ML20070E062
| ML20070E062 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold |
| Issue date: | 06/30/1994 |
| From: | IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | |
| Shared Package | |
| ML20070E054 | List: |
| References | |
| NUDOCS 9407140040 | |
| Download: ML20070E062 (10) | |
Text
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DAEC-1 l
LIMITING CONDITIONS FOR OPERATION nunvmii N CE REuu1===mnis C.
Enant Fuel Peel Water Imel C.
Snent Fuel Pool Water Level p
1.
Whenever irradiated fuel is.
1.
Whenever irradiated fuel is stored stored in the spent fuel pool, in the spent fuel pcol, the water the pool water level shall be level shall be recorded daily.
I maintained at a level of at least
'i 36 ieet.
a.
Whenever the spent iual storage pool water level is found to be 1
less than 36 feet the following i
actions shall be taken:
1 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, and 2)
Immediately take action to establish SECONDARY CONTAINMENT INTEGRITY.
D.
Auxiliary Elsetrical Eerui-nt CORE ALTERATIORS 1.
CORE ALTERATIONS shall not be i
performed unless all of the following conditions are
'j satisfied:
)
a.
At least one off-sits power source and either the startup or standby transformers are OPERABLE and capable of supplying power to l
the 4kV esorgency buses.
b.
One diesel-generator is OPERABLE with:
1) its associated standby gas treatment system train l
orERAsLE, and i
2) its associated main control i
room ventilation standby filter unit system orERAsts. t c
- 3) i 4 s u no c R + c4 c.or W \\
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9407140040 940630 PDR ADOCK 05000331 P
PDR Amendment No. 106 3.9-4 AUG 2 51'G2
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a DAEC-I l
LIMITING CONDITION FOR OPERATION
$URVEILLANCE REQUIREMENT b.
In the COLD SHUTDOWN or REFUELING mode, with one main control room ventilation standby filter unit filtration subsystem inoperable.
I restore the inoperable subsystem to OPERABLE status within 7 days or initiate and maintain operation of the OPERABLE subsystem in the isolation mode of operation or suspend CORE ALTERATIONS, handling i
of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel, c.
In the COLD SHUTDOWN or REFUELING mode, with both main control room ventilation standby filter unit i
subsystems inoperable, IMEDIATELY
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suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.
I B.
REE TE SHUTDOWN PANELS 8.
REETE SHUTDOWN PANELS l
1.
The Remote She+,down 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) and week to verify they are locked.
I local control panels shall be locked.
2.
Operability of the switches on the Remote Shutdown Panels shall be i
functionally tested once per y,3 3 e c 4 4 operating cycle.
.Z' n.5 e c +,2 1
Amenthnent No. J53,165 3.10-2a APR 2 6 Igm
1 Insert 1 C.
CONTROL BUILDING CHILLERS 1.
Both Control Building Chillers shall be OPERABLE at all times 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 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 />.
2)
With both Control Building Chillers inoperable, be in 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 />.
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.
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Insert 2 C.
CLNTilOL BUILDING Ci!ILLERS 1.
Once each quarter, verify the Chiller operates to remove the available hea; load.
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' DAEC-1 efficiencias of the HEPA filters and charcoal adsorbers are as specified.
the resulting doses will be less than the allowable levels stated in Criterion lg of the General Design Criteria for Nuclear Power Piants. Appendix A to 10 CFR Part 50.
Operation of the fans significantly different from the design flow will change the renoval 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 b2 performed l
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 tenninated.
l B.
REMOTE SHUTDOWN PANELS The Remote Shutdown Panels are provided to assure'the capability of controlling -
reactor pressure for taking the plant to the hot shutdown condition external to the control room for the unlikely condition that the control room becomes uninhabitable, r~
.1:nSec& 3 f
Amendment No. 153. 165 3.10-4 e1 APR 26 580
I Insert 3 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 environment 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 time 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, handll:rg of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel are terminated.
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DAEC-P C 9p ;; G i6 '
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If significant painting, fire or chemical release occurs such that the MEPA filter or charcoal adsorber could become contaminated from the fumes, chemicals or foreign materials, the same tests and sample analysis shall be performed as required for operational use. The detemination of significant shall be made by the operator on duty at the time of the incident.
Knowledge-able staff members should be consulted prior to making this detemination.
Denonstration of the automatic initiation capability is necessary to assure system performance capability.
B.
REMOTE SHUTDOWN PANELS l
Once per week verification of the panels being properly secured is considered l
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.
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f.
Amendment No. 79. W. 165 3.10-6 APR 2 61990 O
9 Insert 4 C.
Control Building Chillers The Control Building Chiller surveillence verifles 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 over this time period.
'RTS-257 to NG-94-0669 Page 1 of 1 SAFETY ASSESSMENT 1.
Introduction By letter dated June 30, 1994, IES Utilities Inc. requested changes to the Duane Arnold Energy Center (DAEC) Technical Specifications (TS).
The proposed change will add Limiting Conditions for Operation (LCO) and Surveillance Requirements (SR) for the Control Building Chillers.
2.
Evaluation The DAEC Control Building Chillers are installed to remove the design basis heat load under all normal and emergency conditions.
The Control Building consists of the Control Room, Essential Switchgear Rooms, Battery Rooms and Cable Spreading Room.
The Control Building is designed to be maintained within an allowable tolerance for temperature and humidity to assure long-term equipment operation and habitability by operations personnel.
The Chillers are essential to that purpose because they provide coolant to the heat exchangers which remove heat from the areas in the Control Building.
The operability of the Control Building Chillers is currently controlled by an administrative LCO.
The proposed amendment revises DAEC TS Section 3.10 to add OPERABILITY requirements, LCOs and SRs for the Control Building Chillers.
In addition TS Section 3.9 is revised to address Control Building Chiller OPERABILITY during CORE ALTERATIONS.
The proposed LCO is consistent with BWR/4 Improved Standard Technical Specifications, NUREG-1433.
The proposed SR, combined with the DAEC heat exchanger testing progicm (in accordance with GL 89-13), meets the intent of the Improved Standard Technical Specifications.
Therefore, we conclude that the proposed addition of the Control Building Chillers to the TS is acceptable, i
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'RTS 257 to NG-94-0669 Page 1 of 1 ENVIRONMENTAL CONSIDERATION 10 CFR 51.22(c)(9) identifies certain licensing and regulatory actions which are eligible for categorical exclusion from the requirement to perform an environmental assessment.
A proposed amendment to an operating license for a facility requires no environmental assessment if operation of the facility in accordance with the proposed amendment would not:
(1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; and (3) result in an increase in individual or cumulative occupational radiation exposure.
IES Utilities Inc. has reviewed this request and determined that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment.
The basis for this determination follows:
Basis The change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) for the following reasons:
1.
As demonstrated in Attachment 1 to this letter, the proposed amendment does not involve a significant hazarde consideration.
2.
The proposed addition of the Control Building Chillers to the Technical Specifications for Duane Arnold Energy Center will have no effect on the types or amounts of effluents released offsite.
3.
The proposed addition of the Control Building Chillers to the Technical Specifications for Duane Arnold Energy Center will have no effect on individual or cumulative occupational radiation exposures.
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