ML20052F782
| ML20052F782 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/06/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20052F776 | List: |
| References | |
| TAC-10026, TAC-11262, TAC-11626, TAC-12831, TAC-47044, NUDOCS 8205130626 | |
| Download: ML20052F782 (18) | |
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u GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGI A CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 27 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 October 2,1981, as supplemented January 26, 1982, 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 Commission'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 appifcable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 27, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8205130626 820506 PDR ADOCK 05000321 P
ATTACHMENT TO LICEl6E AMENDMENT N0.27 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET N0. 50-366 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.
The overleaf pages are provided to maintain document completeness.
INSERT REMOVE v
v 3/4 3-63 3/4 3-64 3/4 3-65 3/48-4 3/4 8-4 B3/4 3-5 B3/4 3-5 b,
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INDEX IMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS L
PAGE
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SECTION 3/4.3 INSTRUMENTATION _
3/4.3.1 REACTOR PROTECTION SYSTEN INSTRUMENTATION............ 3/43-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION.................. 3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION 3/4 3-24 INSTRUMENTATION......................................
3/4.3.4 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION 3/4 3-33 INSTRUMENTATION,.....................................
3/4.3.5 CONTROL ROD.WITUDRAWAL BLOCK INSTRUMENTATION......... 3/4 3_
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...... 7"........................
3/4 3-56 Traversing Incore Probe System.......................
3/4 3-57 Chl ori ne Detectors................................... 3/4 3-58 Fire Detection Instrumentation.......................
3/4 3-59 j
TURB INE OVERSPEED PROTECTION SYSTEM....................
3/4.3.7 DEGRADED STATION V0LTAGE PROTECTION INSTRUMENTATION...
3/4. 3.8 l
3/4.4 REACTOR C00LAUT SYSTEM _
l i
l 3 /4'.4.1 RECIRCULATION SYSTEM Reci rcul ati on L, oops.................................. 3/4 4-1 I
Jet Pumps..........'..................................
3/4 4-2 Idle Reci rcul ation Loop 'StarIupi...................... 3/4 4-3 HATCH-UNIT 2 1f Amendment No. 27 l
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE REACTOR COOLANT SYSTEM (Continued) 3/4.4.2 S AFET Y/ REL I EF V ALV ES.................................
3/44-4 3/4 4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems............................
3/4 4-5 Operational Leakage..................................
3/4 4-6 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 Re a c tor Co ol a n t Sys t em...............................
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....................................
3/45-4 Low Pressure Cool ant Injection System................
3/4 5-7 a/4.5.4 SUPPRESSION CHAMBER..................................
3/4 5-9 HATCH-UNIT 2 VI
INSTRlNENTATION 3/4.3.8 DEGRADED STATION VOLTAGE PROTECTION INSTRLNENTATICN LIMITING CCtOITION FOR OPERATION 3.3.8 The degraded station voltage relay channels shown in Table 3.3.8-1 shall be CPERASLE.
APPLICABILITY:
CONDITIONS 1, 2, and 3.
ACTION:
With the number of OPERABI'E channels one less than the required OPERABLE channels, operation may proceed until performance of the next scheduled instrument functional test provided a trip signal is placed in the LOS?
lock-out relay logic for the applicable inoperable channel.
SURVEILLANCE REQUIREMEtTS 4.3.8 Each of the above required degraded station voltage relay channels and shall be demonstrated OPERABLE by performance of the CHANNEL CALIBRATION CHANNEL FIINCTIONAL' TEST operation at the frequencies shown in Table 4.3.8-1.
l l
3/4 3-63 Amendment fio. 27 HATCH-UNIT 2
-n.
s TABLE 3.3.8-1 M
m OECRADEO STATION VOLTAGE PROTECTION INSTRlPENTATION Required Channels
-4 Ref. No.
Instrument Operable Required N
(a)
Channels To Trip Trip Setting 1
4.16 kv Emergency Dus 2/ Bus 2/Dus greater than or equal to 2000 volts Undervoltage Relay At 2800 volts time delay will be (Loss of Voltage less than or equal to 6.5 sec.
Condition) 2 4.16 kv Emergency Bus 2/Ous 2/Dus greater than or equal to 3280 volts Undervoltage Relay At 3280 volts time delay will be (Oegraded Voltage less than or, equal to 21.5 sec.
Condition)
NOTES FOR TABLE 3.3.8-1 a.
The column entitled "Ref.
No." is only for convenience so that a one-to-one relationship can be m3 established between items in Table 3.3.8-1 and items in Table 4.3.8--l.
Y S:
Er ao.
R R
.a:
.f TABLE 4.3.8-1 5N DEGRADED STATION VOLTAGE PROTECTION INSTRUENTATION P
SURVEILLANCE REQUIREMENTS E
Instrument Functional Instrument m
Ref. No.
Instrument Instrument Check Test Minimum Calibration (a)
(b)
Minimum Frequency Frequency Minimum Frequency 1
4.16 kv Emergency Bus N/A Once/ month Once/ operating Undervoltage Relay cycle (Loss of Voltage Condition) 2 4/16 kv Emergency Hus N/A Once/ month Once/ operating Undervoltage Relay cycle (Degraded Voltage Condition) w2 Y
m NOTES FOR TABLE 4.3.8-1 a.
The column entitled "Ref.
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.
b.
Surveillance of this instrumentation is required during reactor startup, power operation, and hot shutdown.
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ELECTRICAL POWER SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) 4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:
In accordance with the frequency specified in Table 4.8.1.1.2-1 a.
on a STAGGERED TEST BASIS by:
1.
Verifying the fuel level in the day fuel tanks.
2.
Verifying the fuel level in the plant fuel storage tank.
3.
Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank.
4.
Verifying the diesel starts from ambien't' condition and
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accelerates to synchronous speed in i 12 seconds.
5.
Verifying the generator. is synchronized, loaded to 2764 kw for diesel generator 2A,2360 kw for' diesel generator 1B or 2742 kw for diesel generator 2C in 1 120 seconds, and operates for 1 60 minutes.
6.
Verifying the diesel generator is aligned to p'rovide stancby power to the associated emergency busses.
7.
Verifying the pre'ssure in both diesel air start receivers to be 1 225 psig.
At le~ast once per 92 days by verifying that a sample of diesel
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b.
fuel from the fuel storage tank, obtained in accordance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM D975-74 when checked for viscosity, water and sediment.
At least once per 18 months during shutdown by:
c.
Subjecting the diesel to an inspection in accordance with 1.
procedures prepar.ed,in conjunction with its manufacturer's recommendations for this class of standby service.
Verifyi,ng that the automatic load sequence timer is 2.
OPERABLE with the interval between each load block within
+ 10" of its design interval.
Verifying the generator capability to reject a load of 3.
> 798 kw while maintaining voltage at 4160 + 400 volts and l frequency at 60 + 2 Hz.
HATCH - UNIT 2 3/4 8-3 Amendment No. 11
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.
Verifying the generator capability to reject a load of 2764 kW for diesel generator 2A, 2360 kW for diesel generator 18 and 2742 kW for diesel generator 2C without exceeding 75% of the difference between nominal speed and the overspeed trip setpoint, or 15% above nominal, whichever is lower.
5.
Simulating a loss of offsite power by itself, and:
a)
Verifying de-energization of the emergency busses and load shedding from the emergency busses.
b)
Verifying the diesel starts from ambient condition on the auto-start signal, energizes the emergency busses with permanently connected loads, energizing the auto-connected shutdown loads through the loao sequencer and operates for 2 5 minutes while its generator is loaded with the shutoown loads.
6.
Verify that on an ECCS actuation test signal, without loss of offsite power, the diesel generator starts on the auto-start signal and operates on standby for 2 5 minutes.
7.
Verifying that on a simulated loss of the diesel generator, with offsite power not available, the loads are shed from the emergency busses and that subsequent loading of the diesel generator is in accordance with design requirements.
8.
Simulating with separate tests a 1) degraded voltage condition and 2) loss of offsite power-in conjunction with an ECCS actuation test sicpal, and a)
Verifying de-energization of the emergency busses and load shedding for the emergency busses.
b)
Verifying the diesel starts from ambient condition on the auto-start signal, energizes the emergency busses with permanently comected loads, energizes the auto-connected emergency (accident) loads through the load sequencer and operates for 2 5 minutes while its generator is loaded with the emergency leads.
c) verifying that all diesel generator trips, except engine overspeed, low lube oil pressure and generator differential, are automatically bypassed upcn loss of voltage on the emergency bus concurrent with an ECCS actuation signal.
HATCH-UNIT 2 3/4 8-4 Ament ' No. 27
2NSTRLNENTATION BASES MONITCAING INSTRLNENTATION (Continued)
FIRE DETECTION INSTRtJ4ENTATION (Continued)
In the event that a portion of the fire detection instrumentation is ~
inoperable, increasing the frequency of fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERASILITY.
3/4.3.7 TURBINE OVERSPEED PROTECTION SYSTEM This specification is 'provided to ensure that the turbine overspeed protection system instrumentation and the turbine 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 could generate potentially damaging missiles which could impact and damage safety-related compcnents, equipment or structures.
3/4.3.8 OEGRADED STATION VOLTAGE PROTECTION INSTRLNENTATION The undervoltate relays shall automatically initite the disconnection of offsite power sources whenever the voltage setpoint and time delay limits have been exceeded. This action 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 delay characteristic that provides protection against 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.
l HATCH-UNIT 2 B 3/4 3-5 Amendment No. 27 e
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