ML050460096

Technical Specification Pages Elimination of Requirements for Hydrogen Recombiners and Hydrogen Monitors

ML050460096
Person / Time
Site:	Summer
Issue date:	02/03/2005
From:	NRC/NRR/DLPM
To:
Cotton K, NRR/DLPM, 301-415-1438
References
TAC MC3307
Download: ML050460096 (4)

Text

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity...............................

314 6-1 Containment Leakage.......................

3/4 6-2 Containment Air Locks.....................

3/4 6-4 Internal Pressure.....................

314 6-6 Air Temperature.....................

3/4 6-7 Containment Structural Integrity.....................

3/4 6-8 Containment Ventilation System.....................

3/4 6-11 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Reactor Building Spray System.3/4 6-12 Spray Additive System.3/4 6-13 Reactor Building Cooling System.3/4 6-14 3/4.6.3 PARTICULATE IODINE CLEANUP SYSTEM.3/4 6-15 3/4.6.4 CONTAINMENT ISOLATION VALVES.3/4 6-17 3/4.6.5 Deleted SUMMER - UNIT 1 Vll Amendment No. 148 170

INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY MODES 1, 2, and 3.

ACTION:

a.

With the number of OPERABLE accident monitoring channels less than the Required Number of Channels shown on Table 3.3-10, either restore the Inoperable channel(s) to OPERABLE status within 30 days or submit a Special Report within the following 14 days from the time the action is required. The report shall outline the preplanned alternate method of monitoring, the cause of the Inoperability, and the plans and schedule for restoring the Instrumentation channels to operable status.

b.1 With the number of OPERABLE Reactor Building radiation monitoring channels less than the Minimum Channels Operable requirement of Table 3.3-10, 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:

I)

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

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.

b.2 Deleted b.3 With the number of OPERABLE accident monitoring channels less than the Minimum Channels Operable requirement of Table 3.3-10, either restore the Inoperable channels to OPERABLE status within 7 days 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 next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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 performing a monthly CHANNEL CHECK and a CHANNEL CALIBRATION every refueling outage. The Reactor Building Radiation Level Instrumentation CHANNEL CALIBRATION may consist of an electronic calibration of the channel, not including the detector, for the range decades above I0R/hr and a single point calibration of the detector below 1 OR/hr with an installed or portable gamma source.

SUMMER - UNIT 1 3/4 3-56 Amendment No. 448 170

TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION c

REQUIRED MINIMUM NO. OF CHANNELS M

INSTRUMENT CHANNELS OPERABLE

1.

Reactor Building Pressure -Narrow Range 2

1 C

Instrument Loop/indicator:

z Channel D IPT-951/lPI-951 Channel B IPT-952/IPI-952

2.

Reactor Building Pressure -Wide Range 2

Instrument Loop/Indicator.

Channel D IPT-954AIPI-954A Channel E IPT-954B11PI-954B

3.

Reactor Building Radiation Level - High Range 2

Instrument Loop/Indicator.

Channel A RMG-18 Channel B RMG-7

4.

Deleted 14

5.

Reactor Building/RHR Sump Level 2

1 Instrument Loop/indicator.

Channel A ILT-1969/lLI-1969 Channel B ILT-1970/lLI-1970

6.

Reactor Coolant Outlet Temperature - THO!- Wide Range 2

Instrument Loop/lindicator Channel A ITE-413/lTI-413 a

Channel A ITE-423AlTI-423 Channel E ITE-433/lTR-413

7.

Reactor Coolant Inlet Temperature - Tcorm-Wide Range 2

1

=1 Instrument Loop/indicator:

zO Channel E ITE-410/lTI-410 Channel E ITE-420/lTI-420 Channel E ITE-430ATR-410 0

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'SUMMER 1-UNIT 1 3J4 6-22 Amendment No. 170