ML17216A258

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Proposed Tech Specs Re Accident Monitoring Instrumentation Tables
ML17216A258
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 07/19/1985
From:
FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17216A257 List:
References
RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8507290469
Download: ML17216A258 (16)
v • d • e


Text

ATTACHMENT I CHANGES TO TECHNICAL SPECIFICATIONS ST. LUCIE UNIT I DPR-67

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e TABLE 3.3-11 ACCIDENT NON ITORING INSTRUHENTATION HINIHUH TOTAL NO. ,CIIANNELS INSTRUHENT OF CIIANNI:LS 01'LIIABLE ACTION n'

1. Pressurizer Mater Level ~

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2. Auxiliary Feedwater Flow Rate 1/pump 1/pump
3. RCS Subcooling Hargin Honitor
4. PORV Position Indicator Acoustic Flow Honitor 1/valve 1/valve
5. PORV Block Valve Position Indicator 1/valve 1/valve
6. Safety Valve Position Indicator 1/valve 1/val ve . 3
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TABLE 3.3-I I (Continued)

ACTION STATEMENTS ACTION I- With the number of OPERABLE channels less than required by Table 3.3-I I, either restore the inoperable channel(s) to OPERABLE status within 30 days or be in HOT STANDBY within the next l2 hours.

ACTION 2- With position indication inoperable, restore the inoperable indicator to OPERABLE status or close the associated PORV block valve and remove power from its operator within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 3- With any individual valve position indicator inoperable, obtain quench tank temperature, level and pressure information once per shift to determine valve position.

ACTION 4- With the number of OPERABLE Channels one less than the Total Number of Channels shown in Table 3.3-I I, either restore the inoperable channel to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the commission pursuant to the specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

ACTION 5- With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirements of Table 3.3-I I, either restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible without shutting down or:

I. Initiate an alternate method of monitoring the reactor vessel inventory; and

2. Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and
3. Restore the Channel to OPERABLE status at the next scheduled re fueling.

St. Lucie'- Unit I 3/4 3-43

TABLE 4.3-7 I ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS C

m CkNNNEL CNANNEL INSTRUMENT CHECK CALIBRATION C

1. Pressurizer Hater Level
2. Auxiliary Feedwater Flow Rate
3. Reactor Coolant System Subcooling Hargin Monitor.
4. PORV Positio'n Indicator
5. PORV Block Valve Position Indicator R'
6. Safety Valve Postition Indicator 7,+~ g~ T BQ.~ O CAD 0 p IC,g Q, Co a)TAr Q one.~ Su mp ~~R ~Yc. l

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ATTACHMENT2 CHANGES TO TECHNICAL SPECIFICATIONS ST. LUCIE UNIT 2-NPF-I 6

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INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With the number of OPERABLE accident monitoring channels less than the Required Number of Channels shown in Table 3.3-10, either restore the inoperable channel to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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b. With the number of OPERABLE accident monitoring channels less than the Minimum Channels OPERABLE requirements of Table 3.3-10; either Add A<4<o~~ restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

+) or be $ n at 'least HOT SHUTOOHN within the next 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.

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t Sw&~lv)KAJc& TD gk 5 With the number of OPERABLE Channels one less than the Total Number of Channels shown in Table 3.3-I I, either restore the inoperable channel to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the commission pursuant to the specification 6.9.2 within 30'days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirements of Table 3.3-I I, either restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible without shutting down or:

I. Initiate an alternate method of monitoring the reactor vessel inventory; and

2. Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and
3. Restore the Channel to OPERABLE status at the next scheduled refueling.

TABLE 3.3-10 ACCIDENT NHITORIHG IHSTRNENTATIOH REQUIREO HIHINH I HUHOER OF CHANNELS IHSTRNENT CHANNELS OPERABLE M

hi Containaent Pressure .- 2 1

2. Reactor Coolant Outlet Teaperature - THot (Harrow 'ange) 2 1
3. Reactor .Coolant Inlet Teaperature - TCold (Mide Range) 2 1
4. Reactor Coolant Pressure - Mide Atange . 2 l.

S. Pressurizer Mater Level 2

6. Steaa Generator Pressure 2/steaa generator 1'/steaa generator

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7. Steaa Generator Mater Level - Harrow Range ]/steaa generator 1/steaa generator EAR
8. /team Generator Mater level - Mide Range ]/steaa generators ]/steaa generator" EAI I S. Refueling Mater Storage Tank Mater Level 2 1 tO

]O. Auxiliary feedwater Flow Rate (Each puap) ]/PuePA

)). Reactor Cooling System Subcooling Hargin Honitor 2 1

12. PORV Position/F low Indicator 2/valve*~ 1/valve ~*
13. PORV Block Valve Position Indicator ]/valve*" ]/valve~e

]4. Safety Valve Position/Flow Indicator /val ye*RA ~

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]S. 'Containment Sump Mater Level (Harrow Range) ~

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16. Containment Mater level (Mide Range) 2 1 D.. Incore Theraocouples 4/core quadrant 2/core quadrant l 3. ReAcvoa Vessel Lc.ve I t,0+4'*~

These corresponding instruaents aay be substituted for each other.

""Hot required if .the POAV block valve is shut and power is removed froa the operator.

If not available, eonitor the quench tank pressure, level and teeperature, and each safety valve/PORV discharge piping teaperature at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

"~"~The non-safety grade containment sump'water level instrument say be substituted.

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TABLE 4.3-7 ACCIOENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS I

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M Ill CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION Containment Pressure= H R Reactor Coolant Outlet Temperature - TH 24 t (Narrow Range) H R

3. Reactor Coolant Inlet Telperature -TC ld (Wide Range) H R Reactor Coolant Pressure - Wide Range H R
5. Pressurizer Water Level '. H R
6. Steam Generator Pressure H R
7. Steam Generator Water Level - Narrow Range H R Cal 8. Steam Generator Water Level -,Wide Range H R CQ
9. Refueling Mater Storage Tank Mater Level H R D

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10. Auxiliary Feedwater Flow Rate (Each pump) H R Reactor Coolant System Subcooling Hargin Honitor H R
12. PORV Position/Flow Indicator H R
13. PORV Block Valve Position Indicator H R
14. Safety Valve Position/FLow Indicator H R.
16. Containment Sump Mater Level (Narrow Range) H R
16. Containment Mater Level (Mide Range) H R Incore Thermocouples H R Q>c'woe )j~ej 4've f 8<<~~>~~<

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ATTACHMENT3 NO S IGNIFI CANT HAZARDS CONSIDERATIONS Introduction The requested amendment to the St. Lucie Units I and 2 operciting licenses adds plant instrumentation currently installed and operational to the Technical Specifications. This addition will provide a higher degree of control and operational readiness for these instrument channels by requiring operability and monthly surveil lances of accuracy.

Evaluation The three criteria for a determination of whether a no significant hazards consideration exists, from IO CFR 50.92(c), are:

I) Involve a significant increase in the probability or consequences of an accident previously evaluated, or

2) create the possibility of a new or different kind of accident from any accident previously evaluated; or
3) involve a significant reduction in a margin of safety.

A. With respect to the first of the above criteria, the requested license amendment does not increase the probability or. consequences of accidents previously analyzed. The plant hardware and normal operating conditions are not affected by the proposed change since this equipment was previously installed and operating. Addition of monthly surveil lances on these instrument channels will not involve any significant increase in the probability or consequences of an accident previously evaluated but will assure accurate output from these instrument channels.

B. With respect to the second criteria, plant hardware and basic plant operation are not affected by the proposed. license amendment. Therefore, the possibility for a new or different type of accident is not created.

C. With respect to the third criteria, since the consequences of accidents are not increased and new or different types of accidents are not introduced by this amendment, all margins of safety will be maintained.

It is concluded from the above evaluation that this amendment involves no significant hazards considerations. Furthermore, the proposed amendment is similar to example (I I) of the Commissions examples of amendments that are considered not likely to involve significant hazards considerations in that, it is a change that'onstitutes an additional limitation, restriction or control not presently in the technical specifications.

STATE OF FLORIDA COUNTY OF DADE J. W. Williams Jr. being first duly sworn, deposes and says:

That he is a Grou Vice President of Florida Power & Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this 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 Licensee.

J. W. Williams, Jr.

Subscribed and sworn to before me this PUBLIC, in and for the County

'f,NOTA'RY Dade, S'tate of Florida My Commission expires:

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