ML20214E956
| ML20214E956 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/17/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | City of Dalton, GA, Georgia Power Co, Municipal Electric Authority of Georgia, Oglethorpe Power Corp |
| Shared Package | |
| ML20214E958 | List: |
| References | |
| NPF-05-A-069, TAC 55543 NUDOCS 8611250149 | |
| Download: ML20214E956 (25) | |
Text
_-
/
4 UNITED STATES 8'
1 NUCLEAR REGULATORY COMMISSION 4
g WASHINGTON. D. C. 20555
\\..... f" GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT N0t 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.69 License No. NPF-5 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated April 23, 1984 as superseded July 18, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations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 conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 common 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 Commission'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. NPF-5 is hereby amended to read as follows:
8611250149 861117 i
PDR ADOCK 05000366 l
P PDR l
4
.e-..-
(2) Technical Specifications
~
The Technical Specifications contained in Appendices A and B, as revised through Amenment No. 69, are
~
hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
s 3.
This iicense amendment is effective as of its date 9f issuance and shall be implemented witnin 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f
4/
!J Daniel R. Muller, Director BWR Project Directorate #2 Division of BL!R Licensing i
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 17, 1986 i
e
o ATTACHMENT TO LICENSE AMENDMENT 110.69 FACILITY OPERATING LICENSE N0. NPF-5 DOCKET NO. 50-366 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendr.ient number and contain a vertical line indicating the area of change. The overleaf pages are provided for convenience Remove Insert V
V I
VI VI 3/4 3-2 3/4 3-2 3/4 3-3 3/4 3-3 3/4 3-5 3/4 3-5 1
3/4 3-66*
3/4 3-67*
3/4 3-68*
,3/4 3-69*
3/4 3-70*
r 3/4 3-71*
3/4 3-72*
3/4 3-73*
1 3/4 3-74*
3/4 3-75*
f B 3/4 3-Sa si B 3/4 3-5b L
- Page added 1
I
M INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUTREMENTS-SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION 3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION 3/4 3-24 3/4.3.4 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION 3/4 3-33 3/4.3.5 CONTROL R00 WITHDRAWAL BLOCK INSTRUMENTATION 3/4 3-37 3/4.3.6 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-43 Seismic Monitoring Instrumentation 3/4 3-47 Remote Shutdown Monitoring Instrumentation 3/4 3-50 Post-Accident Monitoring Instrumentation 3/4 3-53 Source Range Monitors 3/4 3-56 Traversing Incore Probe System 3/4 3-57 Chlorine, Detectors 3/4 3-58 Fire Detection Instrumentatip, 3/4 3-59 Radioactive Liquid Effluent Instrumentation 3/4 3-60a Radioactive Gaseous Effluent Instrumentation 3/4 3-60f 3/4.3.7 TURBINE OVERSPEED PROTECTION SYSTEM 3/4 3-61 3/4.3.8 DEGRADED STATION VOLTAGE PROTECTION INSTRUMENTATION 3/4 3-63 3/4.3.9 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION 3/43-66 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops 3/4 4-1 HATCH-UNIT 2 V
Amendment No. 27, AB, 69
l INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
'~
SECTION pAGE REACTOR COOLANT SYSTEM (Continued)
Jet Pumps 3/4 4-2 Idle Recirculation Loop Startup 3/4 4-3 3/4.4.2 SAFETY / RELIEF VALVES 3/4 4-4 3/4 4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems 3/4 4-5 Operational. Leakage 3/4 4-6 1
3/4.4.4 CHEMISTRY 3/4 4-7 3/4.4.5 SPECIFIC ACTIVITY 3/4 4-10 3/4.4.6 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System 3/4 4-13 Reactor Steam Dome 3/4 4-18 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES 3/4 4-19 3/4.4.8 STRUCTURAL INTEGRITY 3/4 4-20 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 HIGH PRESSURE COOLANT INJECTION SYSTEM 3/4 5-1 3/4.5.2 AUTOMATIC DEPRESSURIZATION SYSTEM 3/4 5-3 3/4.5.3 LOW PRESSURE CORE COOLING SYSTEMS Core Spray System 3/4 5-4 Low Pressure Coolant Injection System 3E45-7 3/4.5.4 SUPPRESSION CHAMBER 3/4 5-9 HATCH-UNIT 2 VI Amendment No. AB, 69
l l
-___._: ;,,.m, ;__,_,,,,,, a _
w 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECT 10h SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERAELE with the REACTOR PROTECTION SYSTEM RESP 0 SE TIME as shown in Table 3.3.1-2.
Set points and interlocks. are given in Table 2.2.1-1.
APPL:CASILITY: As shown in Table 3.3.1-1.
ACTION:
With the reouirements for the minimum number of OPERAELE channels not a.
satisfied for one trip system, place at least one inoperable channel l
in the tripped condition within one hour, g
b.
With the requirenents for the minimum number of OPERAELE channels not satisfied for both trip systems, place at least one inoperable channel in at least one trip system
- in the tripped condition within one hour and take the ACTI0t required by Table 3.3.1-1.
2 The provisions of Specification 5.0.3 are not applicable in CPERA.
c.
TI0liAL ColOITION 5.
SUR1'EILLANCE RE0t:IREMENTS 4.3.1.1 Each reactor protection system instrumentation channei shall be deme.strated OPEPAELE by the perfor=ar.ce of the CHAN:;EL CHECK CHA:NEL FUNCTION TEST and CHANiEL CALIBRATION operations curin; the 0?ERATIONAL CONO:TIO;;S and at the frequencies shown in Table 4.3.1-1.
4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated auto atic coeration of l
all channels shall be perfortned at least once per 18 months and shall 5
include calibration of time delay relays and timers necessary for proper func-ioning of the trip system.
4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip function of Table 3.3.1-2 shall be demonstrated to be within its limit at 4
least once per 18 months.
Each test shall include at least one logic train such that both logic trains are tested at least once.per 36 months and.one
. char.,el per function such that all cha' nels are tested at least once every n
N tices 18 months where N is the total number of redundar.t channels in a specific reactor trip function.
~
-if botn enannels are inoperable in ene trip system, select at least one ine srable channel in that trip syste. to place in the tripped conditiens, exes when this could cause the Tric Function to occur.
HtJCH - UNIT 2 3/4 3-1
' A..cne e r.: ra,. *-
m o
t i
TABLE 3.3.1-1 3= mc B
REACTDR PROTECTION SYSTEM INSTRUMENTATION
$ [2=
~4 APPLICABLE MINIMUM NUMBER Ep ]
OPERATIONAL OPERADLE CIIANNELS m
LUNCitogAL UNIT CONDITIONS.
PER TRIP SYSTEMiel ACTION
- s e r*
1.
me :
(2C51-k601, A, 8, C, D, E, F, C, H)
C O 2
[]
a.
Neutron Flux - High 2,
5'**
3 1
sw 3, 4 2
2 1hro b.
Inopera t ive 2,5
3 1
3, 4 2
2 daj8 2.
Average Power Range Monitor:
(2C51-k605 A, D, C, D, E, F) um
[d a.
Neutron Flux - Upscale, 15%
2, 5 2
1 b.
Flow Referenced Simulated Ch T he rma l Powe r - Upsca le 1
2 3
l c.
Fixed Neutron Flux -
Upscale, 118%
1 2
3 d.
Inope ra t ive 1,2,5 2
4 e.
Downscale 1
2 3
F.
LPRM 1,2,5 (d)
NA to 3.
Reactor Vessel Steam Dome Pressure -
's High (2821-M678 A, B, C, D) 1, 2
2 5
l 4
I#
4.
no Low (i.evel 3) (2B21-N680 A, B, C, D) 1, 2 2
5 l
S.
Main Steam Line Isolation Valve -
Closure (NA) l
4 3
6.
Main Steam Line Radiation - High 1, 2
- 8 2
6 8
(2011-k603 A, 8, C, D) 7.
Drywell Pressure - High 1,
2
2 5
(2C71-N650 A, B, C, D) e e
l:,
,,'r.
's,e l 'y s TABLE 3.3.1-1 (Continued)
REACTOR PROTECTION SYSTEN INSTRUMENTATION x
bh APPLICADLE MINIMUM NUMBER 3
OPERATlONAL OPERABLE CllANNELS
$m 2
FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEMfal ACTION to
$a 8.
Scram Discharge Volume Water Illgh (2C11-NO13A,B,C,D) 1, 2, 5'"'
2 4
level
$. c 2
LoveI - liigh (2C11-N060A,B,C,D) 1, 2, 5 2
4
~
--I 9.
Turbine Stop valve - Closure (NA)
I
4 7
l 10 Turbine Control Valve rest Closure, 2
7 l
Trip Oil Pressure - LvN 18
(2C71-NOOSA,b,C,D) 11.
.eactor Mode Switch in Shutdown Position (NA) 1,2,3,4,5 1
8 6
12.
Manual Scram (NA) 1,2,3,4,5 1
9 hs N
Jh hs 9
ts) i i
4 9
c.
TABLE 3.3.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION In OPERATIONAL CONDITION 2. be in at least HOT SHUTDOWN ACTION 1 l
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS or postive reactivity changes and fully insert all insertable control rods within one hour.
Lock the reactor mode switch in the Shutdown position within ACTION 2 one hour.
Be in at least STARTUP within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
l ACTION 3
' In OPERATIONAL CONDITION 1 or 2, be in at least HOT SHUTDOWN ACTION 4 l
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour.
l Be in at least HOT SHUTDOWN,within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 5 "Be in STARTUP with the main steam line isolation valves closed ACTION 6 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or in at least HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
(
Initiate a reduction in TH5RMAL POWER within 15 minutes and ACTION 7 be at less than 30% of RATED THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
ACTION 8 -
In OPERATIONAL CONDITION 1 or 2, be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
l In OPERATIONAL CONDITION 3 or 4, immediately and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> verify that all control rods are fully inserted.
In OPERATIONAL CONDITION 5 suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour.
HATCH - UNIT 2 3/4 3-4 Amendment No. 8
_. _=
E TABLE 3.3.1-1 (Continued)
Y-REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION 9 -
In OPERATIONAL CONDITION I or 2, be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
In OPERATIONAL CONDITION 3 or 4, lock the reactor mode switch in the Shutdown position within one hour.
In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour.
TABLE NOTATIONS A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for a.
required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.
b.
The " shorting links" shall be removed from the RPS circuitry during CORE ALTERATIONS and shutdown margin demonstrations performed in accordance with Specification 3.10.3.
The IRM scrams are automatically bypassed when the reactor vessel mode c.
switch is in the Run position and all APRM channels are OPERABLE and on scale.
d.
An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than eleven LPRM inputs to an APRM channel.
These functions are not required to be OPERABLE when the reactor e.
pressure vessel head is unbolted or removed.
1 f.
This function is automatically bypassed when the reactor mode switch is in other than the Run position.
g.
This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.
h.
With any control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.11.1 or 3.9.11.2.
- i. These functions are bypassed when turbine first stage pressure is s250*
psig, equivalent to THERMAL POWER less than 30% of RATED THERMAL POWER.
" Initial setpoint.
Final setpoint to be determined during startup testing.
1 l
HATCH - UNIT 3/4 3-5 Amendment No. 28, 79, 53, 69 i
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.1 3/4 3-6 Amendment tio.14 j
HATCH e U;!!T 2
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TABLE 4.3.8-1
- >M DECRADED STATION VOLTAGE PROTECTION INSTRtMNTATION P
SLRVEILLMCE REQUIREMENTS 5
M Instrument Functional Instrument Ref. No.
Instrument Instrument Check Test Minimum Calibration m
(a)
(b)
Mininum Frequency Frequency Minimum Frequency 1
4.16 kv Emergency Bus N/A Once/ month Once/ operating cycle t#xiervoltage Relay l
(Loss of Voltage Condition) 2 4/16 kv Emergency Bus N/A Once/ month once/ operating cycle i
Undervoltage Relay l
(Oegraded Voltage Condition) w1 l
Y l
E NOTES FOR TABLE 4.3.8-1 a.
The colum entitled "Re f.
No." is only for convenience so that a one-to-one relationship can be established between items in Table 3.3.8-1 and items in Table 4.3.8-1.
1 b.
Surveillance of.this instrumentation is required during reactor startup;, power operation, and hot I
shutdown.
Y.
a j
I a
i E
N l
INSTRUMENTATION 3/4.3.9 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION
!IMITING CONDITION FOR OPERATION 3.3.9.1 The anticipated transient without scram recirculation pump trip (ATWS-RPT) system instrumentation channels shown in Table 3.3.9.1-1 shall be OPERABLE with their trip setpoints set consistent with values shown in the Trip Setpoint column of Table 3.3.9.1-2.
APPLICABILITY: OPERATIONAL CONDITION 1.
ACTION:
a.
With an ATWS recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.9.1-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel trip setpoint adjusted consistent with the Trip Setpoint value, b.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, declare the affected trip system (s) inoperable.
With one trip system inoperable, restore the inoperable trip system c.
to OPERABLE status within 14 days or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
d.
With both trip systems inoperable, restore at least one trip system to OPERABLE status within one hour or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.3.9.1.1 Each ATWS recirculation pump trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.9.1-1.
4.3.9.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
t HATCH - UNIT 2 3/4 3-66 Amendment No. 69
O*
=c TA8LE 3.3.9.1-1 gN ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION
- o. z 9
5g JRIP FUNCTION MINIMUM OPERABLE CilANNEl,S PER TRIP SYSTEM yM 1
Reactor Vessel Water Level - Low Low, Level 2 1
2.
Reactor Vessel Pressure - High 1
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HATCH - UNIT 2 3/4 3-68 Amendment No. 69
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I TABLE %.3.9.1-1
$5 AIWS RECIRCULATION PUNP TRIP _ ACTUATION INSTRUMENTATION gy SUiiVEl'L' LANCE RiqUiRLMENIS
- a. x El CilANNEL r, C CllANNEL IUNCTIONAL CllANNEL 5
TRIP FUNCIlON
_CilECK TEST 1
O ~4 CAllBRAllON 1.
Reactor Vessel Water Level - Low i
[
Low, level 2 S
R R
e 2
Reactor Vessel Pressure - liigh NA R
R w
N
.l' O
o, 1D s
e t
9 I
1
l' INSTRUMENTATION END-OF-CYCLE RECIRCULATION pVMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.9.2 The end-of-cycle recirculation' pump trip (E0C-RPT) system instrumentation channels shown in Table 3.3.9.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.9.2-2 and with the END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.9.2-3.
APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER 1s greater than or equal to 30% of RATED THERMAL POWER.
ACTION:
a.
With an end-of-cycle recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.9.2-2,. declare the channel inoperable until the channel is restored to OPERABLE status with the channel setpoint adjusted consistent with the Trip Setpoint value.
b.
With the number of OPERABLE channels one less than required by the j
Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, place the inoperable channel (s) in the tripped condition within one hour.
I c.
With the number of OPERABLE channels two or more less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system and:
1.
If the inoperable channels consist of one turbine control valve channel and one turbine stop valve channel, place both inoperable channels in the tripped condition within one hour.
2.
If the inoperable channels include two turbine control valve channels or two turbine stop valve channels, declare the trip system inoperable, d.
With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or reduce THERMAL POWER to less than 30% of RATED THERMAL POWER within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, With both trip systems inoperable, restore at least one trip system e.
to OPERABLE status within one hour or reduce THERMAL POWER to less than 30% of RATED THERMAL POWER within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
HATCH - UNIT 2 3/4 3-70 Amendment No. 69
o' INSTRUMENTATION j
SURVEILLANCE REOUIREMENTS 4,a 4.3.9.2.1 Each end-of-cycle recirculation pump trip system instrumentation channel shall be demonstrated OPERABLE by the performance cf the CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.9.2.1-1.
4.3.9.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
4.3.9.2.3 The END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME of each trip function shown in Table 3.3.9.2-3 shall be demonstrated to be within its limit at least once per 18 months.
Each test shall include at least the logic of one type of channel input, turbine control valve fast closure or turbine stop valve closure, such that both types of channel inputs are tested at least once per 36 months.
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i HATCH - UNIT 2 3/4 3-71 Amendment No. 69
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T ABL E 3. 3.9. 2-1 4
gi 2 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION k 6:
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MINIMUM LE OPERABLE CalANNftS
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j TRIP FUNCTION PER TRJP SYSIOM'*8 l
PJ 1.
Turbine Stop Valve - Closure 28*8 2.
Turbine Control Valve - Fast Closure 2ses i
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8*3A trip system may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance provided that the other trip system is OPEHABLE.
8* *This function shall be automatically bypassed when turbine first stage pressure is less than or equal to 250 psig, equivalent to THERMAL POWER less than 30 % of RATED THERMAL POWER.
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TABLE 4.3.9.2.1-1 r
Ej END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM SURVElllANCE REQUIRIMEN11 gt:c gg a CHANNEL FUNCTIONAL CHANNEL re c:
TEST cat.18 RATION se 32 J R I P FUNCT ION O -1 A
1.
Turbine Stop Valve - Closure M*
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Turbine Control Valve - Fast Closure M*
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- Ihe Recirculation Pump Breakers need not be tripped on part of the Channel Functional Test. All channel alarm functions and only that portion of the trip Functions which can be tested without causing a trip of the Breakers (and Recirculation Pumps) need be tested during the Channel functional Test.
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l*
' l.
INSTRUMENTATION
~
BASES MONITORING INSTRUMENTATION (Continued)
FIRE DETECTION INSTRUMENTATION (Continued)
'i In the event that a portion of the fire detection I
instrumentation is inoperable, increasing the frequency of fire patrols in the affected areas is required to provide detection i
capability until the inoperable instrumentation is restored to OPERABILITY.
1 3/4.3.6.9 RADICACTIVE LIQUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential j
releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the methods in the CFFSITE DOSE CALCULATION MANUAL (CDCM) to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.
The OPERABILITY and use of this instrumentation is l!
consistent with the requirements of General Design Criteria 60, lw,@
63, and 64 of Appendix A to 10 CFR Part 50.
l 1
t 3/4.3.6.10 RADICACTIVE GASEQUS EFFLUENT INSTRUMENTATION 3
ff.
'The radioactive gaseous affluent instrumentation is provided to 1
monitor and control, as applicable, the releases of radioactive 1 'j materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for i
I these instruments shall ne calculated in accordance with the i
1_
methods in the CDC.M to ensure that the alarm / trip will occur J
prior to exceeding the limits of 10 CFR Part 20.
The monitoring
'.t instrumentation includes provisions for monitoring (and i
l controlling) the concentrations of potentially explosive gas j
.I mixtures in the main condenser offgas treatment system.
The CPERABILITY and use of this instrumentation is consistent with i
I the requirements of General Design Criteria 60, 63, and 64 of Q
Appendix A to 10 CFR Part 50.
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3/4.3.7 TURBINE OVERSFEED PROTECTION SYSTEM l
~f This specification is provided to ensure that the turbine l
overspeed protection system instrumentation and the turbine
,g speed control valves are OPERABLE and will protect the turbine from excessive overspeed.
Protection from turbine excessive overspeed is required since excessive overspeed of the turbine i
- ?)
could generate potentially damaging missiles which could impset
{F and damage safety-related camponents, equipment or structures.
- s t
33 Amendment No. 48
% "/4 3-5 EATCH UNIT 2
" +' h.! ? o M C-
- c
I 9
4 INSTRUMENTATION
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BASES 3/4.3.8 DEGRADED STATION VOLTAGE PROTECTION INSTRUMENTATION The undervoltage relay's shall automatically initiate the disconnection of offsite power sources whenever the voltage
~
setpoint and time delay limits ' ave been exceeded. This action r
shall provide voltage protection for the emergency power systems by preventing sustained degraded voltage conditions due to the offsite power source and interaction between the offsite and onsite emergency power systems. The undervoltage relays have a time celay characteristic that provides protection aga, inst both a loss of voltage and degraded voltage condition and thus minimizes the effect of short duration disturbances without exceeding the maximum time delay, including margin, that is assumed in the FSAR accident analyses.
3/4.3.9 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION The anticipated transient without scram (ATWS) recirculation pump trip system provides a means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient. The response of the plant to this postulated event falls within the envelope of study events in General Electric Company Topical Report NE00-10349, dated March 1971, and NEDO-24222, dated December 1979.
The end-of-cycle recirculation pump trip (EOC-RPT) system is a part of the Reactor Protection System and is an essential safety supplement to the reactor trip. The purpose of the EOC-RPT is to recover the loss of thermal margin which occurs at the end-of-cycle. The physical phenomenon involved is that the void reactivity feedback due to a pressurization transient can add positive reactivity to the reactor system at a faster rate than the control rods add negative scram reactivity. Each EOC-RPT system trips both recirculation pumps, reducing coolant flow in order to reduce the void collapse in the core during two of the most limiting pressurization events. The two events for which the EOC-RPT protective feature will function are closure of the turbine stop valves and fast closure of the turbine
+
control valves.
I A fast closure sensor from each of two turbine control valves provides input to the EOC-RPT system; a fast closure r
sensor from each of the other two turbine control valves provides input to the second EOC-RPT system. Similarly, a limit switch for each of two turbine stop valves provides input to one EOC-RPT system; a limit switch from each of the other two stop valves provides input to the other EOC-RPT system.
For each EOC-RPT system, the sensor relay contacts are arranged to form a ~
1-out-of-2 twice logic for the fast closure of turbine control HATCH - UNIT 2 B 3/4 3-Sa Amendment No. U, AB, 69
e.
INSTRUMENTATION
. t-BASES 3/4.3.9 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION (Continued) valves and a 2-out-of-2 logic for the turbine stop valves. The operation of either logic will actuate the EOC-RPT system and trip both recir'culation pumps.
Each EOC-RPT system may be manually bypassed by use of a keyswitch which is administratively controlled.
The manual bypasses and the automatic Operating Bypass at less than 30% of RATED THERMAL POWER are annunciated in the control room.
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l HATCH - UNIT 2 8 3/4 3-Sb Amendment No. 69 r
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