ML19330B244
| ML19330B244 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 07/17/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19330B245 | List: |
| References | |
| NUDOCS 8007310222 | |
| Download: ML19330B244 (7) | |
Text
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sa ne:
o UNITED STATES g
p, NUCLEAR REGULATORY COMMISSION
- E WASHINGTON, D. C. 20555
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IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 AMENDMENT TO FACILITY ODERATING LICENSE Amendment No. 61 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 Cooperativ'e, and Corn Belt Power Cooperative (the licensees) dated June 28, 1980, complies with the standards and re as amended (the Act)quirements of the Atomic Energy Act of 1954,
, and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 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.
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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 61, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8007S10 M A i
c
. h 3.
This license amendment is effective as of June 28, 1980.
FOR THE NUCLEAR REGULATORY COMMISSION Thoma
. Ippolito, Chief Operating. Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specificaticus Date of Issuance:
July 17,1980 0
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i
7.'
ATTACHMENT TO LICENSE AMENDMEtiT N0. 61 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET 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.
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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 1
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DAEC-1 SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING e
16.C Power Transient Where: S = Setting in percent of rated power (1,593 MWt)
To ensure that the Safety Limits established in Spect-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 s
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 normal For a MFLPD greater than FRP, the active fuel tone. Top of the APRM seram setpoint shall be:
active fuel zone is defined to g
be 344.5 inches above S 3 (0.66W + 54)
M F.)D for two vessel zero (See Bases 3.2) recirculation loop operation and FRP for one
- S $ (0.66W + 50.7) p pg recirculation loop operation.
NOTE: These settings assume operation within the basic thermal design criteria.
These criteria are LHGR f, 18.5 KW/f t (7x7 array) or 13.4 KW/ft (8x8 array) and MCPR > values as indicated in Table 3.1272 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 these design criteria is being violated during operation, action must be taken ininediately to return to operation within these criteria.
shall be set at less than or equal to 15 percent of rated power.
- Effective June 28 through July 1, 1980.
Amendment No.
61 1.1-2
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DAEC-1 SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING 3.
APRM Rod Block When in Run
%de.
For operation with MFLPD less than or equal to FRP the APRM s
f Control Rod Block setpoint shall be.as shown on Fig. 2.1-1 and shal.1 be:
S,f(0.66W+42) l I
t The definitions used above for the APRM scram trip apply.
For a MFLPD greater than FRP, the APRM Control Rod Block set-point shall be:
S f (0.66W + 42) M I#
D two recircQ1ation oop operation, and S < (0.66W + 38.7) FRP for *
'HFLPD 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-2 513.5 inches lation on reac-above vessel tor low water acro (+12" on level icvel instru-ments)
C.
Scram - turbine i 10 percent stop valve valve closure closure
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D.
Turbine control ' valve fast closu:e shall occur within 30 milliseconds of the start of turbine control valve fast closure.
- Effective June 28 through July 1, 1980 Amendment No, 61 1.1-3 I
TABLE 3.2-C Minimum No.
of Operable Instrument Channels Per Number of Instrument Channels Trip System Instrument Trip Level Setting Provided by Design Action 2
APRM Upscalfe (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 15 indicated on scale 6 Inst. Channels (1)
,..-.-~m 1 (7)
Rod Block Monitor for 2 recirc loop operation (Flow Biased) f(0.66W + 39)
FRP 2 Inst. Channels (1)
(2)
MFLPD for 1 recirc loop operation 1(0.66W + 35.7)
FRP (2)
MFLPD 1 (7)
RodB1hekMonitor 15 indicated on scale 2 Inst. Channels (1)
. Downscale E
2
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IRM Downscale (3) 25/125 full scale 6 Inst Channels (1) -
ag 2
IRM Detector not in (8) 6 Inst. Channels (1)
Startup Position
=
P 2
IRM Upscale
$108/125 6 Inst. Channels (1) 2 (5)
SRM Detector not in' (4) 4 Inst. Channels (1)
Startup Position 5
2 (5) (6)
SRM Upscale
$10 counts /sec.
4 Inst. Channels (1).
- Effective June 28 through July 1, 1980.
LIMITING CUNDITION> FOR OPERATION S*"RVELL 1,ANCE Mt,UU A nt,Mr,ft ad g
(g. '
b.
Th9 indicated volue of c ro flow rate varies froan the 7
value derived from loop s.
flow measurements by snore than lot.
i c.
The diffuser to lower plenum dif ferential pressure read '
ing on an individual jet pump varies from the raean of all jet pump differential pressures by more than lot.
i 2.
Whenever there is recarcu-
~
lation flow with the reactor
)
in the Startup or Run mode,
)
and one recirculation pumo 1
is operating, the dif fuser to lower plenum dif ferential pressure shall' be checked daily and the dif ferential l
pressure of an individual jet pump in a loop shall not
)
vary f rom. the mean of all 1
jet pump differential pres-g.-
sures in that loop by more
-8 than 104.
(,
F.
Jet Pump Flow Mismatch F.
Jet Pump' Flow Mismatch' l
1.
When both recirculation 1.
Recirculation pump speeds pumps are in steady state shall be checked and logged operation, the speed of at least once'per day
)
the f aster 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 p
pump when. core power is g
below 80% of rated power.
I g
,2.
- If specification 3.6.F.1 ginnot I
be met, one recirculation pump E
shall be tripped. The reactor f
may be started and nperated with l I
one recirculation loop out of ser-(
vice provided that:
l a.
A MAPLHGR multiplier of l
0.65 is applied.
W
(
b.
The power level is limited to i'
a maximum of 50% of licensed power.
c.
The idle loop is isolated i
(suction valve closed and electrically disconnected).
- Effective 6/28 thru 7/2/80 3.6-7 1