ML19318A822
| ML19318A822 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/10/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19318A823 | List: |
| References | |
| NUDOCS 8006240203 | |
| Download: ML19318A822 (8) | |
Text
_.
k
- p %q h
jo UNITED STATES g
NUCLEAR REGULATORV COMMISSION
- y. v.
g 5.*,
-E WASHINGTON, D. c. 2L555 o, % 3 l
gv..... f GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA
- DOCKET NO. 50-321 EDWIN 1. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 License No. DPR-57 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated March 22, 1979, as supplemented May 11 and 16, June 4, 1979, and February 28, 1980, 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 applicable requirements have been satisfied.
sooeso M
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment,andparagraph2.C.(2)ofFacilityOperatingLicense No. DPR-57 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 76, are hereby incorporated in the license.
The licens_ee shall operate the facility in accordance with the Technical Specifications.
3'.
This amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f
f Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 10,1980 i
=
=
ATTACHMENT TO LICENSE AMENDMENT NO. 76 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the Appe.' dix "A" Technical S'pecifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3.2-20 3.2-20 3.2-45 3.2-45 f
3.2-67 3.2-67 3.2-67a (added) 3.11-2 3.11-2 i
l l
Table 3.2-9 INSTRUMENTATION WilICil INITIATES RECIRCULATION PUMP TRIP Reautred Ref.
Instrument Trip Operable Trip Setting Remarks' No.
Condition Channels (a)
Nomenclature per Trip
, Systein-1 Low Lov 1(b)
> -38 inches Power must be reduced and the ReactorWatergvel (ATWS RPT)
(LL2) mode switch placed in a mode other than the RUN Hode.
CD)
~
2.
Reactor Pressure High I
$ 1120 psig Power must be reduced and the (ATWS RPT) mode switch placed in a mode other than the RUN Mode.
3*.
1.
Turbine Stop 2(*)(f) 1.
Stop Valve Trips recirculation pumps on Valve closure 1 90% Open turbine control valve fast 2.
Turbine Control 2.
Control Valve c,Losure or stop valve closure g
Valve 17ast Hydraulic when reactor is >30%.(e) 4 Closure Press Trip o
Point (a) The column entitled "Ref. No." is only for convenience so that a one-to-one relationship can be established between items in Table 3.2-9 and items in Table 4.2-9.
(b) Whenever the reactor is in the R'UN Mode, there shall be one operable trip system for each parameter for each operating recirculation pump, except that one trip system may remain inoperable for up to 14 days.
If this cannot be met, the indicated action shall be,taken.
(c) Anticipated Transients Without Scram - Recirculation Pump Trip (d) End of Cycle - Recirculation Pump Trip (e) Either of these two EOC - RPT systems can trip both recirculation pumps. Each EOC - RPT' system will trip if 2-out-of-2 fast closure signals or 2-out-of-2 stop valve signals are rec'eived.
(f) The requirement for these channels applies from EOC-2000 MWD /t to EOC.
The RPT system may be placed in an inepernble
'l 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 /> to provide the required monthly surveillance.
If one EOC-RPT system is inoperable fer i
longer than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or if both EOC-RPT systems are simultaneously inoperable, an orderly power reduction
."'1 be j
immediately initiated and reactor power will be <30% within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Amendnent N.,. 76 This iten is effective'after installation of EOC-RPT authori:ed by Amend s.t No.76 1
Table 4.2-9 CllECK AND CALIBRATION MINIMUM FREQUENCY FOR INSTRUMENTATION WilICit INITIATES RECIRCULATION PUMP TRIP Ref.
Instrument Check Instrument Functi*onal Test Instrument Calibration No.
Instrument Minimum Frequency.
Minimum Frequency Minimum Frequency (a) 1 Reactor Water (b) el Once/ day Once/ operating cycle Once/ operating cycle Lev (AWS RPT) 2 Reactor Pressure None Once/ operating cycle Once/ operating cycle (AWS RPT) 3*
EOC - RPT Trip a) Initiating Logic
~None Once/ month None b) Breakers None Once/ operating cycle None c) Response Time None None Once/ operating cycle RPT logics + Breakers Y
w E
vi Notes for Table 4.2-9 (a) The column entitled "Ref. No." is only for convenience so that a one-to-one relationship can be established between times in Table 3.2-9 and items in Table 4~.2-9.
(b) An ATWS recirculation pump trip logic system functional test shall be performed once per operating cycle.
- This item is effective after installation of EOC-RPT authorized by Amendment No. 76 Amendment Na.
76.
1 L
BASES FOR LIMITING CONDITIONS FOR OPERATION 3.2.H.S.
Main Steam Line Radiation Monitors (Continued).
the reactor through the main steam lines to the condenser. Two instrument channels with two radiation detectors in each channel are arranged in a one upscale per channel trip logic (one-out-of-two-taken-twice). The trip settings are based on limiting the release of radioactivity via the normal ventilation path and rerouting this activity to be processed through the standby gas treatment system.
I. Jay:rumentation Which Initiates Recirculation Pump Trip (Table 3.2-9)
A~~J1 - RPT 1ha ATW:t rc. f rculation pump trip has been added at the suggestion of ACRS as a means ut i t. it t ing the consequences of the unlikely occurrenc.e of a failurn to scram during an anticipated transient. The responoe of the plant to this poutulated event falls within the envelope of study events given in General Electric Cc=;any Topical Report NEDO-lO349, dated March,1971 and Appendix L of the FSAR.
f2C - RPT An end Of-cycle recirculation pump trip (EOC-RPT) has been installed which trips both l
recirculation pumps upon sensing turbine stop valve or control valve test closure. The pronpt RPT is comprised.of two separate systems, each capable of tripping both recircu-l lation pumps.
Tripping the' recirculation pumps reduces core flow, which reduces void collapse during pressurization events. The reduced void collapse produces a smaller net positive void reactivity addition which results in less of a power increase and consequently a smaller decrease in MCPR.,
J. Instrumentation Which Monitors Leakage Into The Drywell (Table 3.2-10) 1.
Drywell Equipment Drain Sumo Flow Integrator The equipment drain sump is provided with two sump pumps. A flow integrator is provided on the discharge header. The starting of each su=p pump and high sump level are annunciated in the control room. The restarting frequency of a puup motor, in conjunction with the predetermined volume of liquid pu= ped out during
'each period, provides an alaro in the main control room indicating when the identified leakage rate limit is reached.
2.
Drywell Floor Drain Sump Flow Integrator The floor' drain sump is provided with two sump pumps. A flow integrator is i
pro'vided on the discharge header. The starting of each sump pump and high sump level are annunciated in the control room. The restarting frequency of a pump motor, in conjunction with the predetermined volume of liquid pumped out during each period, provides an alarm in the main control room indicating when the unidentified leakage rate limit is reached.
3.
Scintillation Detector For Monitorine Air Particulates A sodium-iodide scintillation detector contained in an instrument rack is used to monitor the release of airborne radioactive particulates in the drywell and torus. A high radiation level reading is indicative of a leak in the nuclear system process barrier in the primary containment. A sample that is continu-ously drawn from the primary containment is collected on traveling filter paper and monitored by a ga=ma. sensitive scintillation detector. Radiation levels are read out by a log rate meter and recorded on a strip chart located in the control room. A high radiation level alarm and a failure alarm are provided and are annunciated in the control room. Also, a high-low flow alarm is pro-vided which annunciates in the control room.
- ~
Anendment No. 42, 76
i
_ GASES FOR LIMITING CONDITIONS FOR OPERATION 4
Scintillation Detector For Monitorinet Radiciodine A sodium-iodide scintillation detector contained in an instrument rack is used: to monitor the release of radioiodine in the dryvell and torus. A high radiation e
1 3.2-67a Amendmeht }{o._-76
BpSl}S FOR LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3.11.B.
,T.inear Heat Ceneration Rate (LHCR)
(Continued)
Ll!GM is nnt returned to within ' the permrribed limitn within two (2) houin, then reduce rametor power to Jew t h.m 2's% u[ rated thermal power within the next four (4) hours. If the limiting condition for operation is restored prior to expiration of the specified time interval, then further progression to less than 25%
of rated thermal power is not re-quired.
C.
Minuuum Critical Power Ratio (MCPR) 4.11.C Minimum Critical Power Ratio (MCPR)
The MCPR limit is specified through-MCPR shall be determined daily out the cycle. From BOC4 to EOC4-during reactor power operation at 2000 MWD /t the MCPR limit is 1.26 1 25% rated thermal power and for 7 x 7,1.24 for 8 x 8, and 1.21 following any change in power for'8 x 8R fuels.* During power level or distribution that would operation MCPR shall be as above cause operation with a li=iting at rated power and flow.
If at control rod pattern as described any time during operation it is in the bases for Specification determined by normal surveillance 3.3.F.
that the limiting value for MCPR is being exceeded, action shall be initiated within 15 minutes to restore operation to within the prescribed limits.
If the steady state NCPR is not returned to within the prescribed limits within two (2) hours, tun reduce reactor power to less than 25% of rated thermal power within the ne.~t four (4) hours.
If the Limiting condition for Operation is restored prior to expiration of the specified time interval, then further progression to less than 25% of rated thermal power is not required.
For core flows other than rated the MCPR shall be Kf times the MCPR value applicable above, where Kf is as shown in Figure 3.11-3.
- MCPR values for EOC4-2000 MWD /t to EOC4 are identical to BOC4 D.
Reoorting Recuirements to EOC4-2000 MWD /t after install-ation of EOC-RPT as authorized If any of the limiting values iden-by Amendment No. 76 tified in Specifications 3.11.A.,
l 3., or C. are exceeded, a Reportable Occurrence report shall be submitted.
If the corrective action is taken, as described, a thirty-day written report vill meet the* requirements of this specification.
Amendment No. 57, 52, 69, 76 3.11-2