ML19309G009
| ML19309G009 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/10/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19309G010 | List: |
| References | |
| NUDOCS 8005020169 | |
| Download: ML19309G009 (24) | |
Text
_.
O 8006020169 o
UNITED STATES NUCLEAR REGULATORY COMMISSION
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,E WASHINGTON, D. C. 20555 IOWA ELECTR:0 LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 58 License No. DPR-49 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment by Iowa Electric Light and Power Company, Central Towa Power Cooperative, and Corn. Belt Power Cooperative (the licensee) dated August 30, 1977 (supplemented March 18,1980), October 22,1979 (supplemented April 9,1980),
and March 4,1980, comply 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; B.
The facility will operate in conformity with the applications, 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 Specifi-cations 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:
t
2_
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 58, are hereby incorporated in the license. The licensee shall operate the facility in accor-dance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY CO MISSION 0:'
Thoma Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: April 10, 1980
l ATTACHMENT TO LICENSE AMENDMENT NO. 58 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.
3.2-4 3.2-14 3.2-15 3.2-23 3.2-26 3.2-34 3.7-14 3.7-41 3.8-2
- 3.8-11 3.8-12
- No change.
Provided for convenience i
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+
LIMITIflG CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT G.
Recirculation pumo Trio G.
Recirculation Pumo Trip (ATWS)
Instrumentation and logic shall be functionally tested, The limiting conditions for operation calibrated, and response time for the instrumentation that trips tested as indicated on Table the recirculation pumps as a means 4.2-G.
of limiting the consequences of a failece to scram during an anticipated transient are given in Table 3.2-G.
(EOC)
The limiting conditions for operation for the instrumen-tation that trips the recir-culation pumps during turbine stop valve or control valve fast closure for transient margin improvement (especially for end of cycle) are given in Table 3.2-G.
Amendment No. 58 3.2-4 a
w-
TAnLE 3.2-n (continued) ctg INSTRUMENTATION THAT INITIATES OR CONTROLS TIIE CORC AND CONTAINMENT s
ct COOLING SYSTCHS O
M t :imum No.
of Operabic Instrument Number of Channels Por Instrument Channels Trip Syc to:n (1)
Trip Function Trip Lovel Setting Provided by Design Remarks 1
RCIC Luak Detection 30 min.
2 Inst.
Timo Dolay 2 (5)
IIPCI Steam Line Low 100 > P :s SG psig 4 Inst.
Pressure g33 2
IIPCI Equipment noon 6 175 deg. F 4 Inst.
y Iligh A.mbient Temp-O eraturc y
to 0
2 itPCI Equipment Rogm 4 6 50 deg. F 4 Inst.
g3) liigh Di f f. Temperature a
I per 4 t:V Dus 4 kV Emergency nus 20 6: V f. 28 Volts 2
- 1. Trips all loaded Undervoltage breake rs
- 2. Past transfer per-missive
Pe rmits Sequencing g
Sequential Loading of vital loads Relay 2 por 4kV Dus Emcrgency Transformer 65% of Rated Voltage 4
- 1. Trips cmergency trann-
{
Untic rvol tage formor feed to 4KV emergency bus
~~
- 1. Trips 4 KV cmergency bus (7)
Degraded Voltage 8.0 $ T.D. 6 8.5 incoming breakers Sec.
- 2. Starts dicsci
- 3. Permits sequencing of vital loads m-
DAEC-1 NOTES FOR TABLE 3.2-B 1.
Whenever any CSCS subsystem is required by subsection 3.5 to be operable, there shall be two operable trip systems.
If the first column cannot be met for one of the trip systems, that trip system shall be placed in the tripped condition or the reactor shall be placed in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
Close isolation valves in RCIC subsystem.
3.
Close isolation valves in HPCI subsystem.
4.
Instrument setpoint corresponds to 18.5" above the top of active fuel.
5.
HPCI has only one trip systen for these sensors.
6.
The relay drop-out voltage will be measured once per operating cycle and the data examined for evidence of relay deterioration.
7.
Four undervoltage relays with integral timers per 4 KV bus. The relay output contacts are connected to form a one-out-of-two-twice coinci-dent logic matrix. With one relay inoperable, operation may preceed pro-vided that the inoperable relay is placed in the tripped condition within ene hour.
l 3.2-15 Amendment No.
58
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M TABLE 3.2-G a
INSTRUMENTATION THAT INITIATES RECIRCULATION PUMP TRIP g
E Minimum Number of Number of Instrument Operable Instrument Channels per Trip Instrument Trip Level Setting Channels Provided Action System (1)
By Design 1
(ATWS) Reactor liigh
- 6 1120 psig 4
(2)
Pressure F
1 (ATWS) Reactor Low Water h -38.5 in. in-4 (2)
E
'?
Level dicated level y
E$
1 (EOC)
RPT Logic N/A 2
(3) 1 (E0C) RPT System (Response Timel 1
- msec (4) 2 (3)
NOTES FOR TABLE 3.2-G 1.
Whenever the reactor is in the RUN Node, there shall be one operable trip system for each parameter for operating recirculation pump.
If this cannot be met, the indicated action shall be taken.
2.
Reduce power and place the mode selector-switch in a mode other than the RUN Mode.
3.
Two E0C RPT systems exist, either of which will trip both recirculation pumps. The systems will be individually functionally tested monthly.
If the test period for one RPT system exceeds 2 consecutive hours, the system will be declared inoperable.
If both RpT systems are inoperable or if 1 RPT system is inoperable for more than 72 consecutive hours, an orderly power reduction shall be initiated and the reactor power shall be less than 85% within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
1 4.
This response time is from initiation of turbine control valve fast closure to actuation of the breaker auxiliary contact.
~
- To be determined by testing after installation.
(yalue to be design requirement for breaker opening less difference between cycle time for loaded vs. unloaded breaker.)
TABLE 4.2-D R
MItIIMUM TEST Af3D CALIBRATIOtl FREQUEriCY FOR CSCS R
j Instrument Calibration Instrument Inut rnmenet Channel Functional Test (9)
Frequency (9)
Check 1)
Itenctor Water I.evel (1)
Once/3 months Cnce/ day 5
- 2) luyvull Pressure (1)
Once/3, months None 3)
Reactor Pressure (1)
Once/3 months None
- 4) Auto Sequencing Timors N/A Once/ operating None Cycle
Once/3 months None Pressure Interlock o
Y
- 6) Trip System Bus Power Monitors (1)
Not Applicable None
$n o.
7)
Recirculation System d/p (1)
Once/3 months Once/ day
- 0) Core Spray Sparger d/p (1)
Once/3 months once/ day 9)
Steam Line Illgh Flow (llPCI & RCIC)
(1)
Once/3 months None
(1)
Once/ operating Once/ day Cycle
- 11) IIPCI and RCIC Steam Line Low Pressure (1)
Once/3 months None
- 12) IIPCI Suction Source Levels (1)
Once/3 months None
- 13) a.
4KV Emergency Power System Once/ operating Once/ operating Voltage Relays Cycle cycle None b.
4KV Emergency Power System Once/operatin9 None Voltage Relays (Degraded Voltage)
Once/ month cycle
- 14) Instrument A.C. and battery bus (1)
Once/ operating None undoavoltage relays cycle
TABLE 4.2-G MINIMUM TEST AND CAllBRATION FREQUENCY FOR RECIRCULATION PUMP TRIP f
(ATWS) l a
Instrument Channel _
Instrument Functional Check Calibration Frequency Reactor liigh Pressure Once/ refueling cycle Once/ refueling cycle E
Reactor low Water Level Once/ refueling cycle Once/ refueling cycle Logic System Function Test Frequency J
Recirculation Pump Trip Once/ refueling cycle E'
P';'
R.
(E0C) f m*
Instrument Channel Functional Check Calibration. Frequency Instrument Check Response Time RPT Initiate Logic Once/ Month N/A N/A N/A RPT System Once/ Operating Cycle N/A N/A Once/ Operating Cycle l
l l
i I
DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS' I
must be taken out of power functionally tested once per operation operating cycle in conjunction with specification 4.7.A.6.a.
Should one of the two H2 or 02 analyzers serving the drywell or suppression pool be found inoperable, the remaining ana-lyzer of the same type serving the same compartment shall be tested for operability once per week until the defective ana-lyzer is made operable.
7.
Orywell-Suppression Chamber 7.
Drywell-Suppression Chamber Differential pressure Differential pressure a.
Differential pressure between a.
The pressure differential be-the drywell and suppression tween the drywell and suppres-chamber shall be maintained at sion chamber shall be recorded
[
equal to or greater than 1.10 at least once each shift.
psid except as specified in (1) and (2) below:
(1) Within the 24-hour period sub-sequent to placing the reactor in the Run Mode following a shutdcwn', the differential shall be established. The differential may be decreased l
to less than 1.10 psid 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a scheduled shutdown.
~
(2) This differential may be de-l creased to less than 1.10 psid for a maximum of four hours during required operability testing of the HPCI system pump, the RCIC system pump, the drywell-pressure suppres-sion chamber vacuum breakers, and the suppression chamber to reactor building vacuum breakers.
b.
If the differential pressure of specification 3.7.A.7.a cannot be maintained, and the differential pressure cannot be restored within the subsequent six (6) hour period, an orderly shut-down shall be initiated and the reactor shall be in the Cold Shutdown condition 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. 58 '
3.7-14 l
DAIC-1 Due to the nitregen additien, the pressure in the contai==ent after a LOCA could possibly increase with ti=e.
Under the worst expected '
conditions the contain=ent pressure will reach 30 psig in cyproxt=ately
)
70 days. If and when that pressure is reached, venting from the cen-tai =sent shall be manually initiated. ' The venting path vill be through e 4 *ze the offsite dose.
the Standby Cas Treatment Systes in order to m l
To11 cuing a LOCA, periodic operation of the dryvell and torus sprays may be used to assist the natural convection and diffusien =ixing of 1
In conjunction with the Mark I Contain=ent Short Ter= Program, a plant l
unique analysis was perfor=ed which de=onstrated a factor of safety of at 1
1 least two for the weakest ele =ent in the suppression cha=ber support system and attached piping. The maintenance of.a drywell suppression chamber differential pressure of 1.10 psid and a suppression cha=ber water level corresponding to a downconer submergence range of 3.33 to 3.00 feet vill assure the integrity of the suppression r hamber when subjected to post-LOCA suppression pool hydrodynamic forces. Design details are described in References 5 and 6.
7.
Standby Gas Treatment System and Secondary centat= ment The secendary contai=ent is designed to =i-' ':e any greund level release of radioactive =aterials which =ight result fr== a sericus accident. The reacter building provides sec=ndary centat=ent during reactor operatien, when the d: r.iell is sealed and in service; the reaccer building provides pri=a-f containment when the reactor is shut down and the dryvell is Amendment No. 58 3,7_41
9 l
SUR"EILIANCE !!EOUIREN2NTS LIE TI C CCNDITTONS 70:1 CPE7J. TION chargers for the 125 volt station b.
Once per operating cycle the batteries, and one of the two condition under which the 250 volt battery chargers shall diesel-generator is required will be simulated and a test be operable.
conducted to demonstrate that 4.
The e=crgency 4160 volt buses 1A3 it will start and accept the and 1A4, and 480 volt buses 133, emergency load within the spec-134,139 and 1320 shall be ener-ified time sequence. The diesel-gized and operable.
generator shall be operated loaded for a minimum of 5 minutes. An interruption of the diesel-generator will then be si=clated to demonstrate that upon subsequent reconnec-tion, it will again accept the j
emergency load within the specified time sequence. The results shall be logged, The quantity of diesel fuel c.
available shall be logged monthly and after each use of the diesels.
d.
Once a month a sample of diesel fuel shall be checked for viscosity, water and sediment. The values for viscosity, water and sediment shall be within the acceptable ILuits specified in Table 1 of ASIM D975-68 and logged.
Each diesel-generator shall be e.
given an annual inspection in accordance with instructions i
based on the manufacturer's recommendations.
f.
A sa=ple test and record shall be made of each oil delivery before it is placed in the storage tank.
2.
Unit 3atteries a.
Every week the specific gra.ity, the voltage and ce=perature :f the pilot cell and everall battery voltage shall be
=easuied and logged.
Amendment No. 58 3.3-2
DAEC-1 4,8 DASES:
i The monthly tests of the diesel-generators are conducted to demonstrate satis factory system performance and operability.
The test of the automatic starting circuits will prove that each diesel will receive all automatic start signals.
The loading of each diesel-generator is conducted to demonstrate proper operation at maximum expected emergrincy loading and at equilibrium operating conditions.
Generator experience at other generator stations indicates that the testing frequency l
is adequate to assure a high reliability of operation should 4
l the system be required.
I
[
Each diesel-generator has two independent starting air sucoly systems.
one consists of a motor driven air compressor which automatically recharges two air receivers and the other consists of a diesel driven air compressor which is manually operated to recharge a third air receiver.
During the monthly check of the diesel-generator, both air start systems will be checked for proper operation.
Following the tests (at least monthly) or other operation of the units, the L fuel volume re:naining in the diesel oil storage tank will be checked.
3.f8-11 April 197!.
9
DAEC-1 At the end of the monthly loads test of the diesel-generator, the fuel oil transfer pump will be operated to refill the day tank and to check the operation of this pump. The day tank level indicator and alarm switches and fuel oil transfer pump control switches will be checked at this time.
J l
1 The test of the diesels once each oper; ting cycle will be more comprehensive l
in that it will functionally test the system; i.e.,
it will check starting and closure of breakers and sequencing of loads. The units will be started by simulation of a loss-of-coolant accident. In addition, a loss of normal power condition will be imposed to simulate a loss of off-site power. The timing sequence will be checked to assure proper loading in the time re-quired. After operating for a minimrm of 5 minutes, an interruption of the diesel-generator will be simulated. Af ter a load shed, the subsequent re-connection will be checked to assure that loading of the diesel-generator is again through the load sequencer in the time required. Periodic testa check the capability of the units to start in the required time and to deliver the expected emergency load requirements. Periodic testing of the various components plus a functional test each operating cycle are sufficient to maintain adequate reliability.
Logging the diesel fuel supply after each operation (at least monthly) assures that the minimum fuel sugply requirements will be Amendment No.
58 3.8-12 1
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