ML20080J137
| ML20080J137 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/19/1983 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20080J119 | List: |
| References | |
| TAC-42218, TAC-42219, TAC-43684, TAC-43685, TAC-53327, TAC-53328, NUDOCS 8309260206 | |
| Download: ML20080J137 (15) | |
Text
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ATTACHE NT 2 NRC DOCKET 50-321 OPERATING LICENSES DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 SCRAM DISCHARGE SYSTEM TECHNICAL SPECIFICATIONS The proposed change to the Technical Specifications (Appendix A to the Operating License) would be incorporated as follows:
Remove Page Insert Page 3.1-4 3.1-4 3.1-7 3.1-7 3.2-16 3.2-16 3.2-17 3.2-17 3.2-40 3.2-40 3.3-7a 3.3-18 3.3-18 3.3-18a 4
f i
B309260206 030919
'~
PDR ADOCK 05000321 P
Table 3.1-1 (Continued)
Operable Channels Scram Required Per Source of Scram Signal is Required 4
Number Trip System
'Ib Be Operable Except as Indicated (a)
Source of Scram Trip Signal (b)
Scram Trip Setting Below 5
High Drywell Pressure 2
<2 psig Not required to be operable when primary containment integrity is not required.
May be bypassed when necessary during purging for containment inerting or deinerting.
4 6
Reactor Water Inw Level 2
>l2.5 inches (LLl) (Narrow Range) 7 Scram Discharge V@une High Permissible to bypass (initiates j
F High level control rod block) in order to 7
- a. Float Switches 2
471 gallons reset RPS when the Mode Switch is b.'Ihermal Level sensors 2
{71 gallons in the REE1JEL or SH(JILOW position.
8 APRM Flow Referenced 2
S 4 0.66W+54%
Neutron Flux (Not to exceed 117%)
Tech Spec 2.1.A.l.c Fixed High Neutron 2
S 4_120% Power Flux Tech Spec 2.1.A.l.c Inoperative 2
Not Applicable An APRM is inoperable if there are i
less than two LPRM inputs per f
level or there are less than 11 LPRM irputs to the APRM channel 4
4 r-
Table 4.1-1 Reactor Protection System (RPS) Instrumentation Functional Test, Functional Test Minimum Frequency, and Calibraton Minimum Frequency Scram Instrument Functional Test Number Group Minimum Frequency Instrument Calibration (a)
Source of Scram Trip Signal (b)
(c)
Minimum Frequency 1
Mode Switch in SHUIDOkN A
Once/Operatiry Cycle Not Applicable 2
Every 3 months Ibt Applicable 3
IRM High High Flux C
Cnce/ Week during refueling Once/ Week and Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of Startup (e)
Inoperative C
Once/ Week during refuel Once/ Week and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of F
Startup (e)
Y 4
High Reactor Pressure A
Once/ Month (f)
Every 3 nonths 5
High Drywell Pressure A
Once/ Month (f)
Every 3 :aonths 6
Reactor Water Iow Level (LLl)
A Once/ Month (f) (g)
Every 3 months 7
Scram Discharge Volume High High Ievel a.
Float Switches A
Once/ Month (f)
(h) b.
'Ibermal Level Sensors B
Once/ Month (f)
Once/ Operating Cycle 8
APRM Fixed High Flux B
OncefWeek (e)
Wice/ Week Inoperable B
Once/ Week (e)
'IVice/ Week Downscale B
Once/ Week (e)
Twice/ Week Flow Reference B
Once/ Week (f)
Once/ Operating Cycle 15% Flux C
Within 24 Hours of Startup (e)
Once/ Week
Table 3.2-7 (Continued) l Required Operable Ref.
Trip Channels No.
Condition per Trip (a)
Instrument Nomenclature Systen (b)
Trip Setting Remarks 3
APIB1 Downscale 2 (e) 1 3/125 of full scale Not required while performing low power physics test at atmospheric pressure during or after refueling at power levels not to exceed 5 IWt.
12% Flux 2 (e)
< 12/125 of full scale This function is bypassed when the Mode Switch is placed in the RUN position.
i High Flux 2 (e)
< 0.66W + 42%
W is the loop recirculation flow rate in percent of rated. Trip y
level setting is in percent of rated y
power..Not required while performing g
low power physics tests at atmospheric 4
pressure during or after refueling at i
power levels not to exceed 5 MWt.
l j
4 RBM Inoperative 1 (e) (f)
Not Applicable Incperative trip produced by switch j
(g) (h) not in operate, circuit boards not in curcuit, fails to null, less than required number of LPRM irputs for l
rod selected.
Downscale 1 (e) (f)
> 3/125 of full scale (g) (h)
High Flux 1 (e) (f)
< 0.66W + 41%
W is the loop recirculation flow rate in percent of rated. Trip level setting is in percent of i
rated thermal power.
5 Scram High Water 1 (i)
< 18 gallons i
Discharge Level Volume 4
=.
l Notes for Table 3.2-7
- a.
%e column entitled "Ref. No." is only for convenience so - that a one-to-one relationship can l
be established between items in Table 3.2-7 and items in Table 4.2-7.
l b.
For the STARr & HOT STANDBY position ~of the Mode Switch, there shall be two operable or l
tripped. systems. for each potential trip condition.
If the requirements established by the i
column cannot be met for one of the two trip systems, the condition may exist for up to seven j
days provided that during that time the operable systems is functionally tested innediately.
and daily thereafter;. if this condition lasts longer than seven days, the system shall be~
triged.
If the requirements established by this column cannot be met for both trip systems, the systems shall be tripped.
c.
One of the four SRM inputs may be bypassed.
d.
The SRM and IRM blocks need not be operable in the Run Mode. % is function is bypassed when l
the Mode Switch is placed in the RUN position.
e.
The. APRM and RBM rod blocks need not be Operable in the Start and Hot Standby Mode (Except 4
12% APRM Rod Block) w l
f.
Not required while performing low power physics tests at atmospheric pressure durirg or after refueling at power levels not to exceed 5 s t, g.
This trip bypassed when reactor power is $30%.
h.
One channel of the RBM may be inoperative or bypassed if this cordition does not persist longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 30 day period.
l l
- i. This trip is Operable in Power Operation and Hot Standby Mode, and Refuel Mode when any l
control rod is withdrawn. Not applicable to control rods removed per specification 3.10.E.
Table 4.2-7 Check, Functional Test, and Calibration Minimum Frequerx.f for Neutron Monitoring Instrumentation Which Initiates Control Rod Blocks i
Ref.
Instrument Check Instrument Functional Test
. Instrument Calibration No.
Minimum Frequency Minimum Frequency Minimum Frequency (a)
Instrument (b)
(c)
(d) 1 Source Range Monitors Once/ day (f)
(g)
(SRM) 2 Intermediate Rarge Once/ day (f)
(g)
Monitors (IRM) i 3
Average Power Raryje Once/ Day (e)
Every 3 months Monitors (APRM)
Y g
4 Rod Block Monitor Once/ day (e)
Every 3 months (RBM)
~
5 Scram Discharge Volume N/A Every 3 months Once/ Operating Cycle 1
I l
Notes for Table 4.2-7 a.
The column titled "Ref. No." is only for convenience so that a one-to-one relationship can be established between items in Table 4.2-7 and items in Table 3.2-7.
b.
Instrument checks are not required when these instruments are not required to be operable or are tripped.
]
Ilowever, if instrument checks are missed, they shall be performed prior to returning the instrument to an operable status.
i
LIMITING COPOITION FOR OPERATION SLRVEILLANCE REQUIREMENTS 3.3.I Scram Discharge Volume Vent 4.3.I Scram Discharge Volume Vent and Drain Valves and Drain Valves During reactor power operation,
- 1. Valve Position Verification all scram discharge volume vent and drain valves shall be Each scram discharge volume vent operable.
If this specification and drain valve shall be verified cannot be met,-an orderly shut-to be in the open position
- at down shall be initiated and least once per 31 days.
the reactor shall be placed in the Hot Shutdown Condition
- 2. Valve Testing within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
a.
Each scram discharge volume vent and drain valve shall be operated through at least one complete cycle of full travel at least once per 92 days.
b.
At least once per 18 months, it shall be verified that the scram discharge volume vent and drain valves:
- 1. Close within 30 seconds after receipt of a signal for control rods
-to scram, and
~
- 2. Open when the scram signal is reset.
i,
- These valves may be closed intermittently for testing under administrative controls.
l I
3.3-7a l
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BAMS FOR LIMITItC CONDITIONS FOR OPERATION AND SUP/EILLANCE REQUIREMENTS 3.3.G.2.c. Shutdown Margin / Scram Time Testing (Continued) tion simulation switches provided in the RSCS for such purposes.
During the scram time testing, reactor conditions will be such that the reactor rod pattern will be in RSCS B group.
All A12 and A34 rods will be fully withdrawn, alternatively the rod pattern wlll be in RSCS group A and all B12 and 834 rods will be fully withdrawn.
To test A34 rods, it will be necessary to simulate all withdrawn B rods as being at the full in position, and for testing A12 rods, all A34 and all withdrawn B rods as being at the full in position.
The simulation of already withdrawn control rods in the 100% to 50% rod density range (Al2 and A34 or alternatively B12 and B34) as being full in to perform the individual rod test does not violate the intent of the RSCS since; (a) the single notch mode of rod withdrawal for rods in the 50%
density to preset power level will remain in effect until the preset power level has been achieved and the test procedure will require that this be verified; (b) no group B rods can be selected either for withdrawal or insertion during the time that an A12 or A34 rod is fully inserted or is simulated as being in the fully inserted position (similarly for the A group rods when the B sequence is chosen for startup and (c) all rod position simulation switch operations will be verified by a second independent check.
H.
Shutdown Reouirements Should circumstances be such that the Limiting Conditions for Operation as stated in Specifications 3.3. A through 3.3.G cannot be met, an orderly shutdown shall be initiated and the reactor 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 />.
I.
Scram Discharge Volume Vent and Drain Valves The scram discharge volume vent and drain valves are required to be OPERABLE, so that the scram discharge volume will be available when needed to accept discharge water from the control rods during a reactor scram and will isolate the reactor coolant system from the containment wh3n required.
J.
References 1.
FSAR Section 3.4, Reactivity Control Mechanical Design 2.
FSAR Section 3.5.2, Safety Design Bases 3.
FSAR Section 3.5.4, Safety Evaluation 4.
FSAR Section 3.5, Control Rod Drive Housing Supports 3.3-18
i BASES FOR LIMITIPO C0tOITIONS FOR OPERATION AND SURVEILLANCE REQUIEMENTS J.
References (Continued) 5.
FSAR Section 14.4.3, Loss-of-Coolant Accident 6.
FSAR Section 14.4.2, Control Rod Drop Accident 7.
FSAR Appendix G, Plant Nuclear Safety Operational Analysis 8.
C. J. Paone, R.
C.
- Stirn, J.
A.
Woolley, " Rod Drop Accident Analysis for Large Boiling Water Reactcrs", NEDO-10527 Class I, March, 1972.
9.
R.
C.
- Strin, C.
J.
- Paone, R.
M.
Young, " Rod Drop Accident Analysis For Large Boiling Water Reactors Addendum ib.
1 Multiple Enrichment Cores With Axial Gadolinium:, Supplement 1 EDO-10527 Class I, July 1972.
- 10. FSAR Section 3.6.5.4, Control Rod Worth
- 11. FSAR Section 3.6.6, Nuclear Evaluations i
l 3.3-18a 4
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4' ATTACHENT 3 NRC DOCKET 50-366 OPERATING LICENSES NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 SCRAM OISCHARGE SYSTEM TECHNICAL SPECIFICATIONS The' proposed-change to the Technical Specifications (Appendix A to the Operating License) would be incorporated as follows:
Remove Page.
Insert Page I
2-5 2-5 3/4 1-21 B 3/4 1-5 3/4 3-3 3/4 3-3 3/4 3-8 3/4 3-8 4
4 i
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l TABLE 2.2.1-1 (Continued)
S REACIOR PROIECTION SYSTEM INSTRIPElfrATICN SEIPOINTS 5[
FIPCTIONPL UNIT TRIP SETPOINT ALIDWABLE VALUES 8.
Scram Discharge Volume Water Ievel - High
< 57.15 gallons 4 57.15 gallons (2Cll-N013A,B,C,D and 2Cll-N060A,B,C,D)
~
l 9.
Turbine Stop Valve - Closure i 10% closed 3 10% closed (NA)
- 10. Turbine Control Valve Fast Closure, Trip Oil Pressure-Irw 1 00 psig 3 600 psig 6
(2C71-N005A,B,C,D)
- 11. Reactor Mode Switch in Shutdown NA NA l
Position y
(NA) w l
- 12. Manual Scram NA NA l
l l
t l
I i
i i
l l
i
REACTIVITY CONTROL SYSTDS 3/4.1.6 SCRAM DISCHARGE VOLINE VENT AND DRAIN VALVES LIMITING CONDITION EDR OPERATION 3.1.6.1 All scram discharge volume vent and drain valves shall be OPERABLE.
APPLICABILITY: Conditions 1 and 2.
ACTION: With any scram disch. ige volume vent or drain valve inoperable, be in at least HOP SIUIDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILINCE REQUIREMENTS 4.1.6.1 The scram discharge volume vent and drain valves shall be demonstrated OPERABLE by:
a.
At least once per 31 days verifying each valve to be open*.
b.
At least once per 92 days cycling each valve through at least one complete cycle of travel.
c.
At least once per 18 months, by verifying that the drain and vent valves:
1.
.Close within (30) seconds after receipt of a signal for control rods to scram, and 2.
Open when the scram signal is reset.
- These valves may be closed intermittently for testing under administrative controls.
HATG - UNIT 2 3/4 1-21 e
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r REETIVITY CONTR% SYSTD4_5 BASES 3/4.1.6 SCRAM DISCHAPGE V1tNE VENT AND DRAIN VALVES The scram discharge volume vent and drain valves are required to be OPERABLE so that the scram discharge volume will be available when needed to accept discharge water from the control rods during a reactor scram and will isolate the reactor coolant system from the containment when-required.
HNIQI - UNIT 2 B 3/4 1-5
TABLE 3.3.1-1. (Continued)
Yg REAC'IOR PROTECTION SYSTEM INSTRIMNTATION, m
I APPLICABLE NN c
OPERATIONAL OPERABIE CHAT @EIS
.h MJtCTIONAL UNIT CONDITIONS PER TRIP SYSTEM (a)
ACTION 8.
Scram Discharge Volume Water Level - High (2C11-N013A,B,C,D) 1, 2, 5(h) 2 4
Level - High (2Cll-N060A,B,C,D) 1, 2, 5 2
4 l 9.
Turbine Stop Valve - Closure (NA) 1(i) 4 (k) 7
- 10. Turbine Control Valve Fast Closure, Trip' Oil Pressure - Iow 1(i) 2(k) 7 (2C71-N005A,B,C,D)
.11.
Reactor Mode Switch in Shutdown Position (NA) 1,2,3,4,5 1
8
- 12. Manual Scram (NA) 1,2,3,4,5 1
9
TABLE 4.3.1-1 (Continued)
REACIOR PROIILTICE SYSITM INSIRIMNTATION SURVEILIRCE REQUIRDENTS N*
CHANNEL OPERATIONAL CHA MEL MJtCTIONAL CHANNEL CONDITIONS IN WICH h
FUtCTIONAL UNIT CHECK TEST CALIBRATION SURVEILIRCE REQUIRED s
w 9.
Turbine Stop valve - Closure NA M
R(h) 1
- 10. Turbine Control Valve Fast Closure, Trip Oil Pressure -
Low NA M
R 1
- 11. Reactor Mode Switch in Shutdown NA R
NA 1,2,3,4,5 Position
- 12. Manual Scram NA M
NA 1,2,3,4,5 a.
Neutron detectors may be excluded from CHANNEL CALIBRATION.
[
b.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.
c.
The APRM, IRM and SRM channels shall be compared for overlap during each startup, if not performe.
within the previous 7 days, d.
When changing from CONDITION 1 to CONDITION 2, perform the required surveillance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering CONDITION 2.
e.
This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during CONDITION 1 when 'IHERMAL POWER - 25% of RATED 'IHERMAL POWER.
Adjust the APRM channel if the absolute difference 2%.
Any APRM channel gain adjustment made in ccrnpliance with Specification 3.2.2 shall not be' included in determinirg the absolute difference, f.
This calibration shall consist of the adjustment of the APRM flow referenced simulated thermal power channel to conform to a calibrated flow signal.
g.
'Ihe LPRM's shall be calibrated at least once per 1000 effectiw full power hours (EFPH) using the TIP system, h.
Physical inspection and actuation of switches for instruments 2Cll-N013A,B,C,D i.
Instrument alignment using a standard current source.
- j. Calibration using a standard radiation source.