ML20199G164
| ML20199G164 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 03/27/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Central Iowa Power Cooperative, Corn Belt Power Cooperative, Iowa Electric Light & Power Co |
| Shared Package | |
| ML20199G167 | List: |
| References | |
| DPR-49-A-131 NUDOCS 8604090077 | |
| Download: ML20199G164 (9) | |
Text
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[
o UNITE D STATES g
NUCLEAR REEULATORY COMMISSION g
p WASHINGTON, D. C. 20555
~
"%.....l IOWA ELECTRIC LIGHT AND POWER COMPANY ~
CENTRAL IOWA POWER COOPERATIVE _
CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 131 License No. DPR-49 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Iowa Electric Light and Power Company, et al, dated January 3,1986, 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 fccility will operate in conformity 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 conron 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 Specifi-cations as indicated in the attachmant to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-49 is hereby amended to read as follows:
0604090077 860327 DR ADOCK 0500 1
L (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.'131, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION en
'i df Daniel R. Muller, Director BWR Project Directorate #2
^
Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 27, 1986 k
=
1 b
t:
ATTACHMENT TO LICENSE #iENDMENT NO. 131_
FACILITY CPERATING LICENSE NO. DPR-49 q
DOCKET NO. 50-331 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are ir.dicated by carginal lines.
Pages 3.1-4 3.1-7a
- 3.1-18 3.2-5 3.2-7 3.2-39
- Page added o
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TABLE 3,1-1 (Centfrued)
REACTOR PROTFCTION SYSTEM ($CP.AM) 14STRupeEMTAT104 REQUIREENT M!ntamm ho.
of Operable Mo1ec ln Whfeb Weber of
~
f nstrument Fnoction "4Jst be I nstrumen t Channels Operable Channels for Trip Reical Sto rtup Run Prcvfded Systen (1)
Trfp Fenetton Trip Level Setting (C)
By Design Action (1) 2 High Drywell Pressure 1 2.0 psig X( 7)
X(8)
X 4 f astrument A
Chennels 2
Reactor La unter 1 +170" Ind?mted X
X X
4 InstrLannt A
Level Lcvel (15)
Channels 2
Hig% unter Level In 1 60 Gallons X(23 X
X 4 Instrunusnt A
Screm Discherge Volusse Chaarets 2
Mein Steen Line 13 m Nyne l Re
- ed X
X X
4 I nst rument A
w High Red?otton Power BackgroJnd" (16)
Channels l
wb 4
win Steen Line 1105 Velve Closuro X
X X(13) 8 instrument A or C isolation Velve (3)(13) I3)(13)
Chennels Closers 2
Turbine Control Velve within 30 milliseconds Xi4) 4 Ansteuent A or D S
Fast Closure (Loss of the Stdrt of Control C% nnels S.
of Control Oli volw Fsst Closure 2
Pressure)
S 4
Turnine Stop Velve
<10$ Velve Closure A(4)
' b' instrused A or D
?
Closure Che r.nels 2
First Stage Gypots belum *65 psig M
X X
4 i nstrumn+-
A er 0 Chornels C
'Atern satting 1 5 X Norwl Rated Power Background (10)
)
1
- --v.
7..
i DAEC-1 n_
-16.
Within 24 hcars prior to the planned ~ start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full-pcwer r&diation backgro'und level and essociated trip and alarm J
setpaints Bay be changed based on a cal:ulated value of the radiation 1evel expected during the test.
The back. ground radiation level and assocf sted trip and alana selpoints mAy be adjusted during th.e test peogran based on either calcu;ations of measurements of actual radiation levels resulting fiom hydrogen injection, The background radiation leve) shall be determined and associated trig 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 reestablishing normal radiatior. levels after completloo of the hydrogen injection or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of estah11shing reactor power levels below 20% rated power. While these functions are required to be operable.
5 i
/
l Amendment flo.
- 131, 3.1-7a i
DAEC-1 High radiation levels in the main ster 1 line tunnel above that due to the normal nitrogen and oxygen radioactivity is an Indication of leak-ing fuel. A scra is initiated wnenever str:h radiation level exceeds three times normal background.
For the performance of a Hydrogen. Water Chemistry pfe-implementatien test, the scram setpoint may be changed j
based on a calculsted value of the radiaticq level expected during the I
test. Hydrogen additioti will result in an approximate onem to five-fold increase in the nitrogen (N-16) activity in the steam due to increased t<-16 carryover in the main steam.
The purpose of this scram is to reduce the source of such radiation to the extent necessary to limit the amount of radioactivity released due to gross fuel f ailure.
Discharge of excessive amQuats of radioactivity to the environs is prevented by the air ejector offgas moniters which cause an isolation of the main Condenser offgas line to the main stack.
l The MSIV closure scram is set to m when the isolation valves are 10Y, closed in 3 out of 4 line-t :- scram anticipates the pressure and flur transient which woulo when the valves close. By l
scracming at this setting, the resultant transient is less severe than olther the pressure or flux transient which would otherwise result.
t l
A reactor mode switch is provided which actuates or bypasses the various scram functions appropriate to the particular plant operating status.
The manual scram function is active in all modes, thus providing for a manual means of rapidly ins'erting control rods during all modes of reactor operation.
Anendment No. 131' 3.1-18
n r
a TABLE 3.2-A INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION F
Q Minimum No.
Number of of Operable Instrument w
Instrunent Channels Valve Groups M
Channels Per Provided by Opere'.ed by Trip System (1)
Instrument Trip Level Setting Design Signal Action (2) w 2 (6)
Reactor Low
> +170" Indicated Level 4
2,3,4,5 A
Water Level (7)
(Sec. Cont., 3 E) 1 Reactor Low Pres-
< 135 psig 2
4 C
sure (Shutdown Cooling Isolation) 2 Reactor Low-Low-Low
> +18.5" indicated 4
1 A
Water Level Tevel (3) w h 2 (6)
High Drywell
< 2.0 psig 4
2,3,4,8,9*
A
~
Pressure (Sec. Cont., 3 E) 2 High Radiation
< 3 X Normal Rated 4
1 B
Main Steam Line Power Background (S) l Tunnel 2
Low Pressure Main
> 850 psig (7) 4 1
B 4
Steam Line l
2 (5)
High Flow Main
< 140% of Rated 4
1 B
Steam Line Steam Flow 4
i 2
< 200* F.
4 1
B Tunnel / Turbine Bldg.
High Temperature 1
Reactor Cleanup
-< 40 gpmd 2
5 D
System High Diff.
Flow
- Group 9 valves isolate or. high drywell pressure combined with reactor steam supply low pressure
OAEC-1 l
e 5.
Two required for each steam line.
6.
These signals also start SBGTS and initiate secondary containment isolation.
7.
Only required in Run Mode (interlocked with Mode Switch).
8.
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 radiation background level and associated trip setpoints 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 determired 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 reestablishing normal radiation levels after completion of the hydrogen injection test or 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, while these functions are required to be operable.
Amendment No. 89, 131, 3.2-7
v l
DAEC-1 0
Temperature monitoring instrumentation is provided in the main steam line tunnel and turbine building to detect leaks in this area. Trips are provided on this instrumentation and when exceeded, cause closure of isolation valves. See Spec 3.7 for Valve Group. The setting is 200*F for the main steam line tunnel detector. For large breaks, the high steam flow instrumentation is a backup to the tenperature instrumentation.
High radiation monitors in the main steam line tunnel have been provided to detect gross fuel failure as in the control rod drop accident. With the established setting of 3 times normal background, and main steam line isolation valve closure, fission product release is limited so that 10 CFR 100 guidelines are not exceeded for this accident.
For the performance of a Hydrogen Water Chemistry pre-implementation test, the scram setpoint may be changed based on a calculated value of the radiation level expected during the test. Hydrogen addition will result in an approximate one-to five-fold increase in the nitrogen (N-16) activity in the steam due to increased N-16 carryover in the main steam. Reference Subsection 15.4.7 of the Updated FSAR.
Pressure instrumentation is provided to close the main steam isolation valves in RUN Mode when the main steam line pressure drops below 850 psig.
The Reactor Pressure Vessel thermal transient due to an inadvertent opening of the turbine bypass valves when not in the RUN Mode is less severe than the loss of feedwater analyzed in Subsection 15.6.3 of the Updated FSAR, therefore, closure of the Main Steam Isolation valves for thermal transient protection when not in RUN Mode is not required.
Amendment flo. JJA, 131, 3.2-39
.