1.
For the startup and run positions of the Reactor Mode Selector Switch, there shall be two operable or tripped trip systems for each function.
Ths' SRM and IRM blocks need not be operable in "Run" mode, and the APRM [except for APRM Upscale (Not in Run Mode)] and RBM rod blocks need not be operable in "Startup" mode.
If the first column cannot be met for one of the two trip systems, this condition may exist for up to seven days provided that during that time the operable system is functionally tested immediately and daily thereafter; if this condition lasts longer than seven days, the system shall be tripped.
If the first column cannot be met for both trip systems, the systems shall be tripped.
2.
W is the recirculation loop flow in percent of design. Trip level setting is in percent of rated powe'r (1593 MWt). A ratio of FRP/MFLPD
( 1.0 is permitted at reduced power.
3.
IRM downscale is bypassed when it is on its lowest range.
4.
This function is bypassed when the count rate is >100 cps.
Amendment No. 60 3.2-17
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE HEQ u i ne,MENTs 1'
('
b.
The indi.cated valua of core flow rate varies frona the I
value derived f rom loop
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flow measurements by snore than 10%.
c.
The diffuser to 3ower plenum differential pressure read-ing on an individual jet pump varies from the raean of all jet pump dif ferential pressures by more than 10%.
2.
Whenever there is recircu--
lation flow wit.h the reactor in the Startup or Run mode, and one recirculation pump is operating, the dif fuser to Iower plenum dif ferential pressure shall be checked j
daily and the dif ferential pressure of an individual jet pump in a loop shall not vary from. the mean of all jet pump dif ferential pres-sures in that loop by more
[--o than 10%.
b" F.
Jet Pump Flow Mismatch F.
Jet Pump' Flow Mismatch' 1.
When both recirculation 1.
RNirculation pump speeds pumps are in steady state shall be checked and logged
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operation, the speed of at least once~per day.
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.
I 2.
If specification 3.6.F.1 cannot be met, one recirculation pump shall be tripped. The reactor f
may be started and operated with l l
one recirculation loop out of ser-vice provided that:
i a.
A MAPLHGR multiplter of
)i 0.65 is applied.
W
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b.
The power level is limited to I
a maximum of 50% of license,d i
power.
c.
The idle loop is isolated (suction valve closed and electrically disconnected).
L N 60 3.6-7
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