ML19208D652
| ML19208D652 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/11/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19208D653 | List: |
| References | |
| NUDOCS 7909290196 | |
| Download: ML19208D652 (7) | |
Text
N UNITED STATES
,8 A
y NbCLEAR REGULATORY COMMISSION I
j WASHINGTON, D. C. 20666 g
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GEORGIA POWER COMPANY OGLETHORPE ELECTRIC MEMBERSHIP CORPORATION MUNICIPAL ELECTRIC ASSOCIATION OF GEORGIA CITY OF DALTON, GEORGIA s.
DOCKET NO. 50-366 EDWIN 1. HATCH NUCLEAR PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendmcnt No. 11 License No. NPF-5 1.
The Nuclear Regulatory Congnission (the Comission) has found that:
A.
The application for amendment by Georgia Power Company et al.
(the licensee) dated July 19, 1979 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.
There is reasonable assurance (1) 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 comon defense and security or to the health and safety of the public; and E.
The issuance of this ar.endment is in accorAnce with 10 CFR Part 51 of the Comission's regulations and all applicable mquirements have been satisfied.
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2-2.
Accordingly, the license is amerided by changes to the Technical Specificaticas 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 cos,;ained in Appendices A and B, as revised through Amendment No.11, are hereby incorporated in the license. The licensee shall operate the facility in accordance witr the Technical Specifications.
3.
This license snendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION m:
Thoma
. Ippolito, Chief Operating Reactors Branch #3
~
Divisiois of Operating Reactors
Attachment:
CI'anges to the Technical Specifications Date of Issuance: September 11, 1979 b'
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ATTACHMENT TO LICENSE AMENDMENT NO. 11 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the follqwing pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating th; area of change.
Remove Inserc 3/4 3-47 3/4 3-47 3/4 3-48 3/4 3-48 3/4 8-3 3/4 8-3 3/4 8-4*
3/4 8-4*
- Overleaf 1055 195
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a SEISMIC HONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.2 The ' seismic monitoring instrumentation shown in Table 3.3.6.2-1 shall be OPERABLE.
APPLICABILITY: At all t'mes.
ACTION:
a.
With one or more of the above required seismic monitoring instruments inoperable for more than 30 days, in lieu of any other report required by Specification 6.9. I, prepare and submit a Special Report to the Cormiission within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.6.2.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the fre-quencies shswn in Table 4.3.6.2-1.
4.3.6.2.2 Each of the above required seismic monitoring instruments actuated during a seismic event shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION performed within 30 days l
following the seismic event.
Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion.
In lieu of any other report required by Specification 6.9.1, a Special Report shall be prepared and submitted to the Com-mi'sion pursuant to Specification 6.9.2 within 10 days describing the s
magnitude, frequency spectrum and resultant effect upon facility features important to safety.
HATCH - UNIT 2 3/4 3-47 Amendment No. 11
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l TABLE 3.3.6.2-1 R@
g Uk SEISMIC MONITORING INSTRUMENTATION I
i MINIMUM MEASUREMENT INSTRUMENTS RANGE CPERABLE INSTRUMENTSANDSENSORLOCATgtg a)
Triaxial Time-History Accelerographs Diesel Generat; Building El 130'0"(c) 1.
0-0.5g 1
a.
(2L51sN021) b.
Reactor Building 87' Level on Dryweil Pedestal (2L51-N020) 0-0.5g 1
Drywell - Feedwater Inlet to R?Y 0-0.5g 1
l c.
Switchyard (c) (lL51-N005) 0-0.5g i
d.
2.
Triaxial Peak Recording Acceleromegs Diesel Generator Base Support 0-1.0g 1
a.
(IL51-N007)
Intake Structure (c)(lL51-N006) 0-1. 0.9 1
b.
ControlBuyingMaincontrol 0409 1
c.
Room Floor (IL51-N008) 1 Coqtrol Building Floor El 112'(c)'
0-1 Og d.
Reactor Bldg Refueling Floor 0-1.0g 1
e.
(2L51-N029) f.
Reactor Pedestal Inside Biological 0-2.0g 1
Shield (2L51-NO35)
Reactor Piping - Feedwater Inlet 0-2.0g 1
g.
ID) 3.
Triaxial Seismic Switches Reactor Building 87' Level on 0.025-0.25g 1
a.
Drywell Pedestal (2L51-N022)
Reactor Building 185' Level Out-b.
side Biological Shield (2L51-N024) 0.025-0.25g Triaxial Response Spectrum Recorder (a) 2-26 Hz 1
4.
Hatch-Unit 1Coginment Foundation El 87' (IL51-N105) 0-0.5g l
a.
With main control room indication and annunciation.
a I
bWith main centrol room annunciation.
I C
Shared witn Hatch - Unit 1.
j Amendment No. 11 3/4 3-48 HATCH - UNIT 2 1055 197
[I D o k l' ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:
a.
In accordance with the frequency specified in Table 4.8.1.1.2-1 on a STAGGERED TEST BASIS by:
1.
Verifying the fuel level in tne 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 ambient condition and accelerates to synchronous speed in < 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 < 120 seconds, and operates for 1 60 minutes.
6.
Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.
7.
Verifying the pressure in both diesel air start receivers to be 1 225 psig.
b.
At least once per 92 days by verifying that a sample of diesel 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.
c.
At least once per 18 months during shutdown by:
1.
Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service.
2.
Verifying that the automatic load sequence timer is OPEPABLE with the interval between each load block within
+ 10% of its design interval.
3.
Verifying the generator capability to reject a load of 1 798 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 1055 198 ___
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a SURVEILLANCE REQUIREMENTS (Continued) 4.
Verifying the generator capability to reject a load of 2764 kW for diesel generator 2A, 2360 kW for diesel gener-ator 18 and 2742 kW for diesel generator 2C without exceed-ing 75t 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, energizes the auto-connected shutdown loads through the load sequencer and operates for > 5 minutes while its generator is loaded with the shutdown loads.
6.
Verifying 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 > 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 a loss of offsite power in conjunction with an ECCS~ actuation test signal, 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 connccted loads, energizes the auto-connected emergency (accident) loads through the load sequencer and operates for > 5 minutes while its generator is loaded with tiie emergency loads.
c)
Verifying that all diesel generator trips, except engine overspeed, low lube oil pressure and generator differential, are automatically bypassed upon loss of voltage on the emergency bus concurrent with an ECCS actuation signal.
HATCH - UNIT 2 3/4 8-4 1055 199
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