ML20059A871

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Proposed Tech Specs Implementing Changes Identified in Generic Ltr 93-05, Line Item TS Improvements to Reduce SRs for Testing During Power Operation
ML20059A871
Person / Time
Site: Waterford Entergy icon.png
Issue date: 12/23/1993
From: Barkhurst R
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20059A868 List:
References
GL-93-05, GL-93-5, NUDOCS 9401030176
Download: ML20059A871 (14)
v • d • e


Text

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9 TABLE 4.3-3 k RADIATION MONITORING INS 1RUMENTATION SURVEILLANCE REQUIREMENTS -

Nf "O

CHANNEL MODES FOR WHICH g CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE 3g, INSTRUMENT CHECK CALIBRATION TEST IS REQUIRED CO RG$ 1. AREA MONITORS

a. Fuel Stora e Pool Area O$ " fuel Handl ng Building

. @y Ventilation System gy Isolation S R H

  • 8 b. Containment - Purge &

E & ust Isolation S R H 1, 2, 3, 4 & **

2. PROCESS HONITORS
a. Containment /,tmosphere y 1) Gaseous Activity - *
  • RCS Leakage Detection S R H 1, 2, 3, & 4 w

h 2) Particulate Activity

  • RCS. Leakage Detection S R H 1, 2, 3, & 4
b. Control Room Intake Monitors S R H ALL H00ES
c. Steam Generator Blowdown Monitor S R H -

1, 2, 3, & 4

-d. Component Cooling Water System S R H ALL H0 DES

e. Component Cooling Water System 5 R H ALL H0 DES
  • With irradiated fuel in the storage pool.
    • buring. CORE ALTERATIONS or movement of irradiated fuel within the containment.

_. --______ - _ _ : a

e e

~

TABLE 4.3-3 (Continued) .

c h
o RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ',*

$ CHANNEL MODES FOR WHICH E CHANNEL CilANNEL FUNCTIONAL SURVEILLANCE

  • INSTRUMEKf CHECK CALIBRATION TEST 15 REQUIRED E

q 3. EFFLUENT ACCIDENT MONITORS w

a. Containment High Range S R H 1, 2, 3, & 4
b. Plant Stack High Range S R H 1, 2, 3, & 4
c. Condenser Vacuus Pump High Range S R M 1, 2, 3, & 4 m d. Fuel llandling Building g Exhaust High Range 5 R H 1*, 2*, 3*, & 4*
e. Main Steam Line High Range ,S R H 1, 2, 3, & 4
  • With irradiated fuel in the storage pool.

. 1 4

i-l REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

d. Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. i
e. Monitoring the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4.4.5.2.2 Each Reactor Coolant System pressure isolation valve specified in Table 3.4-1, Section A and Section B, shall be demonstrated OPERABLE by verifying leakage to be within its limit:

At least once per 18 months, a.

b. Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been performed in the previous 9 months,  ;
c. Prior to returning the valve to service following maintenance, repair, or replacement work on the valve,
d. Following valve actuation for valves in Section B due to automatic or manual action.or flow through the valve:
1. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying valve closure, and
2. Within 31 days by verifying leakage rate.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

4.4.5.2.3 Each Reactor Coolant System pressure isolation valve power-operated  ;

valve specified in Table 3.4-1, Section C, shall be demonstrated OPERABLE by verifying leakage to be within its limit I

a. At least once per 18 months, and 1
b. Prior to returning the valve to service following maintenance, repair, or replacement work on the valve.

The provisions of Specification 4.0.4 are not ' applicable for entry into MODE 3 i or 4. l i

l l

l VATERFORD - UNIT 3 3/4 4-19

1  ;

REACTOR COOLANT SYSTEM 3/4.4.3 PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.3.1 The pressurizer shall be OPERABLE with:

a. A steady-state water volume greater than or equal to 26% indicated level (350 cubic feet) but less than or equal to 62.5% indicated level (900 cubic feet), and,
b. At least two groups of pressurizer heaters powered from Class 1E buses each having a nominal capacity of 150 kW.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With only one group of the above required pressurizer heaters OPERABLE, restore at least two groups to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least 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 /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. With the pressurizer otherwise inoperable, be in at least HOT STANDBY with the reactor trip breakers open.within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.3.1.1 The pressurizer water volume shall be determined to be within its l limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.3.1.2 The capacity of each of the above required groups of pressurizer l-heaters shall be verified to be at least 150 kW at least once per 92 days.

4.4.3.1.3 The emergency power supply for the pressurizer heaters shall be- l demonstrated OPERABLE at least once per 18 months by:

a. Verifying the above pressurizer heaters are automatically shed from the emergency power sources upon the injection of an SIAS test signal.
b. Verifying that the above heaters can be manually placed and energized on the emergency power source from the control room.

WATERFORD - UNIT 3 3/4 4-9 Amendment No.- 22

t PLAsl' SYSTEMS EMERGENCY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator emergency feedwater pumps and associated flow paths shall be OPERABLE with:

a. Two feedwater pumps, each capable of being powered from separate OPERABLE emergency busses, and
b. One feedwater pump capable of being powered froc an OPERABLE steam supply system.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With one emergency feedwater pump inoperable, restore the required emergency feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. With two emergency feedwater pumps inoperable be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c. With three emergency feedwater pumps inoperable, immediately initiate corrective action to restore at les.tt one emergency feedwater pump to OPEl'ABLE status as soon as possible.

SURVEILLANCE REQUIREMENTS 4.7.1.2 The emergency feedwater system shall be demonstrated OPERABLE:

a. At least once per 31 days by:
1. Verifying on a STAGGERED TEST BASIS that each motor-driven pump develops a discharge pressure of greater than or equal to 1298 psig on recirculation flow, and that the turbine-driven pump develops a discharge pressure of greater than or equal to 1342 psig on recirculation flow when the steam generator pressure is greater than 750 psig. The provisions of Specification 4.0.4 are not applicable for entry into M00E 3 for the turbine-driven pump.
2. Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

WATERFORD - UNIT 3 3/4 7-4 Amendment No. 80

9 PLANT SYSTEMS SURVEILLANCF REQUIREMENTS (Continued)

b. At least once per 18 months during shutdown by:
1. Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of an emergency feedwater actuation test signal.
2. Verifying that each pump starts' automatically upon receipt of an emergency feedwater actuation test signal.
c. Following any cold shutdown cf 30. days or longer or whenever feed-water line cleaning through the emergency feedwater line has been performed, by verifying, by means of a flow test, the normal flow path from the condensate storage pool through each emergency feedwater pump to each of the steam generators. The provisions of Specifica-tion 4.0.4 are not applicable for entry into MODE 3 for the turbine-driven pump.

1 4

1 WATERFORD - UNIT 3 3/4 7-5

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i CHANNEL- HODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE. .

INSTRUMENT CHECK CALIBRATION TEST IS REQUIRED -

1. AREA MONITORS
a. Fuel Storage Pool Area Fuel Handling Building ventilation System Isolation S R Q
  • l
b. Containment - Purge &

Exhaust Isolation S R Q 1. 2. 3. 4 & ** l

2. PROCESS MONITORS
a. Containment Atmosphere
1) Gaseous Activity -

! RCS Leakage Detection S R Q 1. 2. 3. & 4 l

2) Particulate Activity -

.RCS Leakage Detection S R Q 1. 2. 3. & 4 l

b. Control Room Intake Monitors S R Q ALL MODES l
c. Steam Generator Blowdown _ S R Q 1. 2'. 3. & 4 l
d. Component Cooling Water System S R' Q ALL MODES l
e. Component Cooling Water System S R Q ALL MODES l
  • With irradiated fuel in the storage pool.
    • During CORE ALTERATIONS or movement of irradiated fuel within the containment.

~

WATERFORD - UNIT 3' 3/4 3-32

- - - - - . .z

~..

TABLE 4.3-3 (Continued)

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS .,

f CHANNEL MODES FOR WHICH

! CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST IS REQUIRED 3.- EFFLUENT ACCIDENT MONITORS

a. Containment High Range S R M1 1. 2. 3. & 4 l
b. Plant Stack High Range 5 R Mg 1. 2. 3. & 4 l
c. Condenser Vacuum Pump

-High Range S R M1 1. 2. 3. & 4 l

d. Fuel Handling Building Exhaust High Range S R M1 1*. 2*. 3*. & 4* l~_
e. Main Steam Line High Range S R M1 1. 2. 3. & 4 l
  • With irradiated fuel in the storage pool.

WATERFORD UNIT 3- '3/4 3-33'

REACTOR COOLANT SYSTEM SURVEILLANCE RE0JIREMENTS (Continued)

d. Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />,
e. -Monitoring the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4.4.5.2.2 Each Reactor Coolant System pressure isolation valve specified in Table 3.4-1. Section A and Section B shall be demonstrated OPERABLE by verifying leakage to be within its limit:

a. At least once per 18 months,
b. Prior to entering H00E 2 whenever the plant has been in COLD SHUTDOWN for 72-hours 7 days or more and if leakage testing has not been l'
  • performed in the previous 9 months.
c. Prior to returning the valve to service following maintenance, repair. or replacement work on the valve,
d. Following valve actuation for valves in Section B due to automatic or manual action or flow through the valve:
1. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying valve closure, and
2. Within 31 days by verifying leakage rate.

The provisions of Specification 4.0.4 are not applicable for entry into H00E 3 or 4.

4.4.5.2.3 Each Reactor Coolant System pressure isolation valve power-operated valve specified in Table 3.4-1. Section C. shall be demonstrated OPERABLE by verifying leakage to be within its limit:

a. At least once per 18 months, and
b. Prior to returning the valve to service following maintcnance, repair, or replacement work on the valve.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

WATERFORD - UNIT 3 3/4 4-19

+

l REACTOR COOLANT SYSTEM  !

'I

- 3/4.4.3 PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.3.1 The pressurizer shall be OPERABLE with:

a. A steady state water volume greater than or equal to 26% indicated I level-(350 cubic feet) but less than or equal to 52.5% indicated I level (900 cubic feet), and. i
b. At least two groups of pressurizer heaters powered from Class IE i buses each having a nominal capacity of 150 kW. .l 4 APPLICABILITY: H0 DES 1. 2. and 3.

ACTION:

a. With only one group of the above required pressurizer heaters OPERABLE. restore at least two groups to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least 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 /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. With the pressurizer otherwise inoperable, be in at least HOT STANDBY with the reactor trip breakers open within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS a

4.4.3.1.1 The pressurizer water volume shall be determined to be within its 'l; limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

-l '

4.4.3.1.2 The capacity of each of the above required groups of pressurizer heaters shall be verified to be at least 150 kW at least once pcr 92 days each refueling interval.

4.4.3.1.3 The emergency power supply for the pressurizer heaters shall be j demonstrated OPERABLE at each refueling interval least-once per 18 onths by: l1

.a. Verifying the above pressurizer heaters are automatically shed.from <

the emergency power sources upon the injection of an SIAS test signal. -

b. Verifying that the above heaters can be manually placed and energized on the emergency power source from the control room.

WATERFORD - UNIT 3 3/4 4-9 Amendment No. 22

.. EMERGENCY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3,7.1.2 At least three independent steam generator emergency feedwater pumps and associated flow paths shall be OPERABLE with:

a. Two feedwater pumps. each capable of being powered from separate OPERABLE emergency busses, and 5
b. One feedwater pump capable of being powered from an OPERABLE steam supply system.-

APPLICABILITY: MODES 1, 2. and 3.

ACTION:

a. With one emergency feedwater pump inoperable. restore the required emergency feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least 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 /> and in HOT SHUTDOWN '

within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. '

b. With two emergency feedsater pumps inoperable be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following i 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c. With three emergency feedwater pumps inoperable. immediately initiate ,

corrective action to restore at least one emergency feedwater pump to OPERABLE status as soon as possible.

SURVEILLANCE REQUIREMENTS 4.7.1.2 The emergency feedwater system shall be demonstrated OPERABLE:

a. At least once per 31 days by: 4 2"1. Verifying that each valve (manual, power-operated,-or automatic) in the flow path that is not locked, sealed, or otherwise  ;

secured in position, .is in its correct position.

L At least once per 92 days on a STAGGERED TEST BASIS by; L Verifying ^^ ' '"*RE^ " o^SM that each motor-driven pump. l

-develops a discharge pressure of greater than or equal to 1298 psig on recirculation flowgd l; L Verifying that the turbine-driven pump develops a discharge pressure of' l greater than or equal to 1342 psig on recirculation flow when the steam ' ,

generator pressure is greater than 750 psig. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3; for the turbine-dr4ven-punt WATERFORD - UNIT 3 3/4 7-4 Amendment No. 80 1 1

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, PLNIT SYSTEMS

SURVEILLM1CE REOUIREMENTS (Continued) thg At least once per 18 months during-shutdown by: l
1. Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of an emergency feedwater actuation test signal.
2. Verifying that each pump starts automatically' upon receipt of-an emergency feedwater actuation test signal-.

c-d_ ~

Following any cold shutdown of 30 days or longer or whenever l feedwater line cleaning through the emergency feedwater line has -

been performed, by vert fying, by means of a flow test, the normal -!

flow path from the condensate storage pool through each emergency .

feedwater pump to each of the steam generators. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 for ,

the turbine-driven pump.

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l WATERFORD - UNIT 3 3/4 7-5 I

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