ML20210U106
| ML20210U106 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/21/1986 |
| 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 | |
| ML20210U113 | List: |
| References | |
| DPR-57-A-125, TAC 60895 NUDOCS 8606020174 | |
| Download: ML20210U106 (9) | |
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UNITED STATES
[ pg [,,p, NUCLEAR REGULATORY COMMISSION 3,
fj WASHINGTON, D. C. 20555 k'% /
GEORGIA POWER COMPANY OGLETHORPE POWER COR_P_0 RATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA 00_CKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT,__ UNIT N0. 1
' AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.125 License No. DPR-57 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated March 7, 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 (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 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.
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. DPR-57 is hereby amended to read as follows-l 8606020174 860521 PDR ADOCK 05000321 P
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Technical _ Specifications The Technical Specificatic.ns contairred in Appendices A and B, as revised through Amendment N'o.
125, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
l 3.
This license er:endment is effective as of its date of issuance and shall be implerrented withir. 30 days of issuar.ce.
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FOR THE NUCLEAR REGULATORY COMMI5 ION f
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V Daniel R. Muller, Director BWR Project Directorate #2 Division of W R Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 21, 1986 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 125 J
FACILITY OPERATING LICENSE N0. DPR-57
)
DOCKET N0. 50-321 1
i Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and
. centain a vertical line indicating the area of change.
Remove Insert 3
3.1-5 3.1-5 3.1-6 3.1-6 3.1-6a i
3.2-2 3.2-2 3.2-4 3.2-4 3.2-19 3.2-19 1
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Table 3.1-1 (Cant'd)
Scram Operable Number Source of Scram Trip Signal channels Scram Trip Setting Source'of Scram Signal is (a)
Required Per Required to be Operable Except as Indicated Below Trip System (b) e H
8 APRM Downscale 2
>3/125 of full scale The APRM downscale trip is active only when the Mode Switch is in RUN. The APRM downscale trip is automatically bypassed when the IRM instrumentation is operable and not tripped.
15% Flux 2
415/125 of full The APRM 15% Scram is auto-scale Tech Spec mistica11y bypassed when the 2.1.A.1.b.
Mode Switch is in the RUN position.
,u) 7 9
Main Steam Line Radiation 2
<3 times normal Not required if all steam liackground at rated lines are isolated.
g thermal power (c).
10 Main Steam Line Isolation 4
410% valve closure Automatically bypassed when Valve Closure Trom full open the Mode Switch is not in g
in Tech spec 2.1.A.S.
the RUN position. The design
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permits closure of any two 2
lines without a scram being 5
initiated.
l i:f 11 Turbine Control Valve 2
Within 30 milli-Automatically bypassed when l
g Fast Closure seconds of the start turbine steam flow is below of control valve thati corresponding to 30% of fast closure rated thermal power as measured w
O Tech Spec 2.1.A.4.
by turbine first stage pressure.
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Table 3.1-1 (Cont'd)
Scram Operable Number Source of Scram Trip Signal Channels Scram Trip Setting Source'of Scram Signal is (a)
Required Per Required to be Operable Trip System Except as Indicated Below ll (b)
H w
12 Turbine Stop Valve 4
<10% valve closure Automatically bypassed when Closure from full open turbine steam flow is below Tech Spec 2.1.A.3.
that corresponding to 30% of rated thermal power an measured by turbine first stage pressure.
Notes for Table 3.1-1 The column entitled " Scram Number" is for convenience so that a one-to-one relationship can be established a.
{l between items in Table 3.1-1 and items in Table 4.1-1.
I b.
There shall be two operable or tripped trip systems for each potential scram signal. If the number of operable channels cannot be met for one of the trip systems, that trip system shall be tripped. However, EE one trip signal channel of a trip system may be inoperable for up to two (2) hours during periods of required surveillance testing without tripping the associated trip system, provided that the other remaining channel (s)
[f monitoring that parameter within that trip system is (are) operable.
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c.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than Ei 20% rated power, the normal full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual wa I*
radiation levels resulting from hydrogen injection. The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels af ter ya completion of hydrogen injection and prior to establishing reactor power levels below 20% rated power.
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N:tes for Tcble 3.1-1 (coet) h For SCRANS 1 thru 7 and 8 APRM 13% Flux, if the number of operable channels is not met for both trip systems; initiate insertion of all control rods capable of being moved by control rod drive pressure and complete their insertion within four (4) hours.
H For SCRAM 8 (APRM High Trips, Inoperative, and Downscale), if the number of operable channels in not met t"
for both trip systems; initiate insertion of all control rods capable of being moved by control rod drive pressure and complete their insertion within four hours or reduce power to the IRM range and go to the START & HOT STANDBY position of the Mode Switch within eight hours.
1 For SCRAMS 9 and 10, if the number of operable channels is not met for both trip systems; reduce turbine
'l load and close main steam line isolation valves within eight hours or initiate insertion of all control I
rods capable of being moved by control rod drive pressure and complete their insertion within four hours.
For SCRAMS 11 and 12, if the number of operable channels is not met for both trip systems, reduce reactor power to 25% of rated thermal power or less within eight hours.
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TABLE 3.2-1 INSTRUMENTATION WHICH INITIATES REACTOR VESSEL AND PRIMARY CONTAINMENT ISOLATION.
j Required Ref.
Trip Operable Action to be taken if No.
Instrument Condition Channels Trip Setting number of channels is (a)
Nomenclature per Trip not met for both trip Remarks (d)
System (b) systems (c) 1 Reactor Vessel Low (level 3) 2
>8.5, inches Initiate.an orderly Initiates Group 2 & 6 g
shutdown and achieve isolation.
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Water Level Narrow Range i
g the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or isolate the shutdown cooling system.
Low Low 2
>-55 inches Initiate an orderly Starts the SGTS, 2
i (Level 2)
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shutdown and achieve initiates Group 5 the Cold Shutdown isolation, and u)
Condition within 24 initiates p
hours.
N isolation.
Low Low Low 2
>-121.5 inches Initiate an orderly Initiates Group 1
{
g (Level 1) shutdown and achieve isolation.
the Cold Shutdown Con-l Q
dition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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Reactor Pressure High 1
4_135 pais Isolate shutdown Isolates the shatdown 5:
(Shutdown Cooling cooling.
cooling suction valves Mode) of the RHR system.
I h3 Drywell Pressure High 2
<2 peig Initiate an orderly Starts the standby shutdown and achieve gas, treatment system, M
the Cold Shutdown initiates Group 2 7
Condition within 24 isolation and second-i hours.
ary containment j
isolation.
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Main Steam Line High 2
<3 times iiornal full Initiate an orderly load Initiates Group 1 l
Radiation power reduction and close MSIVs isolation.
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background (e) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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1 Notes for Table 3.2-1 1
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a.
The column entitled "Ref. No." is only for convenience so that a one-to-one relationship can be established between lines in Table 3.2-1 and items in Table 4.2-1.
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b.
Primary ' containment integrity shall be maintained at all times prior to withdrawing control rods for the g
pur ose of going critical, when the reactor is critical, or when the reactor water temperature is above 212 F and fuel is in the reactor vessel except while performing low power physics tests at atmospheric r.
pressure at power levels not to exceed 5 MWt.
When primary containment integrity is required, there shall be two operable or tripped trip systems for each function.
I c.
If the number of operable channels cannot be met for one of the trip systems, that trip system shall be I
tripped. However, one trip signal channel of a trip system may be inoperable for up to two (2) hours during periods of required surveillance testing without tripping the associated trip system, provided that the other j
to j
K3 remaining channel (s) monitoring that same parameter within that trip system is (are) operable.
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d.
The valves associated with each Group isolation are given in Table 3.7-1.
ff e.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power g,
at greater than 20% rated power, the normal full power radiation background level and associated g
trip setpoints may be changed based on a calculated value of the radiation level expected during j?
the test. The background radiation level and associated trip setpoints may be adjusted during, the test based on either calculations or measurements of actual radiation levels resulting from i
fI hydrogen injection. The background radiation level shall be determined and associated trip i
setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels af ter completion 1
In of hydrogen injection and prior to establishing reactor power levels below 20% rated. power.
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U TABLE 3.2-8 (cont.)
f Required Ref.
Trip Operable Action to be taken if gg No.
Inggrument Condition Channels Trip Setting there are not two operable (a)-
Nomenclature per Trip or tripped trip systems Remarks System (b) y e
5.
Main Steam Line Hi 2
43 times Isolate the mechanical One trip per trip Radiation Monitor normal full vacuum pump and the logic system will power background gland seal condenser isolate the (e) exhauster mechanical vacuum l pump and the gland seal condenser exhauster.
u K3 a.
The column entitled "Ref. No." is only for convenience so that a one-to-one relationship can be established
{g between items in Table 3.2-8 and items in Table 4.2-8.
b.
Whenever the systems are required to be operable, there shall be two operable or tripped trip systems.
If this cannot be met, the indicated action shall be taken.
EY c.
In the event that both off-gas post treatment radiation monitors become inoperable, the reactor shall be 8-placed in the Cold Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless one monitor is sooner made operable, or adequate alternative monitoring facilities are available.
Ef d.
From and after the date that one of the two off-gas post treatment radiation monitors is made or found to be inoperable, continued reactor power operation is permissible during the next fourteen days (the 0
allowable repair time), provided that the inoperable monitor is tripped in the downscale position.
Rl e.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power in at greater than 20% rated power, the normal full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels af ter completion of hydrogen injection and prior to establishing reactor power levels below 20% rated power.
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