Text

Proposed Changes to Tech Specs Adding Addl Accident Monitoring Instrumentation & Instrumentation for Detection of Inadequate Core Cooling Per Requirements of NUREG-0737, Items II.F.1 & II.F.2
	ML20076F659
Person / Time
Site:	North Anna
Issue date:	06/03/1983
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML20076F648	List: ML20076F647; ML20076F659;
References
	RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-2.F.2, TASK-TM NUDOCS 8306140222
	Download: ML20076F659 (22)
	v • d • e

. .

CONTAINMENT SYSTEMS 3/4.6.4 COMBUSTIBLE GAS CONTROL .

HYDROCEN ANALYZERS LIMITING CONDITION FOR OPERATION 3.6.4.1 Two independent containment hydrogen analyzers (shared with Unit 2) shall be OPERABLE.

APPLICABILITY: MODES I and 2.

ACTION:

a. With one hydrogen analyzer inoperable, restore the inoperable analyzer to OPERABLE status within 30 days or be in at least HOT STANDBY within l 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 7 days or be in at least HOT STANDBY within the next six hours.

NOTE: OPERABILITY of the hydrogen analyzers includes OPERABILITY of the respective Heat Tracing System.

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 gas containing:

a. One volume percent (2 .25%) hydrogen, balance nitrogen, and

b. Four volume percent (1 .25%) hydrogen, balance nitrogen.

c. The Channel Ce'. Tration Test shall include startup and operation of the Heat Trn irg system.

NORTH ANNA - UNIT 1 3/4 6-33 ,

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TABLE 3.3-6 . .

RADIATION MONITORING INSTRUMENTATION h

d

~

MINIMUM N CilANNELS APPLICABLE ALARM / TRIP MEASUREMENT 5 INSTRUMENT OPERABLE MODES SETPOINT RANCE ACTION Q l. AREA MONITORS

1

a. Fuel Storage Pool Area

1. Criticality Monitor i 1

<l5 mR/hr 10 10+I R/hr 19

b. Containment

1. Purge & Exhaust -4 Isolation 1 6 < 50 mR/g3 10 0

- 10 R/hr 22

11. High Range Area 2 1,2,3,8 4 <l.6x10 R/hr 10 - 10 R/hr 35l

2. PROCESS MONITORS M

a. Ventilation Vent # - 6 y i. Gaseous Gross Activity 1 ** < 1 x 10 uCi/ml 10 - 10 cpm 21 w ii. Particulate Cross

< 2 x 10 -9 uCi/ml 6

- 10 - 10 cpm 21 Activity 1

b. Containment

1. Gaseous Activity a) Purge & Exhaust 3 6 Isolation 1 6 < 3.6 x 10 cpm 10 - 10 cpm 22 b) RCS Leakage 6 Detection 1 1,2,3,8 4 N/A 10 - 10 cpm 20 ii. Particulate Activity a) Purge & Exhaust 6 Isolation 1 6 < 1 x 105 cpm 10 - 10 cpm 22 b) RCS Leakage 6 Detection 1 1,2,3,8 4 N/A 10 - 10 cpm 20

With fuel in the storage pool or building

- With irradiated fuel in the storage pool f Common to Unit I and Unit 2

t z TABLE 3.3-6 (continued) i O

@ RADIATION MONITORING INSTRUMENTATION l

h MINIMUM

> CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT

' INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION E

.y 2. PROCESS MONITORS (Cont.)

s

c. Noble Gas High Range Effluent Monitors 2

i. Ventilation Vent i 1 1,2,3, & 4 Hi 5x10 3 5x10 ~7-10+5uci/cc 35 Hi Hi 10 ii. Process Vent # 1 1,2,3, & 4 Hi 5x10 5x10- -10+5pci/cc 35

_ 5 Hi Hi 10 h 111. Main Steam ## 1/ Loop 1,2,3, & 4 Hi .26 mr/hr 10-2-10 +7 mr/hr 35 u,

111 Hi 5.14 mr/hr i$a

$ iv. Auxiliary Feedwater Pump Turbine Exhaust 1 1,2,3, & 4 Hi 0.2 mr/hr 10 10* mr/hr 35 Hi Hi 4.03 mr/hr

Common to Unit I and Unit 2.

1. Main steam release path includes safety valves, atmospheric steam dump valves and the decay heat release path.

TABLE 3.3-6 (Continued) l TABLE NOTATION ACTION 19 - 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 20 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 21 - 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.

ACTION 22 - With the number of channels OPERABLE less than required by by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 35 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:

1. Initiate the preplanned alternate method of monitoring the appropriate parameter (s), and

2. 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 for restoring the system to OPERABLE status.

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NORTH ANNA - UNIT 1 3/4 3-37 l

[

5 . .

A TABLE 4.3-3 x

E RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

' CHANNEL MODES IN WHICH E CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE 5 INSTRUMENT CHECK CALIBRATION TEST REQUIRED

1. AREA MONITORS

a. Fuel Storage Pool Area

i. Criticality Monitor # S R M *

b. Containment

i. Purge & Exhaust w Isolation S R M 6 3 11. High Range Area S R M 1,2,3, & 4 l

4 w

2. PROCESS MONITORS h

a. Ventilation Vent #

i. Gaseous Gross S R M **

Activity

11. Particulate Gross R M **

Activity S

b. Containment

i. Gaseous Activity a) Purge & Exhaust Isolation S R M 6 b) RCS Leakage Detection S R M 1,2,3, & 4

11. Particulate Activity a) Purge & Exhaust Isolation S R M 6 b) RCS Leakage -

Detection S R M 1,2,3, & 4

With fuel in the storage pool or building

- With irradiated fuel in the storage pool

Common to Unit I and Unit 2

~

z TABLE 4.3-3 (Continued)

O RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS gj CHANNEL MODES IN WHICH h

> CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE 8 INSTRUMENT CHECK CALIBRATION TEST REQUIRED E

4 g 2. PROCESS MONITORS (Cont.)

c) Noble Gas High Range Effluent Monitors M 1,2,3 & 4

1. Ventilation Vent i S R 1,2,3 & 4 ii. Process Vent # S R M R M 1,2,3 & 4 111. Main Steam ## S iv. Auxiliary Feedwater Pump Turbine Exhaust S R M 1.2.3 & 4 w

D i'

su

Common to Unit I and Unit 2.

1. Main steam release path includes the safety valves, atmospheric steam dump valves, and the decay heat release path.

INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE. l APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With the number of OPERABLE accident monitoring channels less than the total number of channels shown in Table 3.3-10, either restore the inoperable channel (s) to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With the number of OPERABLE accident monitoring instrumentation channels less than the MINIMUM CHANNELS OPERABLE requirements of Table 3.3-10, either restore the inoperable channel (s) 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 HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 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.

i NORTH ANNA - UNIT 1 3/4 3-49

5 TABLE 3.3-10 - -

?i ACCIDENT MONITORING INSTRUMENTATION 5

> TOTAL NO. MINIMUM 8 0F CIIANNELS CRANNELS OPERABLE g

E

1. Containment Pressure 2 1

2. Reactor Coolant Inlet Temperature-T (wide range) 2 1 hot

3. 2 Reactor Coolant Inlet Temperature-Teold (wide range) 1

4. Reactor Coolant Pressure-Wide Range 1 1 S. Pressurizer Water Level 1 1 hb 6. Steam Line Pressure 2/ steam generator 1/ steam generator

7. Steam Generator Water Level-Narrow Range 2/ steam generator 1/ steam generator

8. Refueling Water Storage Tank Water Level 1 1

9. Boric Acid Tank Solution Level 1 1

10. Auxiliary Feedwater Flow Rate 1/ steam generator 1/ steam generator

11. Reactor Coolant System Subcooling Margin Monitor 2 1

12. PORV Position Indicator 2/ valve 1/ valve

13. PORV Block Valve Position Indicator 1/ valve 1/ valve

14. Safety Valve Position Indicator 1/ valve 1/ valve

15. Reactor Vessel Coolant Level Monitor 2 1

16. Containment Water Level (narrow range) 2 1

17. Containment Water Level (wide range) 2 1 i

TABLE 4.3-7 , ,

y ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS o

CHANNEL CHANNEL h CHECK CALIBRATION INSTRUMENT

> Containment Pressure M R 1.

I

2. Reactor Coolant Inlet Temperature-T (wide range) M R hot s M R H 3. Reactor Coolant Inlet Temperature-Tcold (w e range)

M R

4. Reactor Coolant Pressure-Wide Range M R

5. Pressurizer Water Level M R

6. Steam Line Pressure M R h 7. Steam Generator Water Level-Narrow Range

8. Refueling Water Storage Tank Water Level M R

$e M R

9. Boric Acid Tank Solution Level Auxiliary Feedwater Flow Rate M R 10.

Reactor Coolant System Subcooling Margin Monitor M R 11.

12. PORV Position Indicator M R M R

13. PORV Block Valve Position Indicator Safety Valve Position Indicator M R 14.

15. Reactor Vessel Coolant Level Monitor M R

16. Containment Water Level (narrow range) M R

17. Containment Water Level (wide range) M R .

r l

l l l CONTAINMENT SYSTEMS l 3/4.6.4 COMBUSTIBLE GAS CONTROL .

HYDROGEN ANALYZERS LIMITING CONDITION FOR OPERATION 3.6.4.1 Two independent containment hydrogen analyzers (shared with Unit 1) 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 HOT STANDBY within l 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 7 days or be in at least HOT STANDBY within the next six hours.

NOTE: OPERABILITY of the hydrogen analyzers includes OPERABILITY of the respective Heat Tracing System.

, 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 gas containing:

a. One volume percent (1 .25%) hydrogen, balance nitrogen, and

b. Four volume percent (1 .25%) hydrogen, balance nitrogen.

c. The Channel Calibration Test shall include startup and operation of the Heat Tracing System.

NORTH ANNA - UNIT 2 3/4 6-32

TABLE 3.3-6 , ,

g RADIATION MONITORING INSTRUMENTATION 4

MINIMUM APPLICABLE ALARM / TRIP MEASUREMENT g CHANNELS SETPOINT RANGE ACTION

INSTRUMENT OPERABLE MODES h 1. AREA MONITORS U a. Fuel Storage Pool Area -4 w i. Criticality Monitor # 1

15 mR/hr 10 - 10 R/hr 22

b. Containment

i. Purge & Exhaust -4 Isolation 1 6 150mR/h3 R/hr 10 0

- 10 R/hr 25

11. High Range Area 2 1,2,3,8 4 1 1.6x10 10 - 10 R/hr 35 l

2. PROCESS MONITORS

a. Ventilation Vent # -5 6

i. Gaseous Gross Activity I ** 1 1 x 10 uCi/ml 10 - 10 cpm 24 e

[ 11. Particulate Gross ~ 0 Activity 1 1 2 x 10 ' uCi/ml 10 - 10 cpm 24

b. Contain:nent

i. Gaseous Activity a) Purge & Exhaust 3 6 Isolation 1 6 1 3.6 x 10 cpm 10 - 10 cpm 25 b) RCS Leakage 6 Detection 1 1,2,3,8 4 N/A 10 - 10 cpm 23 ii. Particulate Activity a) Purge & Exhaust 5 6 Isolation 1 6 1 1 x 10 cpm 10 - 10 cpm 25 b) RCS Leakage 6 Detection 1 1,2,3,8 4 N/A 10 - 10 cpm 23

With fuel in the storage pool or building

- With irradiated fuel in the storage pool

Common to Unit 1 and Unit 2

TABLE 3.3-6 (continued)

E RADIATION MONITORING INSTRUMENTATION N*

MINIMUM g CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT

,, SETPOINT RANGE ACTION OPERABLE MODES

, INSTRUMENT h 2. PROCESS MONITORS (Cont.)

s M c. Noble Gas High Range Effluent Monitors Hi 5x10 2

5x10 ~7-10+5pci/cc 35 1,2,3, & 4

i. Ventilation Vent # 1 Hi Hi 10 3

1,2,3, & 4 Hi 5x10 4 5x10-7-10+5pci/cc 35

11. Process Vent # 1 Hi Hi 10 5

-2 # "# #

35 111. Main Steam ## 1/ Loop 1,2,3, a 4 Hi .26 mr/hr 10 -10 hh Hi Hi 5.14 mr/hr Y

iv. Auxiliary f Feedwater Pump 1,2,3, & 4 Hi 0.2 mr/hr 10-2-10+ mr/hr 35 Turbine Exhaust 1 Hi Hi 4.03 mr/hr

Common to Unit I and Unit 2.

1. Main steam release path includes safety valves, atmospheric steam dump valves and the decay heat release path.

TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 19 - 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 20 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 21 - 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.

ACTION 22 - With the number of channels OPERABLE less than required by by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 35 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:

1. Initiate the preplanned alternate method of monitoring the appropriate parameter (s), and

2. 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 for restoring the system to OPERABLE status.

l l

l NORTH ANNA - UNIT 2 3/4 3-40 i

i TABLE 4.3-3 5

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH h

> CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE I INSTRUMENT CHECK CALIBRATION TEST REQUIRED E

1

1. AREA MONITORS

a. Fuel Storage Pool Area M *

1. Criticality Monitor # S R

b. Containment y

1. Purge & Exhaust S R M 6 p Isolation M 1,2,3, & 4 g

ii. High Range Area S R l

2. PROCESS MONITORS

a. Ventilation Vent #

i. Gaseous Gross R M **

Activity S ii. Particulate Gross R M **

Activity S

b. Containment

i. Gaseous Activity a) Purge & Exhaust Isolation S R H 6 b) RCS Leakage Detection S R M 1,2,3, a 4

11. Particulate Activity a) Purge & Exhaust Isolation S R M 6 b) RCS Leakage -

Detection S R M 1,2,3, & 4

With fuel in the storage pool or building

- With irradiated fuel in the storage pool

Conunon to Unit I and Unit 2

TABLE 4.3-3 (Continued) g w

@ RADIATION MONITORING INSTRUMENTATION FURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH

> CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE

' INSTRUMENT CHECK CALIBRATION TEST REQUIRED E

1 w 2. PROCESS MONITORS (Cont.)

c) Noble Gas High Range Effluent Monitors M 1,2,3 & 4

i. Ventilation Vent i S R M 1,2,3 & 4

11. Process Vent i S R R M 1,2,3 & 4 iii. Main Steam ## S iv. Auxiliary Feedwater R M 1,2,3 & 4 u, Pump Turbine Exhaust S 2

4' C

o

Common to Unit 1 and Unit 2.

1. Main steam release path includes the safety valves, atmospheric steam dump valves, and the decay heat release path.

TABLE 3.3-10 , .

g ACCIDENT' MONITORING INSTRUMENTATION 4

TOTAL NO. MINIMUM 0F CHANNELS g; OPERABLE CHANNELS g

i E

2 1 E 1. Containment Pressure n

2. Reactor Coolant Inlet Temperature-T hot

(" * ##"E" 2 1

3. Reactor Coolant Inlet Temperature-Tcold (wide range)

4. Reactor Coolant Pressure-Wide Range 1 1 1

5. Pressurizer Water Level 1

6. Steam Line Pressure 2/ steam generator 1/ steam generator E 7. Steam Generator Water Level-Narrow Range 2/ steam generator 1/ steam generator

8. Refueling Water Storage Tank Water Level 1 1 1

9. Boric Acid Tank Solution Level 1

10. Auxiliary Feedwater Flow Rate 1/ steam generator 1/ steam generator Reactor Coolant System Subcooling Margin Monitor 2 1 11.

12. PORV Position Indicator 2/ valve I/ valve

13. 'PORV Block Valve Position Indicator 1/ valve 1/ valve

14. Safety Valve Position Indicator 1/ valve 1/ valve 2 1

15. Reactor Vessel Coolant Level Monitor .

16. Containment Water Level (narrow range) 2 1

17. Containment Water Level (wide range) 2 1 I

TABLE 4.3-7 , .

g ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS S CHANNEL CHANNEL

@ CilECK CALIBRATION INSTRUMENT

> M R

1. Containment Pressure

2. Reactor Coolant Inlet Temperature-T (wide range) M R hot H

y 3. Reactor Coolant Inlet Temperature-Tcold (" * #8"E*} ~

Reactor Coolant Pressure-Wide Range M R 4.

M R

5. Pressurizer Water Level M R

6. Steam Line Pressure Steam Generator Water Level-Narrow Range M R

$ 7.

Refueling Water Storage Tank Water Level M R j, 8.

Boric Acid Tank Solution Level M R 9.

M R

10. Auxiliary Feedwater Flow Rate Reactor Coolant System Subcooling Margin Monitor M R 11.

M R

12. PORV Position Indicator M R

13. PORV Block Valve Position Indicator M R

14. Safety Valve Position Indicator M R

15. Reactor Vessel Coolant Level Monitor Containment Water Level (narrow range) M R 16.

Containment Water Level (wide range) M R .

17.

9 8 e

4 O

ATTACINENT 2 t

DISCUSSION OF PROPOSED TECHNICAL SPECIFICATION CHANGES NUREG-0737 requires the submittal of Technical Specifications for certain additional Accident Monitoring Instrumentation, Items: II.F.1.1 - Noble Gas Effluent Monitors, II.F.1.3 - Containment High Range Radiation. Monitors, II.F.1.4 - Containment Pressure Monitors, II.F.1.5 - Containment Water Level Monitors, and II.F.1.6 - Containment Hydrogen Monitors. All additional instrumentation systems of Item II.F.1 have been installed, tested and are operational except for the Containment High Range Radiation Monitors. These monitors still require a final in-situ calibration in order to be considered operational for North Anna Unit 1. Submittal of these Technical Specification changes (plus the calibration of the Containment High Range Radiation Monitors) complete the requirements of NUREG-0737 for additional Accident Monitoring Instrumentation for North Anna Units 1 and 2 and North Anna Unit 2 License Conditions 2.C(21)(1)(1) through 2.C(21)(1)(v).

A brief description of additional Accident Monitoring Instrumentation follows:

II.F.1.1 5

Noble gas effluent monitors with an upper range capacity of 10 uCi/cc (Xe-133) have been installed. The monitors have the capability to detect and measure concentrations of noble gas fission products in plant gaseous effluents during and following an accident. The monitors have a digital readout in the control room to provide the operator and emergency planning agencies with information on plant releases of noble gases during and following an accident.

II.F.1.3 Containment High-Range Radiation Monitors, with a maximum range of 10 R/hr have been installed. The monitors provide the capability to detect and measure the radiation level within the reactor containment during and following an accident. The two high-range monitors are placed in separate areas of the containment to provide independent measurements and will " view" a large fraction of containment volume.

II.F.1.4 Containment Pressure Monitors that provide a continuous indication in the control room of containment pressure have been installed. Measurement and indication capability ranges from three times the design pressure of the l

containment to 5 psia. Technical Specifications for the Containment Pressure i

Monitors already exist in the North Anna Units 1 and 2 Technical Specifications. The monitors use unqualified transmitters but they will be qualified in accordance with the schedule of IEB 79-01B. The Technical Specifications will not have to be changed when the qualified transmitters are upgraded. The current Technical Specifications satisfy the Technical Specification requirements for NUREG-0737 for the Containment Pressure Monitors.

l

II.F.1.5 Containment Water Level Monitors that provide continuous indication of containment water level have been installed and the monitors have a reado'ut in the control room. A narrow range monitor is installed to cover the range of water from the bottom to the top of the containment sump. The wide range monitor is installed to cover the range of water from the bottom of the containment to the equivalent to a 600,000 gallon capacity.

II.F.1.6 Containment Hydrogen Monitors that provide indication of hydrogen concentration in the containment atmosphere has been installed and indication is provided in the control room. Measurement capability is provided over the range of 0 to 10% hydrogen concentration under both positive and negative ambient pressure. The containment isolation valves associated with the Containment Hydrogen Monitors were approved by the NRC in North Anna 1 Amendment No. 42 dated October 20, 1982 and North Anna 2 Amendment No. 34 dated May 17, 1982.

The addition of additional Accident Monitoring Instrumentation (NUREG-0737, II.F.1) increases the overall plant margin of safety by providing monitoring of potential radioactive release paths and provides a means to monitor hydrogen buildup in containment, radiation levels in containment,- and containment pressure and water levels. In no case is the information provided by these monitoring systems used to initiate automatic actuation of any plant safety systems.

This proposed change does not involve a significant hazards consideration.

The probability of occurrence or consequences of an accident or malfunction of equipment important to safety and previously evaluated in the UFSAR is not increased, nor has the possibility of an accident or malfunction of a different type previously evaluated in the UFSAR been created do to the additional accident monitoring instrumentation. The margin of safety as defined in the Basis for any Technical Specification is not reduced because the operation or failure of these systems does not lessen any safety system's ability to perform its design function. These systems are used during and following an accident therefore providing information related to plant status and condition.

JHL/acm:m10/002 i

9 9

ATTAClefENT 3

1 DISCUSSION OF PROPOSED TECHNICAL SPECIFICATION CHANGE A Westinghouse designed, redundant microprocessor-based system to mo,nitor reactor vessel coolant level has been installed. The system utilizes differential pressure measuring transmitters which measure water level and relative void content of the circulating primary coolant system fluid and thus .'

provides direct readings of reactor vessel coolant level. This system has been designed to meet the requirements of NUREG-0737, Item II.F.2. It will not affect normal station operation or the operation of any safety related equipment nor does it create an "unreviewed safety question", as defined in 10CFR50.59.

The design basis for.the Reactor Vessel Coolant Level Monitoring System is Appendix B to NUREG-0737, " Design and Qualification Criteria for Accident Monitoring Instrumentation" as clarified in NUREG-0737 Item II.F.2 except that the equipment will not meet with Regulatory Guide 1.100 requirements of testing under seismic conditions with the equipment operating. The Reactor Vessel Coolant Level Monitoring System does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the UFSAR. Reactor coolant losses

, resulting from a line rupture would be restricted by penetration size to that flow which is within the makeup capability of existing ECC Systems.

The system does not provide a path which would allow reactor coolant to exit the containment boundary. The system is designed and constructed in accordance with the General Design Criteria 14, 15, 16, 30, and 55 of Appendix A to 10CFR50. The modification will not affect the operation nor does it

, revise protection or logic schemes of any equipment important to safety previously evaluated in the UFSAR. This proposed change does not pose a significant hazards consideration.

A possibility of an accident or malfunction of a different type than previously evaluated in the UFSAR is not created. This modification will neither replace any existing system nor couple with any safety system. The margin of safety as defined in the basis for any Technical Specification is not reduced. The penetration of the reactor vessel head and the related system piping is limited in size to be within the capacity of the existing ECC Systems and a failure of this additional system (Reactor Vessel Coolant Level Monitoring System) does not challenge the Safety Analysis which forms a basis for the Technical Specification. The modification will not affect safety systems for any postulated accidents. The modification will, however, provide additional information to the operator during accident conditions.

l JHL/acm: mil /035 i l

!

ML20076F659

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