ML17341B548
| ML17341B548 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/29/1982 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17341B547 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 GL-82-16, NUDOCS 8301040710 | |
| Download: ML17341B548 (18) | |
Text
ATTACHMENT 1 The proposed amendment is described below and shown on the accompanying
, Technical Specifications, Pages:
have been added.
Table 3.5-4 (Contd.
The setpoints for Containment Radioactivity High has been added.
Table 4.1-.1 (Sheet 4)
The surveillance requirements for the high containment radioactivity channels have been modified.
Table 4.1-1 Sheet 3)
The surveillance requirements for the Turbine Trip'have been added (Auto-Stop Oil Pressure switches)
~Pa e 6-21 The requirement for prompt reporting of pressurizer PORV's and safety valves failure has been added.
Pa e B2.3-3 The reactor trip upon turbine trip concept has been added.
8301040710 821229 PDR ADQCK 05000250.
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After shutdown, corrective. action shall be taken before operation is resumed.
F.
Above 2% of rated power, two leak detection systems of different principles shall be operable, one of which is sensitive to radioactivity.
The latter may be out of service for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided 1)
Two other systems are operable and.2) containment
, purge valves are maintained closed.
g.
Reactor Coolant System leakage shall be limited to 1 gpm 'total primary-to-second'ary leakage through all steam generators not isolated from the Reactor Coolant System and 500 gallons per day through any one steam generator not isolated from the Reactor Coolant system.
4.
MAXIMUMREACTOR COOLANT ACTIVITY The total specific activity of the reactor coolant due to,nuclides with half-lives of more than 30 minutes, excluding tritium, shall not exceed 135/E* pCi/cc whenever the reactor is critical or average reactor coolant temperature is greater than 500F.
The concentration of radioiodine in the reactor coolant shall be limited to 1.0 microcurie/gram during normal operation and to 30 microcuries/gram during power transients.
If the limit above -is not satisfied, the reactor shall be shutdown and cooled to 500 F or less within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- E is the average.of beta and gamma energy (Hev) per disintergration of the specific activity.
Amendment Nos.
81
& 75
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V TABLE 3.5-3 INSTRUMENT OPERATING CONDITIONS FOR ISOLATION FUNCTIONS NO.
FUNCTIONAL UNIT MIN.
OPERABLE CHANNELS MIN.
'DECREE OF REDUN-DANCY 3
OPERATOR ACTION IF COiNDITIOi"5 OF COLUMN 1 OR 2 CANNOT BE MET 1.2 1 3 CONTAINMENT ISOLATION Manual Safety Injection High Containment Pressure 2
See Item No. l of Table 3.5-2 See Item 2.1 of Table 3.5-2 Cold Shutdown Cold Shutdo.~
Cold Shutdown 2.
STEAM LINE ISOLATION 2.1 High Steam Flow in 2/3 Lines and 2/3 Low T or 2/3 Low avg Steam Pressure
'I 2.2 High Containment Pressure 2.3 Manual See Item 1.5 in Table 3.5-2 See Item No. 2,1 of Table 3.5-2 1/line Cold Shutdown Cold Shutdown Hot Shutdown 3.
FEEDWATER LINE ISOLATION 3.1 Safety Injection PURGE ISOLATION See Item No.
1 of Table 3.5-2 Cold Shutdown P
4.1 Containment High Radioactivity 0
Must actuate two push 'buttons simultaneously-
- Either particulate or'.gaseous
- With Tavg at or above 200 7, and with less than the minimu'm operable
- channels, operations may continue provided the containment purge valves are maintained closed.
3/i 6/73
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TABLE 3.5-4 {Contd.)
NO.
FUNCTIONAL UNIT 10.
Containment Radioactivity High CHANNEL ACTION Close Purge valves**
SET POINT Particulate (R-11)
~6.1 X 105 CPM**
Gaseous
.(R-12)
See Note 1 **
Turbine Auto-stop Oil Pressure-Low
- 1) Turbine Trip
- 2) Reactor Trip above P-7 C45 psig 12.
Turbine Stop Valves
- 1) Turbine Trip
- 2) Reactor Trip above P-7 Both valves closed NOTE 1 R-12 Setpoint
=
(3.2 X 10 )
CPM, where F = Actual Pur e Flow 4
(
F
)
Design Purge Flow (35,000 CFM)
Set point may vary according to current plant conditions provided that release rate does not exceed allowable limits specified on TS.3.9.2.b.
0 Vith Tavg at or above 200 F,
these setpoints could be higher provided that the purge valves are maintained closed.
A purge may be initiated if either setpoint is higher than the allowable value, if the other setpoint is at or below its allowable value.
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TABLE l. l-l SIIEET 4 Using moveable in-core detector system.
Frequency only Effluent monitors only and R-ll & R-12.
Calibration for effluent monitors shall be as speci. fied in 3.9.
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H.A.
Each Shift Daily Weekly Every Two Weeks Hontiily Quarterly Prior to each startup if not done previous week Each Refueling Shutdown Annually Hot appliable H.A. during cold or refueling shutdowns.
The specified tests, however, shall be performed within one surveillance interval prior to startup.
.H.A. during cold or refueling shutdowns.
The specified tests, however, shall be performed within one surveillance interval prior to heatup above 200F.
Rmen<hnent Nos.
70 5 63
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TABLE 4.l-l SIIFET 3 Check Calibrate Test Remarks 23.
Environmental Radiological Honitors 2I.
Loggic Channels
'5.
Emer. Portable Survey Instruments 26.
Seismograph H.A.
N.A.
N.A.
N. A.
A(l).
H(l)
N.A.
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H. A.
(1) Flow Hake trace.
Test battery
{change semi-annually) 27.
Auxiliary Feedwater Flow Rate 20.
RCS Subcooling Hargin Honitor 29.
PORV Position Indicator
{Primary Oetector) 30.
PORV Block Valve Position indicator 3 I ~
Sa fe ty Val ve Pos I t Ion Ind Ica tor 32.
Loss of Voltage {both 1kv busses)
H.A.
N.A N.A H.A.
N. A.
N.A.
H.A.
Check consists of monitoring indicated position and verifying by. observation of related parameters For AFW actuation at power'only 33.
Trfp of both Hain Feedwater Puiii~i Oreakers.
34.
Turbine Trip (Auto-Stop Oil Pressuxe Switches)
H.A.
N.A.
H.A.
R.
N.A.
For AFW actuation at power only Amendment Hos.
70 5 63
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NOTE:
This item is intended to problems.
(10) Failure of the pressurizer PORVs or safety valves.
b.
Thirt Da Mr'tten Re orts The reportable occurrences discussed'elow shall be the subject of written reports to the Director of the appropriate Regional Officq within thirty days of occurrence of the event.
The written report shall include, as a minimum, a completed copy or a licensee event report form.
Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
(1)
Reactor protection system or engineered safety feature instrument settings which are found to be less conserv-ative than those established by the technical specifications but which do nor prevent the fulfillment of the functional requirements of affected systems.
(2)
Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or
. plant shutdo:~ requ'red by a limiting condition fo operation.
Note:
Routine surveillance testing, instrument calibration, or preventative maintenance which require system con'figurations as described in items 2.b(l) and 2.b(2) need not be reported except where test results themselves reveal a degraded mode as described above.
(3)
Observed inadequacies in tne implementation of admin-istrative or procedural controls which threaten to:
cause reduction of degree of redundancy provided in reactor protection systems or enginered safety feature systems.
(4)
Abnormal degradation of systems other, than those specified in item 2.a(3) above designed to contain radioactive material resulting from the fission process.
Note:
Sealed sources or cal'bration sources are not included under this item.
Leakage of valve packing or gaskets within the limits for identified leakage set forth in technical specifications need not be reported under this item.
6-21 11/26/75
Reactor Tri Interlocks Specified reactor trips are by passed at low power where they are not required for protection and would otherwise interfere with normal operation.
The prescribed set points above which these trips are made functional assures their availability in the power range where needed.
An automatic reactor trip will occur if any pump is lost above 55%
power which will prevent the minimum value of the DNBR from going below 1.30 during normal and anticipated transient operations when only.two loops are in service, (9) and the over temperature AT trip setpoint is adjusted to the value specified for three loop operation.
A turbine trip initiates a reactor trip.
On decreasing
- power, the turbine trip is automatically blocked by P-7; and on increasing power reinstated automatically by P-7.
Reset of reactor trip interlocks will be done under strict administrative control.
REFERENCES (1)
FSAR 14. l. 1 (2)
FSAR 14.1.2 (3)
FSAR 14.1 (4)
FSAR 7.2, 7.3 (5)
FSAR 3.2.1 (6)
FSAR 14.3.1 (7)
FSAR 14 (Page 14-3) and 14.1.9 (8)
FSAR 14.1.11 (9)
FSAR 14.1.9 (10)
WCAP-8074 B2. 3-3 7/12/73
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STATE OF FLORIDA
)
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COUNTY OF DADE
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ss.
J.
W. Williams, Jr., being first duly sworn, deposes and says:
That he is.
Vice President Light Company, the herein; of Florida Power That he has executed the foregoing document; that the state-ments made in this said
- document, are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said J.
W. Williams, Jr.
Subscribed and swo~n to before me this day of 19 /8 NOTA' UBLIC, i.
nd fo the County of Dade, Stdt& of"-r=lorida NOTARY PU8UC STATE OF FLORIDA AT LARGE MY COMMISSION EXPIRES DEC II 1984 i<y corn'mi'ssion exPires:
8oNDED XHRv GENERAL INS. UNDERwRITERS
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