ML18064A663

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Proposed Tech Specs for One Time Surveillance Deferment
ML18064A663
Person / Time
Site: Palisades Entergy icon.png
Issue date: 03/30/1995
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18064A662 List:
References
NUDOCS 9503310313
Download: ML18064A663 (14)
v • d • e


Text

ATTACHMENT I Consumers Power Company Pa 1 i sades Pl ant Docket 50-255 PROPOSED ONE TIME SURVEILLANCE DEFERMENT TECHNICAL SPECIFICATIONS REVISED PROPOSED PAGES 9503310313 950330 PDR ACOCK 05000255 P PDR 13 pages e 4:1 OVERPRESSURE PROTECTION SYSTEM TESTS Basis Surveillance Requirements In addition to the requirements of Specification 4.0.5, each PORV flow path shall be demonstrated OPERABLE by: 1. Testing the PORVs in accordance with the inservice inspection requirements for ASME Boiler and Pressure Vessel Code,Section XI, Section IWV, Category B valves. 2. Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 18 months*. 3. When the PORV flow path is required to be OPERABLE by Specification 3.1.8.1: (a) Performing a complete cycle of the PORV with the plant above COLD SHUTDOWN at least once per 18 months. (b) Performing a complete cycle of the block valve prior to heatup from COLD SHUTDOWN, if not cycled within 92 days. 4. When the PORV flow path is required to be OPERABLE by Specification 3.1.8.2: (a) Performance of a CHANNEL FUNCTIONAL TEST on the PORV actuation channel, but excluding valve operation, at least once per 31 days. (b) Verifying the associated block valve is open at least once per

  • 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. 5. Both High Pressure Safety Injection pumps shall be verified inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, unless the reactor head is removed, when either PCS cold leg temperature is < 260°F, or when both shutdown cooling suction valves, M0-3015 and M0-3016, are open. With the reactor vessel head installed when the PCS cold leg temperature is less than 260°F, or if the shutdown cooling system isolation valves M0-3015 and M0-3016 are open, the start of one HPSI pump could cause the Appendix G or the shutdown cooling system pressure limits to be exceeded; therefore, both pumps are rendered inoperable.
  • For Cycle 11 only, this surveillance need not be performed until prior to startup for Cycle 12. Amendment No. 3{}, -149, 4-6 4;16 INSERVICE INSPECTION PROGRAM FOR SHOCK SUPPRESSORS (Snubbers) 4.16.1 Applicability Applies to periodic surveillance of safety-related snubbers as described per Specification 3.20. Specifications Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program in addition to the requirements of Specification 4.0.5. As used in this specification, "type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity.
a. Visual Inspection Snubbers are categorized as inaccessible or accessible during reactor operation.

Each of these categories (inaccessible and accessible) may be inspected independently according to the following paragraph:

If one or more unacceptable snubbers are found, the next inspection interval shall be 2/3 (-25%) of the previous interval.

If no unacceptable snubbers are found, the next interval may be doubled (-25%), but not to exceed 48 months. The interval extension provisions of Technical Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months. Inspections performed before the interval has elapsed may be used as a new reference point to determine the next inspection.

However, the results of such early inspections, performed before the original required time interval has elapsed (nominal time less 25%), may not be used to lengthen the required inspection interval.

Any inspection whose results require a shorter inspection interval will override the previous schedule.

b. Visual Inspection Acceptance Criteria Visual inspection shall verify that (1) the snubber has no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the component and to the snubber anchorage are functional.

Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers, irrespective of type, that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Technical Specification 4.16.ld or 4.16.le, as applicable.

All snubbers found connected to an inoperable common hydraulic fluid reservoir shall be counted as unacceptable for determining the next inspection interval.

4-71 Amendment No. 3-, e.g, -l-G-7, -l-48,

  • 4:16 INSERVICE INSPECTION PROGRAM FOR SHOCK SUPPRESSORS (Snubbers) 4.16.l 2
  • b. Visual Inspection Acceptance Criteria (continued)

A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber. If continued operation cannot be justified, the snubber shall be declared inoperable and the action requirements shall be met. c. Functional Tests* At least once per 18 months during shutdown, a representative sample (10% of the total safety-related snubbers in use at the plant) shall be functionally tested either in place or in a bench test. The test shall verify the snubber has freedom of movement and is not frozen up. For each snubber which did not meet the functional test acceptance criteria of Specification 4.16.1.d or 4.16.1.e, an additional 10% of the total shall be functionally tested. 111 The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers.

Snubbers identified as especially difficult to remove or in high radiation zones during shutdown shall also be included in the representative In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period. If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested.

Test results of these snubbers may not be included for the resampling.

If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and, if caused by manufacturer or design deficiency, all snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.

Snubbers of rated capacity greater than 50,000 pounds are not to be included when defining the total number of safety-related snubbers in use at the plant. Permanent or other exemptions from functional testing for individual snubbers may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date. For Cycle 11 only, this surveillance need not be performed until prior to startup for Cycle 12. 4-72 Amendment No. !48, 4;16 INSERVICE INSPECTION PROGRAM FOR SHOCK SUPPRESSORS (Snubbers) 4.16.l c. Functional Tests* (continued)

Snubbers of rated capacity greater than 50,000 pounds will be functionally tested in lots comprising 25% of their total during each refueling outage. In the event of one snubber failure out of the four tested, no additional snubbers will be tested provided the problem is non-generic.

For each additional snubber failure, however, two additional snubbers will be tested until no further snubber failures are identified or all snubbers have been tested. Generic failures will be handled as the specific circumstances require. For the snubber(s) found inoperable, an engineering evaluation shall be performed on the components which are suppressed by the snubber(s).

The purpose of this engineering evaluation shall be to determine if the components suppressed by the snubber(s) were adversely affected by the inoperability of the snubber(s) in order to ensure that the suppressed component remains capable of meeting the designed service. d. Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that: 1. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

2. Snubber bleed, or release rate, where required, is within the specified range in compression or tension. For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
e. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that: 1. The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force (break away friction).
2. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
3. Snubber release rate, where required, is within the specified range in compression or tension. For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
  • For Cycle 11 only, this surveillance need not be performed until prior to startup for Cycle 12. 4-73 Amendment No. 3-, 6-9, .f.G.7.,

4".16 4.16.1 INSERVICE PROGRAM FOR SHOCK

f. Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.1.

Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each safety related snubber in use in the plant shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled service life review. If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This re-evaluation, replacement or reconditioning shall be indicated in the records. 4-74 Amendment No. 69, 93, +/-G-7,

INSERVICE INSPECTION PROGRAM FOR SHOCK SUPPRESSORS (Snubbers) 4.16 Basis The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.

Inspections performed before that interval has elapsed may be-used as a new reference point to determine the next inspection.

However, the results of such early inspections, performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval.

Any inspection whose results require a shorter inspection interval will override the previous schedule.

When the cause of the rejection of a snubber is clearly established and remedied for the snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable.

Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions such as temperature, radiation and vibration.

When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system. To provide assurance of snubber functional reliability, a representative sample of the installed snubbers, excluding snubbers of rated capacity greater than 50,000 pounds, will be functionally tested at 18 month intervals.

A representative sample of snubbers of rated capacity greater than 50,000 pounds will be functionally tested each refueling outage. Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.

The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high-temperatute area, etc ... ). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.

These records will provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.

4-74a Amendment No. 3-, -!G7-,

e

  • INSTRUMENTATION SYSTEMS TESTS Table 4.17.1 Instrumentation Surveillance Requirements for Reactor Protective System Functional Unit CHANNEL CHECK 1. Manual Trip NA 2. Variable High Power 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3. High Start Up Rate 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 4. Thermal Margin/ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Low Pressure 5. High Pressurizer 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Pressure 6. Low PCS Flow 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 7. Loss of Load NA 8. Low "A" s; Level 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 9. Low "B" SG Level 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 10. Low "A" SG Pressure 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 11. Low "B" SG Pressure 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 12. High Containment Pressure NA 13. RPS Matrix Logic NA 14. RPS Initiation Logic NA CHANNEL FUNCTIONAL TEST (a) 31 days (a) 31 days 31 days 31 days (a) 31 days 31 days 31 days 31 days 31 days 31 days 31. days 15. Thermal Margin Monitor; Verify constants each 92 days. (a) Once within 7 days prior to each reactor startup. CHANNEL CALIBRATION NA (b, c, & d) 18 months 1 e 1 18 months* 18 months* 18 months* 18 months 18 months* 18 months* 18 months* 18 months* . 18 months NA NA (b) Calibrate with Heat Balance each 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, when > 15% RATED POWER. (c) Calibrate Excores channels with test signal each 31 days. (d) CHANNEL CALIBRATION each 18 months. (e) I
  • Include verification of automatic Zero Power Mode Bypass removal. For Cycle 11 only, this surveillance need not be performed until prior to startup for*Cycle
12. Amendment No. -l-l-8, -l-6-G, -l-6e, .J..5.G, -l-&2-, 4-76

e 4*.17 INSTRUMENTATION SYSTEMS TESTS Table 4.17.2 Instrumentation Surveillance Requirements for Engineered Safety Features Functional Unit CHANNEL CHECK I. Safety Injection Signal (SIS) a. Manual Initiation NA b. SIS Logic NA (Initiation, Actuation, and low pressure block auto reset) c. CHP Signal SIS initiation (SP Relay Output) d. Pressurizer Pressure Instrument Channels NA 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 2. Recirculation Actuation Signal (RAS) a. Manual Initiation

b. RAS Logic c. SIRWT Level Switches NA NA NA CHANNEL FUNCTIONAL TEST 18 months (a) 18 months 31 days 18 months 18 months* 18 months* 3. Auxiliary Feedwater Actuation Signal (AFAS) a. Manual Initiation
b. AFAS Logic c. "A" SG Level d. "B" SG Level 4. Emergency Power Sequencers
a. DBA Sequencer
b. Normal Shutdown Sequencer NA NA 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 12 hours NA NA 18 months 92 days 31 days 31 days 92 days 18 Months CHANNEL CALIBRATION NA NA NA 18 months* NA NA 18 months* NA NA 18 months* 18 months* 18 months 18 months (a) Test normal and emergency power functions using test circuits each 92 days. Verify all automatic actuations and automatic resetting of low pressure block each 18 months.
  • For Cycle 11 only, this surveillance need not be performed until prior to startup for Cycle 12. Amendment No. -l-6-2-, 4-77 e
  • 4'.17
  • INSTRUMENTATION SYSTEMS TESTS Table 4.17.3 Instrumentation Surveillance Requirements for Isolation Functions Functional Unit 1. Containment High Pressure a. CHP logic Trains b. Containment Pressure Switches -Left Train c. Containment Pressure Switches -Right Train 2. Containment High Radiation
a. Manual Initiation
b. CHR Logic Trains c. Containment Area Radiation Monitors CHANNEL CHECK {CHP} NA NA NA {CHR} NA NA 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3. Steam Generator Low Pressure {SGLP} a. Manual Actuation NA b. SGLP Logic Trains NA c. "A" Steam Generator 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Pressure d. "B" Steam Generator 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Pressure 4. Engineered Safeguards Pu mg Room High a. East Room Monitor 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> b. West Room Monitor 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> CHANNEL FUNCTIONAL TEST 18 months 31 days 31 days 18 months 18 months 31 days 18 months 18 months 31 days 31 days Radiation 31 days 31 days CHANNEL CALIBRATION NA 18 months 18 months NA NA 18 months* NA NA 18 months* 18 months* 18 months 18 months I
  • For Cycle 11 only, this surveillance need not be performed until prior to startup for Cycle 12. Amendment No. &2-, 4-78 e

INSTRUMENTATION SYSTEMS TESTS Table 4.17.4 Instrumentation Surveillance Requirements for Accident Monitoring Instrument

1. Wide Range TH 2. Wide Range Tc 3. Wide Range Flux 4. Containment Floor Water Level 5. Subcooled Margin Monitor 6. Wide Range Pressurizer Level 7. Containment H 2 Concentration
8. Condensate Storage Tank Level 9. Wide Range Pressurizer Pressure 10. Wide Range.Containment Pressure 11. Wide Range "A" SG Level 12. Wide Range "B" SG Level 13. Narrow Range "A" SG Pressure 14. Narrow Range "B" SG Pressure 15. Position Indication for each Containment Isolation Valve 16. Core Exit Thermocouples (CET) Quadrant 1 17. Core Exit Thermocouples (CET) Quadrant 2 18. Core Exit Thermocouples (CET) Quadrant 3 19. Core Exit Thermocouples (CET) Quadrant 4 20. Reactor Vessel Water Level (RVWL) 21. High Range Containment Radiation CHANNEL CHECK 31 days 31 days 31 days 31 days 31 days 31 days 31 days 31 days 31 days 31 days 31 days 31 days 31 days 31 days 31 days 31 days 31 days 31 days 31 days 31 days 31 days CHANNEL CALIBRATION 18 months 18 months 18 months 18 months 18 months* 18 months 18 months 18 months 18 months* 18 months 18 months* 18 months* 18 months* 18 months* 18 months 18 months(al 18 months(al 18 months(al 18 months(al 18 months 18 months* (a) Calibrate by substituting a known voltage for thermocouple.
  • For Cycle 11 only, this surveillance need not be performed until prior to startup for Cycle 12. Amendment No. 4-79 4*.17 INSTRUMENTATION SY.MS TESTS Table 4.17.5 Instrumentation Surveillance Requirements for Alternate Shutdown System Instrument or Control CHANNEL CHECK 1. Start-up Range Flux (a) 2. Pressurizer Pressure 92 days 3. Pressurizer Level 92 days 4. #1 Hot Leg Temperature 92 days 5. #2 Hot Leg Temperature 92 days 6. #1 Cold Leg Temperature 92 days 7. #2 Coid Leg Temperature 92 days 8. 11 A 11 SG Pressure 92 days 9. 11 B 11 SG Pressure 92 days 10. 11 A 11 SG Level 92 days 11. 11 B 11 SG Level 92 days 12. SIRW Tank Level 92 days 13. P-8B Flow to 11 A 11 SG 18 months 14. P-8B Flow to 11 B 11 SG 18 months 15. P-8B Low Suction Alarm NA 16. P-8B Steam Valve Control NA 17. AFW Flow Control 11 A 11 SG NA 18. AFW Flow Control 11 B 11 SG 19. Transfer Switches, C-150 20. Transfer Switch, C-150A NA NA NA CHANNEL FUNCTIONAL TEST (a) NA NA NA NA NA NA NA NA NA NA NA 18 months 18 months 18 months 18 months 18 months 18 months 18 months 18 months CHANNEL CALIBRATION 18 months 18 months* 18 months 18 months 18 months 18 months 18 months 18 months* 18 months* 18 months* 18 months* 18 months 18 months 18 months 18 months NA NA NA NA NA (a) Once within 7 days prior to each reactor startup. I
  • For Cycle 11 only, this surveillance need not be performed until prior to startup for Cycle 12. Amendment No . .J-2-2., 4-80 e 4.17 INSTRUMENTATION SYSTEMS TESTS Table 4.17.6 Instrumentation Surveillance Reguirements for Other Functions CHANNEL CHANNEL FUNCTIONAL CHANNEL Instrument CHECK TEST CALIBRATION
1. Neutron Flux Monitoring 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (a) 18 months 2. Rod Position Indication 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (b) 18 months 3. SIRW Tank Temperature 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> NA 18 months 4. Main Feedwater Flow 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Not Required 18 months* 5. Main Feedwater Temp. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Not Required 18 months* 6. AFW Flow Indication 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 18 months 18 months 7. PCS Leakage Detection:
a. Sump Level 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 18 months 18 months b. Atmos. Gas Monitor 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 18 months 18 months c. Humidity Monitor 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 18 months 18 months* d. Air Cooler Condensate NA 18 months Not Required Flow Switch Ba. Primary Safety Valve acoustical monitor NA 18 months 18 months Bb/ Safety Va 1 ve / PORV 101 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 18 months 18 months 9a. tailpipe temperature 9b. PORV Acoustical Monitor NA 18 months 18 months 9c. PORV Stem Position 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 18 months 18 months 10. PORV Block Valve 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> NA 18 months Position Indication (a) Once within 7 days prior to each reactor startup. (b) Verification of Regulating Rod Withdrawal and Shutdown Rod Insertion interlocks OPERABILITY only, once within 92 days prior to each reactor startup AND once prior to startup after each refueling. (c) The tailpipe temperature indicator is common to the safety valves and PORVs
  • For Cycle 11 only, this surveillance need not be performed until prior to startup for Cycle 12. (continued)

Amendment No. -l-6-2-, 4-81

... , l .. e INSTRUMENTATION SYSTEMS TESTS 11. 12. 13. 14. 15. 16. 17. 18. 19. 20. I (d) I

  • Table 4.17.6 (continued)

Instrumentation Surveillance Reguirements for Other Safety Functions CHANNEL CHANNEL FUNCTIONAL CHANNEL Instrument CHECK TEST CALIBRATION SWS Break Detector NA 18 months 18 months Flux -AT Comparator 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 31 days 18 months Rod Group Sequence NA 18 months 18 months Control/Alarm BAT Low Level Alarm NA 18 months Not Required Excore Deviation Alarm NA 18 months 18 months ASI Alarm NA 18 months 18 months SOC Suction Interlocks NA 18 months* 18 months* PDIL Alarm NA 31 days 1 d 1 *18 months Fuel Pool Rad Monitor 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 31 days 18 months Containment Refueling Radiation Monitor 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 31 days 18 months Setpoint verification only. For Cycle 11 only, this surveillance need not be performed until prior to startup for Cycle 12. Amendment No. -l-62-, 4-82

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