ML051090239

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Tech Spec Pages for Amendment 173 and 135 Limiting Conditions for Operation and Surveillance Requirements
ML051090239
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 04/13/2005
From:
Office of Nuclear Reactor Regulation
To:
References
TAC MC2741, TAC MC2742
Download: ML051090239 (14)
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Text

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE CONTAINMENT SYSTEMS (Continued) 3/4.6.4 VACUUM RELIEF Suppression Chamber - Drywell Vacuum Breakers................... 3/4 6-44 3/4.6.5 SECONDARY CONTAINMENT Reactor Enclosure Secondary Containment Integrity.3,4 6-46 Refueling Area Secondary Containment Integrity.

3/4 6-47 Reactor Enclosure Secondary Containment Automatic Isolation Valves.

3.4 6-48 Refueling Area Secondary Containment Automatic Isolation Valves.....

3/4 6-50 Standby Gas Treatment System - Common System.

3/4 6-52 Reactor Enclosure Recirculation System..

3/4 6-55 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL Deleted............................

3/14 6-57 Drywell Hydrogen Mixing System.................................... 3/4 6-58 Drywell and Suppression Chamber Oxygen Concentration.3/4 6.59 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Residual Heat Removal Service Water System - Common System.

3/4 7-1 Emergency Service Water System - Common System.

3,4 7-3 Ultimate Heat Sink.3/4 7-5 LIMERICK - UNIT 1' xiii Amendment No. X2-,

40, 4-9, 173

TABLF 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT

1.

Reactor Vessel Pressure

2.

Reactor Vessel Water Level

3.

Suppression Chamber Water Level

4.

Suppression Chamber Water Temperature REQUIRED NUMBER OF CHANNELS 2

2 2

8, 6 locations MINIMUM CHANNELS OPERABLE 1

1 1

6, 1/location APPLICABLE OPERATIONAL CONDITIONS ACTION 1,2 80 1,2 80 1,2 80 1,2 80 5.

6.

7.

8.

9.

10.

11.

12.

13 Suppression Chamber Air Temperature Drywell Pressure Drywell Air Temperature Deleted Deleted Safety/Relief Valve Position Indicators Primary Containment Post-LOCA Radiation Monitors North Stack Wide Range Accident Monitor**

Neutron Flux 1

2 1

1 1

1 1,2 1,2 1,2 80 80 80 I:

1/valve 4

3*

2 l/valve 2

  • 3*

1 1,2 1,2,3 1,2,3 1,2 80 S1 81 80 LIMERICK -

UNIT 1 3/4 3-85 Amendment No. 9, 4-11, 173

Table 3.3.7.5-1 (Continued)

ACCIDENT MONITORING INSTRUMENTATION TABLE NOTATIONS

  • Three noble gas detectors with overlapping ranges (10- to 10', 10' to
102, 10-' to 105 ptCi/cc).
    • High range noble gas monitor.

ACTION STATEMENTS ACTION 80 -

a. With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3.7.5-1, 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b. With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels OPERABLE requirements of Table 3.3.7.5-1, 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 in at least 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 />.

ACTION 81 -

With the number of OPERABLE accident monitoring instrumentation channels less than required by the Minimum Channels OPERABLE requirement, initiate the preplanned alternate method of monitor-ing the appropriate parameters within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and

a. Either restore the inoperable channel(s) to OPERABLE status within 7 days of the event, or
b. Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 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.

ACTION 82 -

DELETED I

LIMERICK - UNIT I 3/4 3-86 Amendment No. 4-54,173

TABLE ACCIDENT MONITORING INSTRUMEN INSTRUMENT

1.

Reactor Vessel Pressure

2.

Reactor Vessel Water Level

3.

Suppression Chamber Water Level

4.

Suppression Chamber Water Temperature

5.

Suppression Chamber Air Temperature

6.

Primary Containment Pressure

7.

Drywell Air Temperature

8.

Deleted

9.

Deleted

10.

Safety/Relief Valve Position Indicators

11.

Primary Containment Post LOCA Radiation Monitors

12.

North Stack Wide Range Accident Monitor***

13.

Neutron Flux 4.3.7.5-l TATION SURVEILLANCE REQUIREMENTS CHANNEL CHECK C

M M

M M

M

.CHANNEL ALIBRATION R

R R

R R

R R

M H

H H

MH H

I I

R R

R

-I

    • CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10 R/h and a one point calibration check of the detector below 10 R/h with an installed or portable gamma source.
      • High range noble gas monitors.

LIMERICK - UNIT I 3/4 3-87 Amendment No. 14-6, 173

CONTAINMENT SYSTEMS 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL PRIMARY CONTAINMENT HYDROGEN RECOMBINER SYSTEMS LIMITING CONDITION FOR OPERATION 3.6.6.1 DELETED LIMERICK - UNIT 1 3/4 6 -57 Amendment No. 28, 74,173

INSTRUMENTATION BASES 3/4.3.7 MONITORING INSTRUMENTATION 3/4.3.7.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring instrumentation ensures that; (1' the radiation levels are continually measured in the areas served by the individual channels, and (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with 10 CFR Part 50, Appendix A, General Design Criteria 19, 41, 60, 61, 63, and 64.

The specified surveillance interval for the Main Control Room Normal Fresh Air Supply Radiation Monitor has been determined in accordance with GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," as approved by the NRC and documented in the SER (letter to R.D. Binz, IV, from C.E. Rossi dated July 21. 1992).

3/4.3.7.2 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE UFSAR.

3/4.3.7.3 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE ODCM.

3/4.3.7.4 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION AND CONTROLS The OPERABILITY of the remote shutdown system instrumentation and controls ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room.

This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR Part 50, Appendix A.

3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an accident. This-capability is consistent with the recommendations of Regulatory Guide 1.97, "Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an-Accident,"

December 1975 and NUREG-0737, "Clarification of TMI Action Plan Requirements,"

November 1980.

LIMERICK - UNIT 1 B 3/4 3-5 Amendment No. 48, 6X, 7.,.7, 4-a4, ER 02 00470, 173

CONTAINMENT SYSTEMS BASES 3/4.6.5 SECONDARY CONTAINMENT (Continued)

The field tests for bypass leakage across the SGTS charcoal adsorber and HEPA filter banks are performed at a flow rate of 5764 +/- 10% cfm.

The laboratory analysis performed on the SGTS carbon samples will be tested at a velocity of 66 fpm based on the system residence time.

The SGTS filter train pressure drop is a function of air flow rate and filter conditions. Surveillance testing is performed using either the SGTS or drywell purge fans to provide operating convenience.

Each reactor enclosure secondary containment zone and refueling area secondary containment zone is tested independently to verify the design leak tightness. A design leak tightness of 2500 cfm or less for each reactor enclosure and 764 cfm or less for the refueling area at a 0.25 inch of vacuum water gage will ensure that containment integrity is maintained at an acceptable level if all zones are connected to the SGTS at the same time.

The Reactor Enclosure Secondary Containment Automatic Isolation Valves and Refueling Area Secondary Containment Automatic Isolation Valves can be found in the UFSAR.

The post-LOCA offsite dose analysis assumes a reactor enclosure secondary containment post-draw down leakage rate of 2500 cfm and certain post-accident X/Q values. While the post-accident X/Q values represent a statistical inter.

pretation of historical meteorological data, the highest ground level wind speed which can be associated with these values is 7 mph (Pasquill-Gifford stability Class G for a ground level release). Therefore, the surveillance requirement assures that the reactor enclosure secondary containment is verified under meteorological conditions consistent with the assumptions utilized in the design basis analysis.

Reactor Enclosure Secondary Containment leakage tests that are successfully performed at wind speeds in excess of 7 mph would also satisfy the leak rate surveillance requirements, since it shows compliance with more conservative test conditions.

3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL The primary containment atmospheric mixing system is provided to ensure adequate mixing of the containment atmosphere to prevent localized accumulations of hydrogen and oxygen from exceeding the lower flammability limit during post-LOCA conditions.

All nuclear reactors must be designed to withstand events that generate hydrogen either due to the zirconium metal water reaction in the core or due to radiolysis. The primary method to control hydrogen is to inert the primary containment.

With the primary containment inert, that is, oxygen concentration

<4.0 volume percent (v/o), a combustible mixture cannot be present in the primary containment for any hydrogen concentration. The capability to inert the prim3ry containment and maintain oxygen <4.0 v/o works together with Drywell Hydrogen Mixing System to provide redundant and diverse methods to mitigate events that produce hydrogen.

LIMERICK - UNIT 1 B 3/4 6-6 Amendment No. 8, 4.U, 44-2, EGR 00 001-3-, 173

INDEX LIMITING ADITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE CONTAINMENT SYSTEMS (Continued) 3/4.6.4 VACUUM RELIEF Suppression Chamber - Drywell Vacuum Breakers.....

.............. 3/4 6-44 3/4.6.5 SECONDARY CONTAINMENT Reactor Enclosure Secondary Containment Integrity............... 3/4 6-46 Refueling Area Secondary Containment Integrity.....

.............. 3/4 6-47 Reactor Enclosure Secondary Containment Automatic Isolation Valves.

............................................... 3/4 6-48 Refueling Area Secondary Containment. Automatic Isolation Valves.

............................................... 3/4 6-50 Standby Gas Treatment System - Common System.................... 3/4 6-52 Reactor Enclosure Recirculation System.......................... 3/4 6-55 3/4.5.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL Deleted..........................................................

3/4 6-57 Drywell Hydrogen Mixing System.................................. 3/4 6-58 Drywell and Suppression Chamber Oxygen Concentration............ 3/4 6-59 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Residual Heat Removal Service Water System - Common System..........................................................

3/4 7-1 Emergency Service Water System - Common System.................. 3/4 7-3 Ultimate Heat Sink............

................................... 3/4 7-5 LIMERICK - UNIT 2 xiii Amendment No. &9, 135

TABMTEN

.3 SUMTI5-O ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT

1. Reactor Vessel Pressure
2. Reactor Vessel Water Level
3. Suppression Chamber Water Level
4. Suppression Chamber Water Temperature REQUIRED NUMBER OF CHANNELS 2

2 2

8, 6 locations MINIMUM CHANNELS OPERABLE 1

1 1

6, 1/location APPLICABLE OPERATIONAL CONDITIONS 1,2 1,2 1,2 1,2 ACTION 80 80 80 80 5.

6.

7.

8.

9.

10.

11.

12.

13.

Suppression Chamber Air Temperature Drywell Pressure Drywell Air Temperature Deleted Deleted Safety/Relief Valve Position Indicators Primary Containment Post-LOCA Radiation Monitors North Stack Wide Range Accident Monitor**

Neutron Flux 1

2 1

1 1,2 1,2 80 80 80 1

1

.,2

  • 1/valve 4

3*

2 1/valve 2

3*

1 1,2.

1,2,3 1,2,3 1,2 80 81 81 80 LIMERICK - UNIT 2 3/4 3-85 Amendment No. 445,135

Table 3.3.7.5-1 (Continued)

ACCIDENT MONITORING INSTRUMENTATION TABLE NOTATIONS

  • Three noble gas detectors with overlapping ranges (10-7 to 10', 104 to
102,
10. to 105 ltCi/cc).
    • High range noble gas monitor.

ACTION STATEMENTS ACTION 80 -

a.

With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3.7.5-1, 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels OPERABLE requirements of Table 3.3.7.5-1, 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 in at least 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 />.

ACTION 81 -

With the number of OPERABLE accident monitoring instrumentation channels less than required by the Minimum Channels OPERABLE requirement, initiate the preplanned alternate method of monitor-ing the appropriate parameters within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and

a.

Either restore the inoperable channel(s) to OPERABLE status within 7 days of the event, or

b.

Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 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.

ACTION 82 -

DELETED LIMERICK - UNIT 2 3/4 3 -86 Amendment No.

4-16,135

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CONTAINMENT SYSTEMS 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL PRIMARY CONTAINMENT HYDROGEN RECOMBINER SYSTEMS LIMITING CONDITION FOR OPERATION 3.6.6.1 DELETED LIMERICK - UNIT 2 3/4 6-57 Amendment No. 34,135

INSRUMENTATION BASES 3/4.3.7 MONITQRII.G INSTRUMENTATION 3/4.3.7.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring instrumentation ensures that; (1) the radiation levels are continually measured in the areas-served by the individual channels, and (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient information is available on selected plant parameters to monitor and assess these variable following an accident.

This capability is consistent with 10'CFR Part 50, Appendix A, General Design Criteria 19, 41, 60, 61, 63, and 64.

The specified surveillance interval for the Main Control Room Normal Fresh Air Supply Radiation Monitor has been determined in accordance with GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specification," as approved by the NRC and documented in the SER. (letter to R. D. Binz, IV, from C. E. Rossi'dated July 21, 1992).

3/4.3.7.2 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE UFSAR.

3/-X.3.7.3 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO-THE ODCM.

3/4.3.7.4 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION AND CONTROLS The OPERABILITY of the remote shutdown system instrumentation and controls ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR Part 50, Appendix A. The Unit 1 RHR transfer switches are included only due to their potential impact on the RHRSW system, which is common to both units.

3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an accident.

This capability is consistent with the recommendations of Regulatory Guide 1.97, "Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0737, "Clarification of TMI Action Plan Requirements," November 1980.

LIMERICK - UNIT 2 B 3/4 3-5 Amendment No. 14, 4-7-,

33, 36, 1-s, ECR 92 0047-0,135

CONTAINMENT SYSTEMS 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL The primary containment atmospheric mixing system is provided to ensure adequate mixing of the containment atmosphere to prevent localized accumulations of hydrogen and oxygen from exceeding the lower flammability limit during post-LOCA conditions.

All nuclear reactors must be designed to withstand events that generate hydrogen either due to the zirconium metal water reaction in the core or due to radiolysis. The primary method to control hydrogen is to inert the primary containment.

With the primary containment inert, that is,

'oxygen concentration <4.0 volume percent (v/o), a combustible mixture cannot be present.in the primary containment for any hydrogen concentration.

The capability to inert the primary containment and maintain oxygen <4.0 v/o works together with Drywell Hydrogen Mixing System to provide redundant and diverse methods to mitigate events that produce hydrogen.

I LIMERICK - UNIT 2 B 3/4 6-7 Amendment No.

EGR- 0 nn.02, 135

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