ML17341B548

Proposed Tech Spec Changes in Response to Generic Ltr 82-16 Re NUREG-0737 Items

ML17341B548
Person / Time
Site:	Turkey Point
Issue date:	12/29/1982
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17341B547	List: ML17341B546 ML17341B548
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. t ( I P PDR

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e. 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. MAXIMUM REACTOR 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 3

MIN. OPERATOR ACTION MIN. 'DECREE IF COiNDITIOi"5 OF OPERABLE OF COLUMN 1 OR 2 NO. FUNCTIONAL UNIT CHANNELS REDUN- CANNOT BE MET DANCY CONTAINMENT ISOLATION Manual 2 Cold Shutdown 1.2 Safety Injection See Item No. l of Table 3.5-2 Cold Shutdo.~

1 3 High Containment Pressure See Item 2.1 of Table 3.5-2 Cold Shutdown

2. STEAM LINE ISOLATION 2.1 High Steam Flow in 2/3 Lines and 2/3 Low Tavg or 2/3 Low See Item 1.5 in Table 3.5-2 Cold Shutdown Steam Pressure

'I 2.2 High Containment Pressure See Item No. 2,1 of Table 3.5-2 Cold Shutdown 2.3 Manual 1/line Hot Shutdown

3. FEEDWATER LINE ISOLATION 3.1 Safety Injection See Item No. 1 of Table 3.5-2 Cold Shutdown P

PURGE ISOLATION 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 CHANNEL ACTION SET POINT

10. Containment Radioactivity High Close Purge valves** Particulate (R-11)

~6.1 X 105 CPM**

Gaseous .(R-12)

See Note 1 **

Turbine Auto-stop Oil Pressure- 1) Turbine Trip C45 psig Low 2) Reactor Trip above P-7

12. Turbine Stop Valves 1) Turbine Trip Both valves closed

2) Reactor Trip above P-7 4

NOTE 1 R-12 Setpoint = (3.2 X 10 ) CPM, where F = Actual Pur e Flow

( 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, allowable value.

if the other setpoint is at or below its

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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.

Each Shift 0 Daily W Weekly II/O Every Two Weeks Hontiily Q Quarterly Prior to each startup if not done previous week Each Refueling Shutdown Annually H.A. 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

i 0 'P TABLE 4.l-l SIIFET 3 Check Calibrate Test Remarks

23. Environmental Radiological Honitors H.A. A(l). H(l) (1) Flow 2I. Loggic Channels N.A. N.A. Il~

'5. Emer. Portable Survey Instruments N.A.

26. Seismograph N. A. H. A. Hake trace. Test battery

{change semi-annually)

27. Auxiliary Feedwater Flow Rate N. A.

20. RCS Subcooling Hargin Honitor N.A.

29. PORV Position Indicator

{Primary Oetector) N.A Check consists of monitoring indicated

30. PORV Block Valve Position indicator N.A position and verifying by. observation 3I ~ Sa fe ty Val ve Pos t I I on I nd I ca tor H.A. of related parameters

32. Loss of Voltage {both 1kv busses) H.A. H.A. For AFW actuation at power'only

33. Trfp of both Hain Feedwater Puiii~i Oreakers. H.A. H.A. For AFW actuation at power only

34. Turbine Trip (Auto-Stop Oil Pressuxe Switches) N.A. R. N.A.

Amendment Hos. 70 5 63

iO 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 shall be the subject of written reports to the Director discussed'elow 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

i5 0 STATE OF FLORIDA )

) ss.

COUNTY OF DADE )

J. W. Williams, Jr., being first duly sworn, deposes and says:

That he is. Vice President of Florida Power Light Company, the herein; 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& o f"-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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