ML20032A461
| ML20032A461 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/23/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20032A460 | List: |
| References | |
| DPR-51-A-060 NUDOCS 8110290620 | |
| Download: ML20032A461 (14) | |
Text
I 8
UNITED STATES 4
NUCLEAR REGULATORY COMMisslON y*
WASHINGTON, D. C. 20555
\\*'O /
ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 60 313 ARKANSAS NUCLEAR ONE - UNIT N0.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.60 License No. OPR-51 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Arkansas Pot 3r and Light Company (the licensee) dated February 20, 1981, as supplemented May 29, 1981, and October 8,1981, 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 facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comissi,:n; 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 ccnducted 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.
ine 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-51 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.60, are hereby-incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
T'ais license amendment is effective as of the date of its
'ssuance.-
FOR THE NUCLEAP REGULATORY COMMISSION r
n
(. f, '
hn)F.-Stolz, Chief
/
jeatingReactorsBrahh#4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 23, 1981
3-
.. A_TTACHMENT TO LICENSE AMENDMENT NO. 60 FACILITY OPERATING LICENSE NO. DPR-51.
DOCKET NO. 50-313 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.
-42a 43a 45b 45c 45d-(new page) 56 57 57a 72 72a-100 D
9 i
i
l 3.5.1.7.
The Decay Heat Removal' System iselation valve closure setpoints shall Le equal to or less than 340 psig for one valve-and equal to or less than 400 psig for the second valve in the suction line. The relief valve setting for the DHR system shall be equal to or less than 450 psig.
3.3.1.d
-The degraded voltage monitoring relay settings shall be as J
follows:
a.
The 4.16 XV emergency bus undervoltage relay setpoints shall be > 3115 VAC but < 3177 VAC.
b.
The 460 V emergency bus undervoltage relay setpoints shall be > 423 VAC but < 431 VAC with a time delay setpoint of 8 seconds +1 second.
l l
l l
i Amendment No.60
-42a-
I for protective action from a digital ESAS subsystem will not cLse that subsystem to trip. The fact that a module has been removed will be con-tinuously annunciated to the operator.
The redundant digital subsystem is still sufficient to indicate complete ESAS action.
The testing schemes of both the RPS and the ESAS enable complete system testing while the reactor is operating.
Each channel is capable of being tested independently so that operation of individual channels may be eval-uated.
The Automatic Closure and_ Isolation System (ACI) is designed to close the Decay Heat Removal System (DHRS) return line isolation valves when the Re ntor Coolant System (RCS) pressure exceeds a selected fraction of the 9dRS design pressure or when core flooding system isolation valves are opened. The ACI is designed to permit manual operation of the DHRS re-turn line isolation valves when permissive conditions esist.
In addition, the ACI is designed to disallow manual operation of the valves when per-missive conditions do not exist.
Power is normally supplied to the control rod drive mechanisms from two separate parallel 480 volt sources.
Redundant trip devices are employed in each of these sources.
If any one of these trip devices fails in the untripped state, on-line repairs to the failed device, when practical, will be made and the remaining trip devices will be tested.
Four hours is ample time to test the remaining trip devices and, in many cases, make on-ine repairs.
The Steam Line Break Instrumentation and Control System (SLBIC) is designed to automatically close the Main Steam Block valves and the Main Feedwater Isolation valves upon loss of pressure in either of the two main steam lines.
The SLSIC is also designed to be reset from its trip position only when the system is shut down or the Main Steam line pressure is below 650 psig.
The Degraded Voltage Monitoring relay settings are based on the short term startirg voltage protection as well as long term running voltage prctection.
The 4.16 KV undervoltage relay setpoints are based on the allowable starting j
voltage plus maximum system voltage drops to the motor terminals, which l
allows approximately 78% of motor rated voltage at the motor terminals. The j
460V undervoltage relay setpoint is based on long term motor voltage re-l quirements plus the maximum feeder voltage drop allowance resulting in a I
92% setting of motor rated voltage.
The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident. This capability is consistent with the recortrnendations of Regulatory Guide 1.97 " Instrumentation for Light-Water-Cooled Nucitar Power Plants to Assess Plant Conditions During and Folicwing an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recomendations."
(j
-REFERENCE FSAR, Section 7.1 l
l Amendment No. g, 60 43a-
,t
G-
,wa Table 3.5.1-1 (Cont'd) h' OTilER SAFETY RELATED SYSTEMS l
2 3
4 5
No. of Operator action channels Hin.
Min.
1f conditions of
~
E No. of for sys-operable degree of column 3 or 4 functional Unit channels tem trip ~
channels redundancy cannot be met M
-s 8
2.
Steam line break instrumenta-tion control system (SLBIC).
(a) SLBIC Control & Logic
~
Channels 2
1 2
1 Notes 9, 5 3.
- Pressurizer level channels 3
N/A 2
1 Note 10 L
4.
Emergency feedsater flow
- 1 0
Note 10 g
channels 2/S.G.
N/A 5.
RCS subcooling margin monitors 2 H/A 1
0 Note 10 6.
Electromatic relief valve flow monitor 2
N/A 1
0 Note 11 7.
Electromatic relief block valve position indicator 1
N/A 1
0 Note 12 8.
Pressurizer code safety valve flow monitors 2/ valve
.N/A 1/ valve 0
Not,e 10 9.
Degraded Voltage Monitoring a.
4.16 KV Emergency Bus Undervol tage 2/ Bus I/ Bus 2/ Bus 0
Note 14 b.
4160 V Emergency Bus Undervol tage
- l/ Bus 1/ Bus 1/ Bus 0
Notes 13, 14
- Two undervoltage relays per bus are used with a coincident trip logic (2-out-of-2)
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3.7 Auxiliary Electrical Systems Applic.bility Applies to the auxiliary electrical power systems.
Objectives-To specify conditions of operation for plant station power necessary' to ensure safe reactor operation and ccmbined availability of the engineered safety features.
Soecifications 3.7.1 The reactor shall not be heated or maintained above 200F unless the following conditions are met (except as permitted by para-graph 3.7.2):
A.
Any one of the following combinations of power sources operable:
1.
Startup Transformer No. 1 and Startup Transformer No. 2.
2.
Startup Transformer No. 2 and Unit Auxiliary Transformer provided that the latter one is connected to the 22KV line from the switchyard rather than to the generator bus.
B.
All 4160 V switchgear, 480 V load centers and 480 V motor control centers in both of the ESAS distribution systems are operable and are being powered from either,one of the two startup transformers or the unit auxiliary transformer.
C.
Both diesel generator sets are operable each with:
1.
a separate day tank containing a minimum of 160 gallons of fuel, 2.
a separate emergency storage tuk containing a minimum of 138 inches (20,000 gallons) of fuel, 3.
a separate fuel transfer pump, and l
4.
a separate starting air compressor.
D.
Both station batteries are operable and each is capable of supplying power to the 125V d-c distribution system. At l
least 2 of the 3 battery chargers are operable.
f E.
A least 2 of 3 d-c control power sources to the 125V d-c l
switchyard distribution system are operable.
F.
The off-site power undervoltage and protective relaying in-terlocks associated with required startup transformer power i
sources shall be operable per Table 3.5.1-1.
G.
The selective load-shed features associated with Startup l
Transformea No. 2 shall be operaole if, selected for auto transfer.
Amendment No. JE,60.
l 3.7.2 A. The specifications in 3.7.1-may be modified to allow one of the following conditions to exist after the reactor;has been heated above-200F.
Except as indicated in the following conditions, if any of these_ conditions are not met, a hot shutdown shall be initiated within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
If the condition is not cleared with-in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor.shall be brought to cold shutdown.within
- an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B..In the event that one of the offsite power sources specified in 3.7.1.A (1 or 2) is inoperable,-reactsr operation may continue for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.if the availability of the diesel generators is immediately verified.
C. Either one of the two diesei generators may be inoperable for up
~
to 7 days in any month provided that during such 7 days the opera-bility of the remaining diesel generator is demonstrated immedi-ately and daily _thereafter, there are no inoperable ESF compenents associated with the operable diesel generator, and provided that the two sources of off-site: power specified in 3.7.1.A(1) or 3.7.1.A(2) are available.
D. Any 4160V, 480V, or 120V switchgear, load center, motor control center, or distribution panel in one of the two ESF distribution systems may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, provided that the
-operability of the diesel generator associated with the operable ESF distribution system is demonstrated immediately and all of the components of the operable distribution system are operable.
If the.ESF distribution system is not returned to service at the end of the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, specification 3.7.2. A shall apply.
E. Two station battery chargers may be inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, after whicn specification 3.7.2. A shall apply.
F. One of the two station batteries and the associated distribution system may be inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> orovided that there are no inoperable safety related components associated with the remaining station battery which are redundant to the inoperable station battery and the operability of the diesel generator is verified-immediately.
If the battery is not returned to service at the end of the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, specification 3.7.2. A shall apply.
G. Two control power sources from the plant to the switchyard and the attendant distribution system may be inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, after which specification 3.7.2. A'shall apply.
H. If the requirements of specification 3.7.1.G cannot be met, either:
(1) place all Startup Transformer No. 2 feeder breakers in'" pull-to-lock" within l', hour, restore the inoptrable interlocks to operable status within 30 days or submit a special report pur-suant to specification 6.12.3.2 outlining cause of the failure, proposed corrective action and schedule for implementation; or The provisions of specification 3,0.4 are not applicable NOTE:
(2) apply the action requirements of Table 3.5.1-1, Note 14.
Amendment No. 60.
3.7.3 Any degradation beyond those conditions specified in 3.7.1 and 3.7.2 shall be cause to initiate a reportable occurrence report per speci-i fications 6.5 and 6.12.
Bases Theelectricalsystemisdesignedtobeelectricallysekf-sufficientand provide adequate, reliable power sources for all electrical equipment during'startup, normal operation, safe shutdown and handling of all emer-gency situations. To prevent the concurrent loss of all auxiliary power, the various sources of power are independent of and isolated from each-other.
In the event that the offsite power sources specified in 3.7.1.A (1 or 2) are inoperable, the required capacity of one emergency storage tank plus one day tank (20, 160 gallons) will be sufficient for not less than three and one-half days operation for one utesei generator loaded to full capa-city.
(ANO-1 FSAR 8.2.2.3) The underground emergency storage tanks are gravity fed from the bulk storage tank and are normally full, while the day tanks are fed from transfer pumps which are capable of being cross connected at their suction and discharges and automatically receive fuel oil when their inventory is less-than 180 gallons. Thus, at least a seven day total diesel oil inventory is available onsite for emergency diesel generator operation during complete loss of electric power conditions.
Technical Specification 3.7.2 allows for the temporary modification of the specifications in 3.7.1 provided that backup system (s) are operable with safe reactor operation and combined availability of the engineered safety features ensured.
Technical Specifications 3.7.1.F and 3.7.1.G provide assurance that~the 4:
Startup Transformer No. 2 loads will not contribute to a sustained.de.
graded grid voltage situation. This will protect ESF equipment from damage caused by sustained undervoltage.
1 l
l l
Amendment No. 75,60
-57a-e I
.~.
4 F
Table 4.1-1(Cont'd) i 3
}
a 1
3 Ci d'!"cl Ec55.r,1ytlon Check Test Calibrate t
J O
RcMs l (
30.
Ilecay lleat 1(emoval 5(1)(2)
M(1)(3)
R System isolation Valve (1) Includes RCS Pressure Analog Channel Automatic Closure and w
Interlock Systosa (2) includes CFT Isolation Valve Position t
m (3) Shall Also Be Tested During Refuel-o, ing Shutdown Prior to Repressuriza-l tion at a pressure greater than 300 but less than 420 psig.
1 1
- 31. Turbine Overspeed Trip M
R M
)
Hechanism 4
- 32. Sicam 1.ine lircak W
Q R.'
~
TJ lustrima:ntatinn and Control System logic j
Test & Control Circuits 33 Olesel Generator M
Q M
Protective Itclavin 3 Starting interlocks And Circuitry
- 34. Of f-site Power thidervoltage W
R (1)
R (1)
(1) Shall be tested during refueling shutdown And Protective Relaying to demanstrate selective load shedding Interlocks And Ch ccitry interlocks function during manual or auto-matic transfer of Unit 1 auxiliary loads to Startup Transformer No. 2'.
- 35. Dorated Water Storage W
M R
Tank Level Indicator
- 36. Itcactor Trip Upon Loss M
PC M
of Main feedwater Cir-cultry i
1
Id.I'!"._. 4.:.I~.!_1Cojt ',jl),
t F
' y Cliannel llescription Clicck
_1cs t Calibrate Remarks-i g
r+ -
- 37. Doric Acit! Ailtlition Tank 2
P
- a. Level Channel flA flA R
- b. Temperature Cliannel M
llA R
'(
i
- 30. Degraded Voltage Monitoring W
R R
tR
. ' 39. Soditan Ilydrox ide Tank ilA flA R
I.evel Indicator'
- 40. Incore ticutron Detectors M(1) flA NA
'(1)Checkfunctioning
- 41. Imergency Plant Radiation M(1) ilA it (1) Battery Clicck ins i nnnents y
o,
- 42. lleactor Irlp Upon ilA PC flA lurlaine Irlp Circuitry
- 43. Strong Hollon Accelcograplis Q(1)
NA Q
(1)DatteryCheck
- 44. ESAS Hanual Trip functions
- a. Swltclies & Logic liA P
tlA
- b. I.ngic flA H
iia
- 45. Reactor Manual Trip flA P
NA
- 46. Reactor Dullding Stanp Level NA NA R
^~
4.6 AUXILIARY ELECTRICAL SYSTEM TESTS
'Apolicability Applies to the periodic testing and surveillance requirements of the auxil-iary electrical system to ensure it will respond promptly and properly when -
required.
Soecification-4.6.1 Diesel Generators
- 1. Each diesel generator shall be manually started each month and demonstrated to be ready for loading within 15 seconds. -The signal initiating the start of the diesel shall be varied from one test to another (start with handswitch at control room panel and at diesel local control panel) to verify all starting circuits are operable. The generator shall be synchronized from the control room and loaded to full rated load and allowed to run until diesel generator operating temperatures have stabilized.
- 2. A test shall be conducted once every 18 months to demonstrate the ability of the diesel generators to perform as designed by:
a.
simulating a loss of off-site power, b.
simulating a loss of off-site power in conjunction with an ESF s;gnal, c.
simulating interruption of off-site power and subsequent re-connection of the on-site power source to their respective busses, and d.
operating the diesel generator for g 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after operating temperatures have stabilized.
- 3. Each diesel generator shall be given cn inspection once every 18 months following the manufacturer's recommendations for this class of standby service.
- 4. Du;ing the monthly diesel generator test specified in paragraph 1 above, the following shall be cerformed:
The diesel generator starting air compressors shall be checked a.
for operation and their ability to recharge the air receivers, b.
The diesel oil transfer pumps shall be checked for operability and their ability t transfer oil to the day tank.
c.
The day tank fuel level shall be verified.
d.
The emergency storage tank fuel level shall be verified.
Amendment No. JE, 25,60
-100-e'
-