ML20079B098
| ML20079B098 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 12/29/1994 |
| From: | Norrholm L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079B100 | List: |
| References | |
| NUDOCS 9501050138 | |
| Download: ML20079B098 (8) | |
Text
_
("%,%
UNffED STATES E
N'UCLEAR REGULATORY COMMISSION U
wASHWGTON, D.C. SOME SMM s-r.....j IES UTILITIES INC.
CENTRAL IOWA POWER COOPERATIVE "~ # '
CORN BELT POWER COOPERATIVE.'-
er ;
DOCKET NO. 50-331
^
DUANE ARNOLD ENERGY CENTER mWw r-ANENDNENT TO FACILITY OPERATING LICENSE '.. ' t' Amendment No. 205 License No. DPR-49 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by IES Utilities Inc., et al., dated June 30, 1994, as supplemented November 10, 1994, 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; 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 (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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Technical Specifications 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:
9501050138 941229 PDR ADOCK 05000331 P
pgg
o (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 205, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the
- Technical Specifications.
-P 3.
The license amendment is effective as of the date of issuance and shall be implemented within 120 days of the date of issuance.
4 FOR THE NUCLEAR LATORY C0ttilSSION y
w y:-,
%/
ei<
J orhoim,ProjectDirector Projec Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: December 29, 1994
~'
e ATTACHNENT TO LICENSE ANENDNENT No. 205 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 areas are indicated by vertical lines.
s.
s Remove Insert 3.9-6 3.9-6 3.10-2a 3.10-2a 3.10-2b n
3.10-4 3.10-4 3.10-6 3.10-6
^
1
I.*
DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS
.C.
Soent Fuel Fool Water Level C.
SDent Puel Fool Water Level
+
1.
Whenever irradiated fuel is 1.
Whenever irradiated fuel is stored stored in the opent fuel pool, in the spent fuel pool, the water the pool water level shall be level shall be recorded daily.
maintained at a level of at least 36 feet.
a.
Whenever the spent fuel storage pool water level is found to be less than 36 feet the following 3
actions shall be taken:
1)
Immediately suspend movement of irradiated fuel assemblies in the spent fuel storage pool and place any load suspended in or above the spent fuel pool or reactor vessel into a safe configuration, ADA I
2)
Immediately take action to f
establish SECONDARY l
CONTAINMENT INTEGRITY.
D.
Auxiliary Electrical EcuiDment -
CORE ALTERATIONS shall not be performed unless all of the I
following conditions are satisfied:
a.
At least one off-site power source and either the startup or standby transformers are OPERABLE and capable of supplying power to the 4kV emergency buses.
b.
One diesel-generator is OPERABLE with:
1) its associated standby gas treatment system train OPERABLE, and 2) its associated main control
(
room ventilation standby l
filter unit subsystem OPERABLE, And 3) its associated control building chiller OPERABLE.
l l
l l
Amendment No. AAA, 205, 3.9-6
-_________-___-__________________-___-____-___-_____-_____-_____2__________
DAEC-1 I
l LIMITING CONDITIONE FOR OPERATION SURVET'2 "
- L; -il =-- m e b.
In the OOLD SEUTDOWN or REFUELING mode, with one main control room ventilation standby filter unit filtration subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or initiate and maintain operation of the OPERABLE subsystem in the isolation mode i
of operation or suspend OORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.
- -, vec m.
r
+
c.
In the COLD SHUTDOWN or REFUELING mode, with both main control room ventilation standby filter unit y%"0" "
,y subsystems inoperable, IMMEDIATELY suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary j
containment and operations with the potential for draining the l
reactor vessel.
B.
REMOTE SHUTDOWN PANELS B.
REMOTE SHUTDOWN PANELS 1.
The Remote Shutdown Panels (Bay 1.
At all times when not in use or "A" Door) and local control panels being maintained the Remote shall be visually checked once per Shutdown Panels (Bay "A" Door) week to verify they are locked.
and local control panels shall be locked.
2.
Operability of the switches on the Remote Shutdown Panels shall be functionally tested once per operating cycle.
C.
CONTROL BUILDING CHILLERS C.
CONTROL BUILDING CHILLERS 1.
Once each quarter, verify the 1.
Both Control Building Chillers Chiller operates to remove the shall be OPERABLE at all times available heat load.
when SECONDARY CONTAINMENT INTEGRITY is required, except as specified in Specifications 3.9.D, 3.10.C.2.a and 3.10.C.2.b.
2.a.
During POWER OPERATION or Reactor
- Startup, 1)
With one of the Control Building Chillers inoperable, providing the remaining Control Building Chiller is verified to be OPERABLE, restore the inoperable Chiller to OPERABLE status within 30
- 4 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Amendment No. JE3.JEE 205 3.10-2a T'C-'
We-
+-ew
- * ~
~
. _ _ _, ~.
D DAEC-1 lLIMITINGCONDITIONSFOROPERATION SURVEILLANCE REOUIREMENTS I
c.
2)
With both control Building chillers inoperable, be in a
HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in OOLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
.. a
.. e -- c b.
In the COLD SHUTDOWN or REFUELING mode, 1) with one control Building chiller inoperable, provided the remaining control Building chiller is verified to be OPERABLE, restore the inoperable Chiller to OPERABLE status within 30 days or suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.
2)
With both control Building Chillers inoperable, IMMEDIATELY suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.
a Amensment No. 205 3.10-2b
- ~ --
DAEC-1 efficiencies of the HEPA filters and charcoal adsorbers are as specified, the resulting doses will be less than the allowable levels stated in Criterion 19 of the General Design Criteria for Nuclear Power Plants, Appendix A to 10 CFR Part 50. Operation of the fans significantly different from the design flow will change the removal efficiency of the HEPA filters and charcoal adsorbers.
If one of the systems is found to be inoperable, the second unit provides protection and reactor operation, fuel handling operations may be perfomed' for a limited period of time while repairs are being made.
If the system cannot be repaired within seven days, the reactor is shut down and brought to hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, fuel handling operations or operations with the potential for draining the vessel are terminated.
B.
REMOTE SHUTDOWN PANELS The Remote Shutdown Panels are provided to assure the capability of controlling reactor pressure for taking the slant to the hot shutdown condition external to the control room for t1e unlikely condition that the control room becomes uninhabitable.
C.
Control Building Chillers The Control Building Chillers provide coolant for the Control Building HVAC system. There are two independent Chillers to ensure reliable temperature control in the Control Building. The HVAC system is designed to provide a controlled environntent under both normal and accident conditions. A single Chiller provides sufficient cooling capacity to maintain a suitable Control Room environment.
If one of the Control Building Chillers is found to be inoperable, the second unit provides protection so that Reactor Operation, CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel may continue for a limited period of tin,e while repairs are being made.
If the system cannot be repaired within thirty days, the reactor is shut down and brought to HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel are terminated.
]
Amendment No. JAA,)f), 205 3.10-4
-DAEC-1 l
If significant painting, fire or chemical _ release occurs such that the HEPA-filter or charcoal adsorber could become contaminated from the fumes, i
chemicals or foreign materials, the same tests and sample analysis shall be i
performed as required for operational usc. The determination of significant
-shall be made by the operator on duty at the time of the incident.
i Knowledgeable staff members should be consulted prior to making this determination.
. a _:,
i c
Demonstration of the automatic initiation' capability is necessary to assure,,
system performance capability.
e 4
B.
REMOTE SHUTDOWN PANELS
- ,..g Once per week verification of the panels being properly' secured is considered
[
adequate. The associated equipment is proven operable during surveillance testing of that equipment. An operability verification by functional test once per operating cycle is adequate to assure that the panels are available and can perform their design function.
C.
Control Building Chillers l
The Control Building Chiller surveil 1'ance verifies that the heat removal capability of the system is sufficient to remove the available heat load in the Control Room. The surveillance consists of a continuous run while monitoring associated Chiller parameters. The frequency of this surveillance, once per quarter, is appropriate since significant degradation of the Chillers is not expected ovqr this time period.
l i
i i
9 I
?
i i
Amendment No. 77,Ff7,FFF 205 3.10-6
[
_