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Amend 175 to License DPR-23,revising TS Section 3.5.1 & Tables 3.5-2,3 & 4 Concerning Reactor Trip Sys,Engineered Safety Feature Actuation Sys & Isolation Function
	ML14183A356
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Site:	Robinson
Issue date:	09/12/1996
From:	Imbro E; NRC (Affiliation Not Assigned)
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ML14183A357	List: ML14183A356; ML14183A358;
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	NUDOCS 9609190233
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NR REGj UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT KO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 175 License No. DPR-23

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Carolina Power & Light Company (the licensee), dated December 10, 1995, as supplemented August 1, 1996, and September 4, 1996, 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.

2.

Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 3.B. of Facility Operating License No. DPR-23 is hereby amended to read as follows:

9609190233 960912 PDR ADOCK 05000261 P

PDR

-2 B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 175, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 90 days.

FOR THE NUCLEAR REGULATORY COMMISSION Eugene V. Imbro, Director Project Directorate II-1 Division of Reactor Projects -

I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 12, 1996

ATTACHMENT TO LICENSE AMENDMENT NO. 175 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Pages Insert Pages 3.5-1 3.5-1 3.5-12 3.5-12 3.5-13 3.5-13 3.5-13a 3.5-13b 3.5-13c 3.5-14 3.5-14 3.5-15 3.5-15 3.5-15a 3.5-16 3.5-16 3.5-17 3.5-17 3.5-17a

3.5 INSTRUMENTATIONPYSTEMS 3.5.1 Operational Safety Instrumentation Apolicablity Applies to plant operational safety instrumentation systems.

Objective To provide for automatic initiation of the Engineered Safety Features in the event that principal process variable limits are exceeded, and to delineate the conditions of the plant instrumentation and safety circuits necessary to ensure reactor safety.

Soeci ficati on 3.5.1.1 The Engineered Safety Features initiation instrumentation setting limits shall be as stated in Table 3.5-1.

3.5.1.2 For on-line testing or in the event of a subsystem instrumentation channel failure, plant operation at rated power shall be permitted to continue in accordance with Tables 3.5-2 through 3.5-5.

In the event the number of channels in service listed in Table 3.5-5 falls below the limits given in the column entitled Minimum Channels Operable, operation snall be limited according to the requirement shown in Column 2.

3.5.1.4 The containment ventilation isolation function is only required when containment integrity is required.

3.5.1.5 In the event the number of operable channels of a particular functional unit listed in Tables 3.5-2, 3, or 4 falls below the limits given in the column entitled Total Number of Channels, operation shall be limited according to the requirement shown in Column 3.

3.5-1 Amendment No. 85,175

TABLE 3.5-2 REACTOR TRIP INSTRUMENTATION LIMITING OPERATING CONDITIONS 1

2 3

TOTAL NO.

MINIMUM OPERATOR ACTION IF OF CHANNELS COLUMN 1 OR 2 APPLICABLE NO.

FUNCTIONAL UNIT CHANNELS OPERABLE CANNOT BE MET CONDITIONS

1. Manual 2

2 ACTION 1 Reactor Critical 2

2 ACTION 8 Hot/Cold Shutdown *

2. Nuclear Flux Power Range A. High Setpoint 4

3 ACTION 2 Reactor Critical B. Low Setoint 4

3 ACTION 2 Reactor Critical **

3. Nuc ea Lux 2

2 ACTION 3 Reactor Critical **

Inte~rmeiate Rance Nuclear Flx Source Range A. S

.artu:

2 2

ACTION 4 Reactor Critical ***

Sncown 2

1 ACTION 5 Hot/Cold Shutdown Snu ctdn 2

2 ACTION 8 Hot/Cold Shutdown *

6. Overtemperature LT 3

2 ACTION 6 Reactor Critical

6. Over.ower LT 3

2 ACTION 6 Reactor Critical

7. Low Pressurizer Pressure 3

2 ACTION 6

8.

Hi Pressurizer 3

2 ACTION 6 Reactor Critical Pressure

9.

Pressurizer Hi 3

2 ACTION 6 Water Level

10. Low Reactor Coolant Flow A. Single Loop 3/loop 2/loop ACTION 6

>45% of rated power B. Two Loop 3/loop 2/loop ACTION 6 3.5-12 Amendment No. 8S, 175

TABLE 3.5-2 (Continued)

REACTOR TRIP INSTRUMENTATION LIMITING OPERATING CONDITIONS 1

2 3

TOTAL NO.

MINIMUM OPERATOR ACTION IF OF CHANNELS COLUMN 1 OR 2 APPLICABLE NO.

FUNCTIONAL UNIT CHANNELS OPERABLE CANNOT BE MET CONDITIONS

11.

Turbine Trip A. Auto Stop Oil 3

2 ACTION 6 Pressure B. Turb Stop Valves 2 2

ACTION 6

12.

Lo Lo Steam Generator 3/SG 2/SG ACTION 6 Reactor Critical Water Level Un-erfrequency 3

2 ACTION 6 Reactor Critical 4 KV SYStE

r.

Und"eve age on 3

2 ACTION 7 Reactor Critical A. ERFIS Rod 1

1 ACTION 9 Reactor Critical Position Deviation B. Quadrant Power 1

1 ACTION 10

>50% of rated power Tilt Monitor (upper and lower ex-core neutron detectors)

"Detector Current Comparator" 3.5-13 Amendment No. 85, 175

TABLE 3.5-2 (Continued)

REACTOR TRIP INSTRUMENTATION LIMITING OPERATING CONDITIONS 1

2 3

TOTAL NO.

MINIMUM OPERATOR ACTION IF OF CHANNELS COLUMN 1 OR 2 APPLICABLE NO. FUNCTIONAL UNIT CHANNELS OPERABLE CANNOT BE MET CONDITIONS

16. Low Steam Generator 2 Level 1 Level ACTION 6 Reactor Critical Level Coincident With and 2 Stm/ and 2 Stm/

Steam Flow/Feedwater Feed Flow Feed Flow Flow Mismatch Mismatch Mismatch Per SG Per SG OR 2 Level and 1 Stm/

Feed Flow Mismatch Per SG 3.5-13a Amendment No.

TABLE 3.5-2 (Continued)

REACTOR TRIP INSTRUMENTATION LIMITING OPERATING CONDITIONS TABLE NOTATIONS With the reactor trip breakers closed.

Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) setpoint.

Below the P-6 (Intermediate Range Neutron Flux Interlock) setpoint.

Above the P-10 (Low Setpoint Power Range Neutron Flux Interlock) setpoint or P-7 (Turbine First Stage Pressure Interlock) setpoint and below the P-8 (Low Setpoint Power Range Neutron Flux Interlock) setpoint.

- - - - Above the P-10 (Low Setpoint Power Range Neutron Flux Interlock) setpoint or P-7 (Turbine First Stage Pressure Interlock) setpoint.

ACTION STATEMENTS ACTION 1 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , or be in the Hot Shutdown Condition within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

ACTION 2 With the number of OPERABLE channels one less than the Total Number of Channels. Startup and/or Power Operation may proceed provided the following Conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

Either, thermal power is restricted to less than or equal to 75% of rated power and the Power Range Neutron Flux trip setpoint is reduced to less than or equal to 85% of rated power within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the Quadrant Power Tilt Ratio is monitored within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter, using the movable incore detectors to confirm that the normalized symmetric power distribution is consistent with the indicated Quadrant Power Tilt Ratio.

ACTION 3 With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the thermal power level:

a.

Below the P-6 (Intermediate Range Neutron Flux Interlock) setpoints. restore the inoperable channel to OPERABLE status prior to increasing thermal power above the P-6 setpoint.

b.

Above the P-6 (Intermediate Range Neutron Flux Interlock) setpoint but below 10% of rated power. restore the inoperable channel to OPERABLE status prior to increasing thermal power above 10% of rated power.

3.5-13b Amendment No.175

TABLE 3.5-2 (Continued)

REACTOR TRIP INSTRUMENTATION LIMITING OPERATING CONDITIONS TABLE NOTATIONS ACTION 4 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement. suspend all operations involving positive reactivity changes.

ACTION 5 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, verify compliance with Shutdown Margin within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6 With the number of OPERABLE channels one less than the Total Number of Channels. Startup and/or Power Operation may proceed until performance of the next required operational test provided the inoperable channel is placed into the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 7 With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel into the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . and restore the inoperable channel to OPERABLE status within 7 days or be in at least the Hot Shutdown Condition within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

ACTION 8 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor Trip Breakers within the next hour.

ACTION 9 Log individual rod position within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and every hour thereafter, and following load changes of >10% of rated power. or after >30 inches of control rod motion. In addition to the above ACTIONS, if both rod misalignment monitors (15.A and 15.B) are inoperable with reactor power >50% of rated power for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or more. the nuclear overpower trip shall be reset to < 93% of rated power.

ACTION 10 Log individual upper and lower ion chamber currents within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and every hour thereafter, and following load changes of >10% of rated power, or after >30 inches of control rod motion. In addition to the above ACTIONS. if both rod misalignment monitors (15.A and 15.B) are inoperable with reactor power >50% of rated power for two hours or more, the nuclear overpower trip shall be reset to < 93 percent of rated power.

3.5-13c Amendment No. 175

TABLE 3.5-3 ENGINEERED SAFETY FEATURES INSTRUMENTATION LIMITING OPERATING CONDITIONS 1

2 3

TOTAL NO.

MINIMUM OPERABLEACTION IF OF CHANNELS COLUMN 1 OR 2 APPLICABLE NO.

FUNCTIONAL UNIT CHANNELS OPERABLE CANNOT BE MET CONDITIONS

1.

SAFETY INJECTION A. Manual 2

2 ACTION 11

>200OF B. High Containment 3

2 ACTION 12

>200*F Pressure (Hi Level)

C. High Differential 3/Steam 2/Steam ACTION 12 Pressure between Line Line Any Steam Line and the Steam Header D. Pressurizer Low 3

2 ACTION 12 Pressure E. High Steam Flow In 2/Steam 1/Steam ACTION 12

>3500F ##

2/3 Steam Lines Line Line and Coincident with and 1 T& in Low T i n 1I To 2 Loops 2/3 loops Loop OR 2/Steam Line and 1 Tavg F. High Steam Flow In 2/Steam 1/Steam ACTION 12

>350aF ##

2/3 Steam Lines Line and Line and Coincident with 1 Press/

1 Press in Low Steam Line 2 Lines Pressure in OR 2/3 lines 2/Steam Line and 1 Press

2.

CONTAINMENT SPRAY A. Manual 2

2 ACTION 13

>200*F B. High Containment 3/Set 2/Set ACTION 12

>2000F Pressure (Hi Hi Level) 3.5-14 Amendment No. gB, 175

TABLE 3..5-3 (Continued)

ENGINEERED SAFETY FEATURES INSTRUMENTATION LIMITING OPERATING CONDITIONS 1

2 3

TOTAL NO.

MINIMUM OPERABLE ACTION IF OF CHANNELS COLUMN 1 OR 2 APPLICABLE NO.

FUNCTIONAL UNIT CHANNELS OPERABLE CANNOT BE MET CONDITIONS

3.

LOSS OF POWER A. 480V Emerg. Bus 2/Bus 1/Bus ACTION 14 Reactor Undervoltage Critical (Loss of Voltage)

B. 480V Emerg. Bus 3/Bus 2/Bus ACTION 14 Reactor Undervoltage Critical (Degraded Voltage) 3.5-15 Amendment No. 87, 136, 175

)

TABLE 3.5-3 (Continued)

ENGINEERED SAFETY FEATURES INSTRUMENTATION LIMITING OPERATING CONDITIONS TABLE NOTATIONS Above Low Pressure SI Block Permit interlock.

Trip function may be blocked below Low T, Interlock setpoint.

The reactor may remain critical below the Power Operating conditions with this feature inhibited for the purpose of starting reactor coolant pumps.

ACTION 11 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least the Hot Shutdown Condition within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and the Cold Shutdown Condition within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 12 With the number of OPERABLE channels one less than the Total Number of Channels.

Power Operation may proceed until performance of the next required operational test provided the inoperable channel is placed into the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 13 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least the Hot Shutdown Condition within.the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and the Cold Shutdown Condition within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 14 With the number of OPERABLE channels one less than the Total Number of Channels: place the inoperable channel into the blocked condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . and restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least the Hot Shutdown Condition within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and the Cold Shutdown Condition within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

3.5-15a Amendment No. 175

TABLE 3.5-4 ISOLATION FUNCTIONS INSTRUMENTATION LIMITING OPERATING CONDITIONS 1

2 3

TOTAL NO.

MINIMUM ' OPERABLE ACTION IF OF CHANNELS COLUMN 1 OR 2 APPLICABLE NO.

FUNCTIONAL UNIT CHANNELS OP.ERABLE CANNOT BE MET CONDITIONS

1.

CONTAINMENT ISOLATION A. Phase A

i.

Safety Injection See Item No. 1 of Table 3.5-3 for all Safety Injection initiating functions and requirements ii.

Manual 2

2 ACTION 11

>200*F B. Phase B See Item No. 2 of Table 3.5-3 for all Containment Spray initiating functions and requirements C. Ventilation Isolation

i.

High Containment 1

0 ACTION 15 During Activity. Gaseous Containment Purge ii. High Containment 1

0 ACTION 15 During Activity.

Containment Particulate Purge iii.Phase A See Item No. 1.A of Table 3.5-4 for all Phase A initiating functions and requirements 3.5-16 Anendment No. 8S 175

TABLE 3.5-4 (Continued)

ISOLATION FUNCTIONS INSTRUMENTATION LIMITING OPERATING CONDITIONS 1

2 3

TOTAL NO.

MINIMUM OPERABLE ACTION IF OF CHANNELS COLUMN 1 OR 2 APPLICABLE NO.

FUNCTIONAL UNIT CHANNELS OPERABLE CANNOT BE MET CONDITIONS

2.

STEAM LINE ISOLATION A. High Steam Flow in See Item No. 1.E of Table 3.5-3 for initiating 2/3 Steam Lines functions and requirements Coincident with Low TV, in 2/3 loops B. High Steam Flow in See Item No. 1.F of Table 3.5-3 for initiating 2/3 Steam Lines functions and requirements Coincident with Low Steam Pressure in 2/3 lines C. High Containment See Item No. 2.B of Table 3.5-3 for initiating Pressure functions and requirements (Hi Hi Level)

D. Manual 1/Line 1/Line ACTION 16

>350*F

3.

FEEDWATER LINE ISOLATION A. Safety Injection See Item No. 1 of Table 3.5-3 for all Safety Injection initiating functions and requirements 3.5-17 Amendment No. 5, 175

ABLE 3.5-4 (Continued)

ISOLATION FUNCTIONS INSTRUMENTATION LIMITING OPERATING CONDITIONS TABLE NOTATIONS ACTION 15 With less than the Total Number of Channels, Power Operations may continue provided the Containment Ventilation Purge and Exhaust valves are maintained closed.

ACTION 16 With the number of channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take the ACTION required by Specification 3.4.3.

3.5-17a Amendment Noi175

ML14183A356

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