Text

Proposed Changes to Tech Specs Pages 3/4 4-36,3/4 3-40, 3/4 3-57,3/4 6-19 & B3/4 4-14,per Generic Ltr 83-37 & NUREG- 0737
	ML20083B359
Person / Time
Site:	Farley
Issue date:	12/12/1983
From:	; ALABAMA POWER CO.
To:	;
Shared Package
ML20083B354	List: ML20083B353; ML20083B359;
References
	RTR-NUREG-0737, RTR-NUREG-737 GL-83-37, NUDOCS 8312210121
	Download: ML20083B359 (11)
	v • d • e

r-Attachment 2 Proposed Changes to T.S. Pages Unit 1 Page 3/4 4-36 Page 3/4 3-40 Page 3/4 3-57 Page 3/4 6-19 Page B3/4 4-14 Unit 2 Page 3/4 4-36 Page 3/4 3-40 Page 3/4 3-57 Page 3/4 6-19 Page B3/4 4-14

(

i 8312210121 831212 PDR ADOCK 05000348 '

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REACTOR COOLANT SYSTEM 3/4.4.12 REACTOR VESSEL HEAD VENTS LIMITING CONDITION FOR OPERATION 3.4.12 At least one of the two reactor vessel head vent system paths, consisting of two valves in series powered from the Auxiliary Building D.C. Distribution System, shall be OPERABLE and closed.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With both reactor vessel head vent system paths inoperable, maintain the inoperable vent paths closed with power removed from the valve actuators of all valves in the inoperable vent paths; restore at least one of the vent paths to OPERABLE status within 30 days or be in H01 STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.12 Each reactor vessel head vent system shall be demonstrated OPERABLE at leart once per 18 months by:

a. Verifying all manual isolation valves in each vent path are locked in the open position.

b. Operating each valve in the vent system through one cycle of full travel from the control room during COLD SHUTDOWN or REFUELING.

c. Verifying flow through the reactor vessel head vent systems by t venting during COLD SHUTDOWN or REFUELING.

FARLEY-UNIT 1 3/4 4-36

TABLE 3.3-6 (Continued)

ACTION STATEMENTS l

3 ACTION 23 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 24 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.7.1.

ACTION 25 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12 and 3.9.13.

ACTION 26 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 27 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.

ACTION 27a - With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirement, initiate the preplanned alternate method of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1) Either restore the inoperable Channel (s) to OPERABLE status within 7 days, or

2) Prepare and submit a Special Report to the Coninission pursuant to Specification 6.9.2 within the next 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for resto' ring the system to OPERABLE status,

a. With fuel in storage pool.

b. With irradiated fuel in the storage pool.

c. Above background with no flow.

d. With mini-purge in operation.

e. With slow speed main purge in operation.

f. With fast speed main purge in operation.

FARLEY-UNIT 1 3/4 3-40

TABLE 3.3-11 s ACCIDENT MONITORING INSTRUENTATION ie Q REQUIRED MINIMUM

, NUMBER CHANNELS c- INSTRUMENT OF CHANNELS OPERABLE 5

1. Reactor Coolant Outlet Temperature-T ot-Wide h Range 2 1

2. Reactor Coolant Inlet Temperature-Tcold-Wide Range 2 1

3. Reactor Coolant Pressure-Wide Range 2 1

4. Steam Generator Water Level-Wide Range or Narrow Range 2/ steam generator 1/ steam generator

5. Refuelinq later Storage Tank Water Level 2 1

6. Containment Pressure 2 1

7. Pressurizer Water Level 2 1

8. Steam Line Pressure 2/ steam generator 1/ steam generator j 9. Auxiliary Feedwater Flow Rate 2 1 y 10. Reactor Coolant System Subcooling Margin Monitor 2 1 -

$ *11. PORV Position Indicator 1/ valve 1/ valve

- 12. PORV Block Valve Position Indicator 1/ valve 1/ valve

13. Safety Valve Position Indication (One channel 2/ valve 1/ valve is position indicator and one channel is discharge temperature)

14. Containment Water Level - Narrow Range 1*** 1*** {

15. Containment Water Level - Wide Range 2 1

16. Incore Thermocouples 4/ core quadrant 2/ core quadrant

Not applicable if the associated block valve is in the closed position.

- Not applicable if the block valve is verified in the closed position and power removed.

- - 0peration may continue up to 30 days with less than minimum channels operable for narrow range l instruments.

l T

CONTAINMENT SYSTEMS 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS LIMITING CONDITION FOR OPERATION 3.6.4.1 Two independent containment hydrogen analyzers shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

a. With one hydrogen analyzer inoperable, restore the inoperable analyzer to OPERABLE status within 30 days or be in at least H0T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With both hydrogen analyzers inoperable, restore at least one analyzer to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.4.1 Each hydrogen analyzer shall be demonstrated OPERABLE at least once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using sample gases containing:

a. Ten volume percent hydrogen, balance nitrogen, for zero check.

b. Ten volume percent hydrogen, balance nitrogen, mixed with compressed air, for span check.

FARLEY-UNIT 1 3/4 6-19

REACTOR COOLANT SYSTEM BASES The use of the composite curve is necessary to set conservative heatup limitations because 11, is possible for conditions to exist such that over the course of the heatup ramp the controlling condition switches from the inside to the outside and the pressure limit most at all times be based on analysis of the most critical criterion.

Finally, the composite curves for the heatup rate data and the cooldown rate data are adjusted for possible errors in the pressure and temperature sensing instruments by the values indicated on the respective curves.

Although the pressurizer operates in temperature ranges above those for which there is reason fo* concern of non-ductile failure, operating limits are provided to assure compatibility of operation with the fatigue analysis performed in accordance with the AMSE Code requirements.

The OPERABILITY of two RHR relief valves or an RCS vent opening of greater than or equal to 2.85 square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10CFR Part 50 when one or more of the RCS cold legs are less than or equal to 310*F. Either RHR relief valve has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to either (1) the start of an idle RCP with the secondary water temperature of the steam generator less than or equal to 50*F above the RCS cold leg temperatures or (2) the start of 3 charging pumps and their injection into a water solid RCS.

3/4.4.11 STRUCTURAL INTEGRITY The intervice inspection and testing programs for ASME Code Class 1, 2 and 3 components ensure that the structural integrity and operational readiness of these components will be maintained at an acceptable level throughout the life of the plant. These programs are in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10CFR Part 50.55a(g) except where specific written relief has been granted by the Commission pursuant to 10CFR Part 50.55a (g)(6)(1).

3/4. 4.12 Reactor Vessel Head Vents The OPERABILITY of the Reactor Head Vent System ensures that adequate core cooling can be maintained in the event of the accumulation of non-condensable gases in the reactor vessel. This system is in accordance with 10CFR50.44(c)(3)(i11).

FARLEY-UNIT 1 B 3/4 4-14

REACTOR COOLANT SYSTEM 3/4.4.12 REACTOR VESSEL HEAD VENTS LIMITING CONDITION FOR OPERATION 3.4.12 At least one of the two reactor vessel head vent system paths, consisting of two valves in series powered from the Auxiliary Building D.C. Distribution System, shall be OPERABLE and closed.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With both reactor vessel head vent system paths inoperable, maintain the inoperable vent paths closed with power removed from the valve actuators of all valves in the inoperable vent paths; restore at least one of the vent paths to CPERABLE status within 30 days or be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTD0WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.12 Each reactor vessel head vent system shall be demonstrated OPERABLE at least once per 18 months by:

a. Verifying all manual isolation valves in each vent path are locked in the open position.

b. Operating each valve in the vent system through cne cycle of full travel from the control room 6uring COLD SHUTDOWN or REFUELING.

c. Verifying flow through the reactor vessel head vent systems by l Venting during COLD SHUTDOWN or REFUELING.

I i

l

FARLEY-UNIT 2 3/4 4-36 l

l

TABLE 3.3-6 (Continued) ,

< ACTION STATEENTS

]

ACTION 23 -- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring j instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 24 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.7.1.

ACTION 25 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the

., ACTION requirements of Specification 3.9.12 and 3.9.13. ,

ACTION 26 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the '

ACTION requirements of Specification 3.9.9.

ACTION 27 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.

i ACTION 27a - With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirement, initiate the preplanned alternate method of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1) Either restore the inoperable Channels (s) to OPERABLE

! status within 7 days, or I

i. ?) Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule I for restoring the system to OPERABLE status,

a. With fuel in storage pool.

b. With irradiated fuel in the storage pool.

l c. Above background with no fla.

l d. With mini-purge in operation.

~ e. With slow speed main purge in operation.

f. With fast speed main purge in operation.

FARLEY-UNIT 2 3/4 3-40 l

l l

t

TABLE 3.3-11 l ACCIDENT MONITORING INSTRUENTATION

, m E REQUIRED MINIMUM E NUMBER CHANNELS

) INSTRUMENT OF CHANNELS OPERABLE

, 1. Reactor Coolant Outlet Temperature-T ot-Wide h Range 2 1 l

89 2. Reactor Coolant Inlet Temperature-Tcold-Wide Range 2 1

3. Reactor Coolant Pressure-Wide Range 2 1

4. Steam Generator Water Level-Wide Range or Narrow Range 2/ steam generator 1/ steam generator

5. Refueling Water Storage Tank Water Level 2 1

6. Containment Pressure 2 1

! 7. Pressurizer Water Level 2 1

8. Steam Line Pressure 2/ steam generator 1/ steam generator

{ R 9. Auxiliary Feedwater Flow Rate 2 1 j [ 10. Reactor Coolant System Subcooling Margin Monitor 2 1 l h) *11. PORY Position Indicator 1/ valve 1/ valve

} **12. PORY Block Valve Position Indicator 1/ valve 1/ valve

13. Safety Valve Position Indication (One channel 2/ valve 1/ valve

, is position indicator and one channel is discharge temperature)

14. Containment Water Level - Narrow Range 1*** 1*** l i

15. Containment Water Level - Wide Range 2 1 y 16. Incore Thermocouples 4/ core quadrant 2/ core quadrant

) *Not applicable if the associated block valve is in the closed position.

- Not applicable if the block valve is verified in the closed position and power removed.

- - 0peration may continue up to 30 days with less than minimum channels operable for narrow range l I i nstruments.

-,w

CONTAINMENT SYSTEMS 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDR 0 GEN ANALYZERS LIMITING CONDITION FOR OPERATION 3.6.4.1 Two independent containment hydrogen analyzers shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

a. With one hydrogen monitor inoperable, restore the inoperable l analyzer to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With both hydrogen monitors inoperable, restore at least one monitor to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.4.1 Each hydrogen analyzer shall be demonstrated OPERABLE at least once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using sample gases containing:

a. One volume percent hydrogen, balance nitrogen, for zero check.

b. Four volume percent hydrogen, balance nitrogen, mixed with compressed air, for span check.

FARLEY-UNIT 2 3/4 6-19

. - - - - - - -. . - - - - - _ . . - - - . . - =

REACTOR COOLANT SYSTEM BASES j i -

The use of the composite curve is necessary to set conservative heatup limitations because it is possible for conditions to exist such that over the course of the heatup ramp the controlling condition i switches from.the inside to the outside and the pressure limit must at all times be based on analysis of the most critical criterion.

Finally, the composite curves for the heatup rate data and the cooldown rate data are adjusted for possible errors in the pressure and ,

temperature sensing instruments by the values indicated on the respective curves.

l i

Although the pressurizer operates in temperature ranges above those for which there is reason for concern of non-ductile failure, operating !

limits are provided to assure compatibility of operation with the '

, fatigue analysis performed in accordance with the AMSE Code j requirements.

l The OPERABILITY of two RHR relief valves or an RCS vent opening of greater than or equal to 2.85 square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10CFR Part 50 when one or more of the RCS cold legs are less than or equal to 310*F. Either RHR relief valve has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to either (1) the start of an idle RCP with the secondary water temperature of the steam generator less than or equal to

50*F above the RCS cold leg temperatures or (2) the start of 3 charging pumps and their injection into a water solid RCS.

4 3/4.4.11 STRUCTURAL INTEGRITY The inservice inspection and testing programs for ASME Code Class 1, ,

2 and 3 components ensure that the structural integrity and operational readiness of these components will be maintained at an acceptable level

throughout the life of the plant. These programs are in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addende as required by 10CFR Part 50.55a(g) except where specific written rclief has been granted by the Commission pursuant to 10CFR Part 50.55a (g)(6)(1).

-3/4. 4.12 Reactor Vessel Head Vents The OPERABILITY of the Reactor Head Vent System ensures that adequate core cooling can be maintained in the event of the accumulation

, of non-condensable gases in the reactor vessel. This system is in t

accordance with 10CFR50.44(c)(3)(fii).

4 FARLEY-UNIT 2 B 3/4 4-14

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ML20083B359

Text

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