ML20207H972
| ML20207H972 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/29/1986 |
| 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 | |
| ML20207H974 | List: |
| References | |
| NPF-05-A-071, TAC 63412 NUDOCS 8701080241 | |
| Download: ML20207H972 (19) | |
Text
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o UNITED STATES 4
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8 NUCLEAR REGULATORY COMMISSION o
h WASHINGTON, D. C. 20555 k.....,/
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET N0. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. NPF-5 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated Novr.mber 10, 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 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 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 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. NPF-5 is hereby amended to read as follows:
8701080241 851229 i
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 71, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION W
c Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 29, 1986 l
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4 ATTACHMENT TO LICENSE AMENDMENT N0. 71 FACILITY OPERATING LICENSE N0. NPF-5 DOCKET N0. 50-366 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are identified by Amendment number and contain vertical lines indicating the area of change. The overleaf pages are provided for convenipnce.
Remove Insert V
V 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 3/4 3-15 3/4 3-15 3/4 3-58 3/4 3-58 3/4 3-58a 3/4 3-58b 3/4 3-58c 3/4 3-58d 3/4 3-58e 3/4 7-6 3/4 7-6 1
3/4 7-8 3/4 7-8 6
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4 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS j
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 ROD 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 Main Control Room Environmental Control System 3/4 3-58 (MCRECS) Actuation Instrumentation 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 3/4.4 REACTOR COOLANT SYSTEM l
3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops 3/4 4-1 Jet Pumps 3/4 4-2 Idle Recirculation Loop Startup 3/4 4-3 HATCH-UNIT 2 V
Amendment 27,77,69,70, 71 g-.
O INDEX
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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREW.ENTS lm'-
t SECTION PAGE i
REACTOR COOLANT SYSTEM (Continued) i Jet Pumps 3/4 4-2 j
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 Operatio.nal. Leakage 3/4 4-6 i
3/4.4.4 CHEMISTRY 3/4 4-7 l
3/4.4.5 SPECIFIC ACTIVITY 3/4 4-10 3/4.4.6 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System 3/4 4-13 i
Reactor Steam Dome 3/4'4 !
3/4.4.7 MAIN STEAM LINE ISOLATION VALVES 3/4 4-19 j
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 l
3/4.5.3 LOW PRESSURE CORE COOLING SYSTEMS l
Core Spray System 3/4 5-4 Low Pressure Coolant Injection System 3/4 5-7 3/4.5.4 SUPPRESSION CHAMBER 3/4 5-9 HATCH-UNIT 2 VI Amendment No. #,69
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TABLE 3.3.2-1 8
ISOLATION ACTUATION INSTRUMENTATION c*
-4 m
VALVE CROUPS MINIMUM NUMBER APPLICABLE TRIP FUNCTiod OPERATED BY OPERABLE CHANNELS OPERATIONAL SIGNAL (a)
PER TRIP SYSTEM (b)(c)
CONDITION ACTION 1.
PRIMARY CONTAINMENT ISOLATION a.
Low (Love 1 3) 2, 6, 10, 2
(2821-N680 A, B, C, D) 11, 12 1,2,3 20 2.
Low-Low (Love 1 2)
(2821-N682 A, B, C, D) 5,
- 2 1,2,3 20 1
g 3.
Low-Low-Low (Love 1 11 1
(2821-N681 A, B, C, D) 2 1,2,3 20 i
b.
Drywell Pressure - High (2CT1-N650 A, B, C, D) 2, 6 h 10, 2
1, 2, 3
20 12,
- c.
1.
Radiation - High 1, 12, ( d )
2 1, 2, 3 21 (2D11-k603 A, B, C, D) l 2.
Pressure - Low 1
(2821-E015 A, B, C, D) 2 1
22 y
3.
Flow - High 1
a (2821-M686 A, 8. C, D) 2/IIne 1, 2, 3 21 (2821-N687 A, B, C, D)
I Y
(2821-N688 A, B, C, D)
(2B21-N689 A, B, C, D) w l
d.
Main Steam Line Tunnel Temperature - High 1
(2821-N623 A, B, C, D) 2/line'*8 1,2,3 21 (2820-N624 A, B, C, D)
(2E21-N625 A, B, C, D)
(2B21-2626 A, B, C, D) e.
Condenser Vscuum - Los 1
(2821-M056 A, B, C, D) 2 1,
2,8,38'8 23 i
P.
Turbire Building Ares TevrJture - High 1
i i
(2t,64-R001, 2U61-R002, 2061-R003, 2t**
1, 2, 3 21
'1461-R004) a n
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TABLE 3.3.2-1 (Continued) e ISOLATION ACTUATION INSTRUMENTAT1011
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VAL'vE CROUPS MINIMUM NUMBER APPLICABLE TRIP FUNCTlogi OPERATED BY OPERA 8LE CHANNELS OPERATIONAL S IGNAL(a )
PER TRIP SYSTEM (b)(c)
CONDITION ACTION 2.
SECONDARY CONTAINMENT IS0tATION a.
Reactor Building Exhaust Radiation - High 6, 10, 12,
- 2 1,2,3,5 and**
24 (2011-K609 A, B, C, D) b.
DryweII Pressure - High 2, 6, 7, 10, 2
1,2,3 24 (2CT1-N650 A, B, C, D) 12,
- c.
Reactor Vessel Water l
Level - Low Low (Level 2) 5,
- 2 1,2,3 24 (2821-N682 A, 8, C, D) l d.
Rerueling Floor Exhaust Radiation - High 6, 10, 12,
- 2 1,2,3,5 and**
24 (2011-K611 A, b, C, D) l ss1 3.
HEACTOR WATER CLEANUP SYSTEM ISOLATION Y
a.
A Flow - High (2C31-N603 A, 8) 5 1
1,2,3 25 e-*
N b.
Area Temperature - High 5
1 1,2,3 25 (2C31-N662 A, D, E, H, J, M) c.
Area Ventilation & Temp. - High 5
1 1,2,3 25 (2C31-N663 A, D,E,H.J M;
2C38-N661 A, 0, E, H, J, M; 2C31-N662 A, D, E, H, J, M) d.
SLCS Initiation (NA) 5"'
NA 1,2,3 25 e.
Reactor Vessel Water Level - Low Low 5,
- 2 1, 2, 3 25 (Level 2) (2821-N682 A, 8, C, D)
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TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUNENTATION J
ACTION ACTION 20 Be in at least HOT SHUT 00WN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 21 Be in at least STARTUP with the main steam line isolation valves closed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT SHUT 00WN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUT 00WN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 22 - 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 />.
ACTION 23 Be in at least STARTUP with the Group 1 isolation valves closed 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 NOT SHUT 00WN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 24 - Establish SECONDARY CONTAINNENT INTEGRITY with the standby gas treatment system operating within one hour.
ACTION 25 Isolate the reactor water cleanup systam.
ACTION 26 - Close the affected system isolation valves and declare the affected system inoperabic.
ACTION 27 i
Verify power availability to the bus at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or close the affected system isolation valves and declare the affected system inoperable.
ACTION 28 Close the shutdown cooling supply and reactor vessel head spray isolation valves unless reactor steam dome pressure s 145 psig.
E01fl Actuates the standby gas treatment system.
I When handling irradiated fuel in the secondary containment.
See Specification 3.6.3 Table 3.6.3-1 for valves in each valve group.
a.
b.
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 required surveillance without placing the trip system in the tripped condition provided at least one other OPERA 8LE channel in the same trio system is monitoring that parameter.
With a design providing only one channel per trip system, an inoperable c.
channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken, d.
Trips the mechanical vacuum pumps.
A channel is OPERABLE if 2 of 4 instruments in that channel are OPERABLE.
e.
f.
May be bypassed with all turbine stop valves closed.
g.
Closes only RWCU outlet isolation valve 2631-F004.
h.
Alarm only.
1.
Adjustable up to 60 minutes.
HATCH - UNIT 2 3/4 3-15
nsratFINTATION f
TRAVEPSITE DCORE PROEE SYSTEM i
LIMITI?U CO?DITION FOR OPERATION l
3.3.6.6.
'Ihe traversirg incore probe system shall be OPERABLE with:
I a.
Four movable detectors, drives and readout equipnent to map the l
core, and I
b.
Indexing equipment to allow all four detectors to be normalized in l
a connon location.
APPLICABILITY:
e When the traversing incore' probe is used for:
a.
Recalibration of the IRRM detectors, b.
Monitoring the APIMR, IRGR, or M3'R, and Adjustment of the'APRM setpoints.
c.
ACTION:
(-
With the traversing incore probe system inoperable preve7tirg normalization of the. TIP detectors, do not use the system for the above applicable monitoring :or calibration functions for more than 31 EFPD followirg the last normalization.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
l I
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stweILInCE etuv1PIMems 4.3.6.6 The traversing incore probe system shall be demonstrated OPERABLE by normalizire each of the above required detector outputs prior to or I
during use when required for the above applicable nonitoring or calibration functions, if not performed within the previous 31 EFPD.
l I
HA1014 UNIT 2 3/4 3-57 Amendment No. 43
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e INSTRUMENTATION MAIN CONTROL ROOM ENVIRONMENTAL CONTROL SYSTEM (MCRECS) ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.7 The MCRECS actuation instrumentation channels shown in Table 3.3.6.7-1 shall be OPERABLE, with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6.7-2.
APPLICABILITY: As shown in Table 3.3.6.7-1.
ACTION: As shown in Table 3.3.6.7-1.
SURVEILLANCE REQUIREMENTS 4.3.6.7 Each MCRECS actuation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations during the OPERA 1IONAL CONDITION and at the frequencies shown in Table 4.3.6.7-1.
HATCH - UNIT 2 3/4 3-58 Amendment No. 71 l
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-e TABLE 3.3.6.7-1 (SHEET 1 OF 2) x MCRECS ACTUATION INSTRUMENTATl_qq e
E M
MINIMUM NUMBER APPLICABLE d
TRIP FUNCT10el OPERABLE CHANNELS OPERATIONAL N
PER TRIP SYSTEMielfbt
_CONDITIOh.
ACTION 1
Low Low Low (Level 1) (c) 1,2,3 52 2
2821-N691 A, B, C, D 2.
Drywell Pressure - High (c) 2 2E11-N694 A, B, C, D 1,2,3 52 t
3.
Mein Steen Line Radletion - High (c) 2D11-M603 A, B, C, D 2
1, 2, 3 53 4.
Main Steen Line Flow - High (c) 2B21-N686 A, 8, C D 2/line 1, 2, 3 53 2821-N687 A, B, C, D 2821-N688 A, B, C, D 2f>21-N689 A, B, C, D 5.
Refueling Floor Area Radletion - High (c) i 2D21-M002 A, D 1
y 1,2,3,5,*
54 N*
6.
Control Room Air Inlet Radletion - High (d) 1Z41-R615 A, B 1
w 1,2,3,5,*
54 e
I" 7.
Control Room Air Inte*, Chlorine Lovel - High (d)
IZ41-N022 A, B 1
1,2,3,4,5 55 J
8 i
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2, d
4
y *,
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DSTRIFINTATION j.
TRAVEPSIlU ITCORE PROEE SYSTD4
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l LTMITItC CONDITION mR OPEPATION l
3.3.6.6.
'Ihe traversirg incore probe system shall be OPERABLE with:
l a.
Four movable detectors, drives and readout equipnent to map the l
core, and
},
b.
Indexingequipme$ttoallowallfourdetectorstobenormalizedin l
a cor:rnon location.
APPLICABILITY:
i When the traversirg incere probe is used fort a.
Recalibration of the LPRM detectors, b.
Monitoring the APIJiGR, IRGR, or MCPR, and c.
Adjustment of the, APRM setpoints.
ACTION:
C With the traversing incore probe system inoperable preventing normalization of the. TIP detectors, do not use the system for the above applicable monitoring :or calibration functions for more than 31 EEPD following the last normalization.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
[
SURVEmAtCE PEOUIPDirt7Ps 4.3.6.6 The traversing incere probe system sell be demonstrated OPERABLE by normalizing each of the above required detector outputs prior to or during use when required for the above applicable monitorire or calibration functions, if not performed within the previous 31 EFPD.
1 HMQ1 J UNIT 2 3/4 3-57 Amendment No. 43 i
.i
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INSTRUMENTATION MAIN CONTROL ROOM ENVIRONMENTAL CONTROL SYSTEM (MCRECS) ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.7 The MCRECS actuation instrumentation channels shown in Table 3.3.6.7-1 shall be OPERABLE, with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6.7-2.
APPLICABILITY: As shown in Table 3.3.6.7-1.
ACTION: As shown in Table 3.3.6.7-1.
SURVEILLANCE REQUIREMENTS 4.3.6.7 Each MCRECS actuation channel shall be demonstrated OPERABLn by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations during the OPERAlIONAL CONDITION and at the frequencies shown in Table 4.3.6.7-1.
4 HATCH - UNIT 2 3/4 3-58 Amendment No. 71
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TABLE 3.3.6.7-1 (SHEET 1 0F 2)
MCRECS ACTUATION thSTRLMNTATION 8
E 1
M MINIMUM NUMBER APPLICABLE
-4 TRIP FUIICTlost OPERABLE CHANNELS OPERATIONAL N
PER TRIP SYSTEMfallb)
CONDITION _
KIlgg 1.
4 Lw Lw Lw (Level 1) (c) 2 1,2,3 52 2821-18691 A, 8, C, D i
2.
Drywell Pressure - High (c) 2 2E11-90694 A, 8, C, D 1,2,3 52 3.
Mein Stese Line Radletion - High (c) 2011-I(603 A, 8, C, D 2
1, 2, 3 53 4.
Main Steam Line Flw - High (c) 2821-N686 A, 8, C, D 2/line 1,2,3 53 2821-N687 A, B, C, D 2821-18688 A, 8. C, D 2821-II689 A, 8, C, D 5.
Refueling Floor Area Radiation - High (c) 2021-M002 A, D 1
- y 1,2,3,5,*
54 i %
i
- 6.
Control Room Air inlet Radiation - High (d) j 1Z41-R615 A, 8 1
1,2,3,5,*
54 7.
i I Control Room Air inlet Chlorine Level - High (d) 1Z41-N022 A, 8 1
1,2,3,4,5 55 d'
i S
a o.
3!$n i
l D
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1 1
i
C TABLE 3.3.6.7-1 (SHEET 2 0F 2)
MCRECS ACTUATION INSTRUMENTATION ACTION ACTION 52 Take the ACTION required by Specification 3.3.3.
ACTION 53 Take the ACTION required by Specification 3.3.2.
ACTION 54 With one of the required radiation monitors inoperable, restore the a.
monitor to OPERABLE status within 7 days or, within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, initiate and maintain operation of the MCRECS in the pressurization mode of operation.
b.
With no radiation monitors OPERABLE, within I hour initiate and maintain operation of the MCRECS in the pressurization mode of operation.
The provisions of Specification 3.0.4 are not applicable.
c.
ACTION 55 -
With one of the required chlorine detectors inoperable, restore the a.
inoperable detector to OPERABLE status within 7 days or, within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, initiate and maintain operation of the MCRECS in the isolation mode of operation.
b.
With no chlorine detectors OPERABLE, within I hour initiate and maintain operation of the MCRECSs in the isolation mode of operation.
The provisions of Specification 3.0.4 are not applicable.
c.
i NOTES When handling irradiated fuel in secondary containment.
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 other OPERABLE channel in the same trip
.ystem is monitoring that parameter.
b.
With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.
In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.6.7-1 for that Trip Function shall be taken.
Actuates the MCRECS in the control room pressurization mode.
c.
d.
Actuates the MCRECS in the control room isolation mode.
HATCH - UNIT 2
^**" **"
3/4 3-58b
'. O 6
h
-4Q TABLE 3.3.6.7-2 l
MCRECS ACTUATION INSTRUMENTAT1088 SETPolNTS e
TRIP FUNCTION
-4 TRIP SETPOINT ALLOWA8tE VALUE 1.
N 2 -113 inches Lw Lw Lw (Level 1) 2 - 113 inches 2.
Grywell Pressure - High 5 1.92 psig 5 1.92 psig 3.
Main Steen Line Radletion - High 5 3 x full-power background 5 3 x full-power background al.
Mein Steam Line FIw - High 5 138% reted fIw 5 138% reted fIw 5.
Refueling Floor Area Redletion - High 5 20 mr/ hour s 20 mr/ hour 6.
Control floom Air inlet Radletion - High 5 1 mr/ hour 5 1 er/ hour l
7.
Control Room Air inlet Chlorine Level - High 5 5 ppa chlorine 5 5 ppe chlorine M.
I, i
S a
4 n
o *,
- 2 4
3m
-4 n
3:
TA8LE 4.3.6.7-1
~
MCRECS ACTUATl000 INSTRUMENTATIOff SURVEllLAffCE REQUIREMEIQ$
2 CHA90NEL Q
TRIP FUfeCTIOff CHANNEL FUNCTIONAL CHANNEL OPERATIONAL
_CHECM TEST CAllBRATION CONDITIONS IN WHICH N
1.
SURVEILLANCE REQUIRED S
M R
Low Low Low (Lovei 1) 1,2,3 2.
Drywell Fressure - High S
M R
3.
Main Steam Line Radiation - High D
W888 R
1 2, 3 4.
Main Steam Line Flow - High S
M R
1, 2, 3 5.
Refuellpg Floor Area Radiation -
1,2,3 D
Mt*'
High Q
1, 2, 3, 5
- 6.
Control Room Air inlet NA M'**
Radiation - High R
1
- 2 *
'1' 5*
- 7.
Control Room Air inlet NA M
R Chlorine - High 1,2,3,4,5 U
b e
a c.n i
CL I
When handling irradiated fuel in the secondary containment.
Instrument alignment using a standard current source.
a.
e o.
(D=
ct 2
b 5
1
o
, TABLE 4.3.6.7-1 MCRECS ACTUATION IksTRUMENTATION SURVEILLANCES REQUIREMENTS CHANNEL OPERATIONAL CHANNEL
~ FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 1.
Reactor Vessel S
M R
1,2,3 Water Level Low Low Low 2.
Drywell S
M R
1,2,3 Pressure-High 3.
W(a)
R 1,2,3 Line Radiation-High 4.
Main Steam Line S M
R 1,2,3 Flow-High 5.
Refueling Floor.
M(a)
Q 1,2,3,5,*
Area Radiation-High 6.
Control Room NA M(a)
R 1,2,3,5
- Air Inlet Radiation-High 7.
Control Room Air NA M
R 1,2,3,4,5 Inlet Chlorine Level-High
- When handling irradiated fuel in the secondary containment a.
Instrument alingment using a standard calibration source.
HATCH - UNIT 2 3/4 3-58e Amendment No. 71
C j
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Coatinued At least once per 18 months during shutdown, by verifying e.
that:
1.
Each automatic valve servicing non-safety related equip-ment actuates to its isolation position on an isolation test signal.
2.
Each plant service water pump starts automatically, when on Standby, to maintain service water pressure > 60 psig.
3.
The standby service water subsystem pump starts automatically when the 18 diesel generator starts.
(
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a b'
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p HATCH - UNIT 2 3/4 7-5
PLANT SYSTEMS o
3/4.7.2 MAIN CONTROL ROOM ENVIRONMENTAL CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.7.2 Two independent main control room environmental control (MCREC) systems shall be OPERABLE.
APPLICABILITY: CONDITIONS 1, 2, 3, 4*,
5, and **.
ACTION:
With one main control room environmental control system inoper-a.
able, restore the inoperable system to OPERABLE status within 7 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 tne following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
With both main control room environmental control systems inoperable, be in at least HOT SHUTDOWN within 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 next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.2 Each main control room environmental control system shall be demonstrated OPERABLE:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room a.
air temperature is s 105*F.
b.
At least once per 31 days, by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes, At least on.e per 18 months or (1) after any structural main-c.
tenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any venti-lation zone communicating with the system by:
1.
Performing a visual inspection of the system and all associated components before each leak test in accordance with Section 5 of ANSI N510-1975.
- Isolation mode only required to be OPERABLE.
- When handling irradiated fuel in secondary containment.
HATCH - UNIT 2 3/4 7-6 Amendment No. 71
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.
Verifying that the cleanup system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.S.a, C.5.c and C.5.d of Regulatory Guide 1.52, Revision 1, July 1976, and the system flow rate is 2500 cfm + 10%.
3.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 1, July 1976, meets the laboratory testing criteria of Regulatory Position C.6.a of Regula-tory Guide 1.52, Revision 1, July 1976.
4.
Verifying a system flow rate of 2500 cfm + 10% during system operation when tested in accordance with ' ANSI N510-1975.
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d.-
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory f
analysis of a representative carbon sample obtained in a j7 4 ccordance with Regulatory Position C.6.b of Regulatory Guide i.
L 1.52, Revision 1, July 1976, meets the laboratory testing criteria of Regulatory Position C.6.a cf Regulatory Guide 1.52, Revision 1 July 1976.
t.
4.
'i e.
At least once per 18 months by:
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1.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is < 6 L. '
inches Water Gauge while operating the system at a flow i
rate of 2500 cfm + 10%.
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2.
Verifying that on an isolation mode actuation test signal from the chlorine detectors, the system automatically switches to the isolation mode of operation with recircula-tion flow through HEPA filters and charcoal adsorber banks i
and that the isolation dampers close in < 7 seconds.
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HATCH - UNIT 2 3/4 7-7
e PLANT SYSTEMS
_ SURVEILLANCE REQUIREMENTS (Continued) 3.
Verifying that on each of the below pressurization mode actuation test signals, the system automatically switches to the pressurization mode of operation and maintains the main control room at a positive pressure of 2 0.1 inch W.G. relative to the ad.facent Turbine Building during system operation at a flow rate s 400 cfm.
a) Reactor vessel water level - low low low b) Drywell pressure - high c) Refueling floor area radiation - high d) Main steam line radiation - high e) Main steam line flow - high f) Co, trol room intake monitors radiation - high 4.
Verifying that on a high chlorine concentration actuation test signal, the system automatically switches to the isolation mode of operation.
f.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove 2 99% of the DOP when they are tested in place in accordance with ANSI H510-1975 while operating the system at a flow rate of 2500 cfm 1 10%.
g.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove 2 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 2500 cfm i 10%.
HATCH - UNIT 2 3/4 7-8 A"1en ment rio. 71 4
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