ML052220439

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Tech Spec Pages for Amendment 160 Regarding Elimination of Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process
ML052220439
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 08/09/2005
From:
NRC/NRR/DLPM
To:
References
TAC MC4792
Download: ML052220439 (6)
v • d • e


Text

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE Drywell Average Air Temperature ........................ 3/4 6-10 Drywell and Suppression Chamber Purge System ........... 3/4 6-11 3/4.6.2 DEPRESSURIZATION SYSTEMS Suppression-Chamber .................................... 3/4 6-12 Suppression Pool Spray ................................. 3/4 6-15 Suppression Pool Cooling ............................... 3/4 6-16 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES ................... 3/4 6-17 Table 3.6.3-1 Primary Containment Isolation Valves... 3/4 6-19 3/4.6.4 VACUUM RELIEF Suppression Chamber - Drywell Vacuum Breakers .......... 3/4 6-43 Reactor Building - Suppression Chamber. Vacuum Breakers ............................................. 3/4 6-45 3/4.6.5 SECONDARY CONTAINMENT Secondary Containment Integrity ........................ 3/4 6-47 Secondary Containment Automatic Isolation Dampers ...... 3/4 6-49 Table 3.6.5.2-1 Secondary Containment Ventilation System Automatic Isolation Dampers Isolation Group No. 19 ............... 3/4 6-50 Filtration, Recirculation and Ventilation System ....... 3/4 6-51 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL Containment Hydrogen Recombiner Systems (Deleted) ...... 3/4 6-54 Drywell and Suppression Chamber Oxygen Concentration... 3/4 6-55 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Safety Auxiliaries Cooling System ...................... 3/4 7-1 Station Service Water System ........................... 3/4 7-3 Ultimate Heat Sink ..................................... 3/4 7-5 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM ............... 3/4 7-6 HOPE CREEK xii Amendment No; 160

TABLE 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION MINIMUM APPLICABLE REQUIRED NUMBER CHANNELS OPERATIONAL INSTRUMENT OF CHANNELS OPERABLE CONDITIONS ACTION

1. Reactor Vessel Pressure 2 1 1,2,3 80
2. Reactor Vessel Water level 2 1 1,2,3 80
3. Suppression Chamber Water level 2 1 1,2,3 80
4. Suppression Chamber Water Temperature* 2 1 1,2,3 80
5. Suppression Chamber Pressure 2 1 1,2,3 80
6. Drywell Pressure 2 1 1,2,3 80
7. Drywell Air Temperature 2 1 1,2,3 80
8. Deleted
9. Safety/Relief Valve Position Indicators 2/valve** 1/valve** 1,2,3 80
10. Drywell Atmosphere Post-Accident Radiation Monitor 2 1 1,2,3 80
11. North Plant Vent Radiation Monitor # 1 1 1,2,3 81
12. South Plant Vent Radiation Monitor # 1 1 1,2,3 81
13. FRVS Vent Radiation Monitor # 1 1 1,2,3 81
14. Primary Containment Isolation Valve Position Indication ## 2/valve 1/valve 1,2,3 82 Average bulk pool temperature.

Acoustic monitoring and tail pipe temperature.

High range noble gas monitors.

One channel consists of the open limit switch, and the other channel consists of the closed limit switch.

HOPE CREEK 3/4 3-85 Amendment No. 160

Table 3.3.7.5-1 (Continued)

ACCIDENT MONITORING INSTRUMENTATION ACTION STATEMENTS ACTION 80 -

a. With the number of OPERABLE channels less than the Required Number of Channels shown in Table 3.3.7.5-1, restore the inoperable channel to OPERABLE status within 30 days, or immediately initiate actions in accordance with 6.9.2.
b. With the number of OPERABLE channels less than the Minimum Number of Channels shown in Table 3.3.7.5-1, (except for the Drywell Atmosphere Post Accident Radiation Monitor) restore at least one inoperable channel 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 /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c. Deleted
d. With the number of OPERABLE Drywell Atmosphere Post Accident Radiation Monitor channels less than the Minimum Number of Channels requirement shown in Table 3.3.7.5-1, initiate action in accordance with ACTION 81, below.

ACTION 81 - With the number of OPERABLE accident monitoring instrumentation 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:

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

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, verify the valve(s) position by use of alternate indication methods. If the affected penetration is not isolated by either (i) a closed manual valve, (ii) a blind flange, or (iii) a deactivated automatic valve located outside primary containment, restore the inoperable channel(s) to OPERABLE status within 30 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 /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

HOPE CREEK 3/4 3-86 Amendment No. 160

TABLE 4.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS APPLICABLE CHANNEL CHANNEL OPERATIONAL INSTRUMENT CHECK CALIBRATION CONDITIONS

1. Reactor Vessel Pressure M R 1,2,3
2. Reactor Vessel Water Level M R 1,2,3
3. Suppression Chamber Water Level M R 1,2,3
4. Suppression Chamber Water Temperature M R 1,2,3
5. Suppression Chamber Pressure M R 1,2,3
6. Drywell Pressure M R 1,2,3
7. Drywell Air Temperature M R 1,2,3
8. Deleted
9. Safety/Relief Valve Position Indicators N R 1,2,3
10. Drywell Atmosphere Post-Accident Radiation Monitor N R** 1,2,3
11. North Plant Vent Radiation Monitor# N R 1,2,3
12. South Plant Vent Radiation Monitor# N R 1,2,3
13. FRVS Vent Radiation Monitor# N R 1,2,3
14. Primary Containment Isolation Valve Position Indication M R 1,2,3
    • CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10 R/hr and a one point calibration check of the detector below 10 R/hr with an installed or portable gamma source.
  1. High range noble gas monitors.

HOPE CREEK 3 /4 3-87 Amendment No. 160

CONTAINMENT SYSTEMS 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL CONTAINMENT HYDROGEN RECOMBINER SYSTEMS The material originally contained in Section 3/4.6.6.1 was deleted with the issuance of Amendment No.160 . However, to maintain numerical continuity between the succeeding sections and existing station procedural references to those Technical Specification sections, 3/4.6.6.1 has been intentionally left blank.

HOPE CREEK 3/4 6-54 Amendment No. 160

CONTAINMENT SYSTEMS BASES 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL The primary containment oxygen concentration is maintained less than -4% by volume to ensure that an event that produces any amount of hydrogen does not result in a combustible mixture inside primary containment.

The primary containment oxygen concentration must be less than 4% by volume when primary containment is inerted, except as allowed by the relaxations during startup and shutdown addressed below. The primary containment must be inert in OPERATIONAL CONDITION 1, since this is the condition with the highest probability of an event that could produce hydrogen.

Inerting the primary containment is an operational problem because it prevents containment access without an appropriate breathing apparatus. Therefore, the primary containment is inerted as late as possible in the plant startup and de-inerted as soon as possible in the plant shutdown. As long as reactor power is less than 15% of RATED THERMAL POWER, the potential for an event that generates significant hydrogen is low and the primary containment need not be inert. Furthermore, the probability of an event that generates hydrogen occurring within the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a startup, or within the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before a shutdown, is low enough that these "windows, when the primary containment is not inerted, are also justified. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time period is a reasonable amount of time to allow plant personnel to perform inerting or de-inerting.

If oxygen concentration is > 4% by volume at any time while operating in OPERATIONAL CONDITION 1, with the exception of the relaxations allowed during startup and shutdown, oxygen concentration must be restored to < 4% by volume within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> completion time is allowed when oxygen concentration is 2 4% by volume because of the low probability and long duration of an event that would generate significant amounts of hydrogen occurring during this period.

If oxygen concentration cannot be restored to within limits within the required completion time, the plant must be brought to an OPERATIONAL CONDITION in which the LCO does not apply. To achieve this status, plant must be in at least STARTUP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> completion time is reasonable, based on operating experience, to reduce reactor power from full power conditions in an orderly manner and without challenging plant systems.

The primary containment must be determined to be inert by verifying that oxygen concentration is less than 4% by volume. The 7 day Frequency is based on the slow rate at which oxygen concentration can change and on other indications of abnormal conditions (which would lead to more frequent checking by operators in accordance with plant procedures). Also, this Frequency has been shown to be acceptable through operating experience.

HOPE CREEK B 3/4 6-14 Amendment No. 160

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