ML18058A285

Revised TS Pages 3-81a & 3-82 to 880902 TS Change Request Re Core Exit Thermocouples

ML18058A285
Person / Time
Site:	Palisades
Issue date:	03/17/1992
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18058A284	List: ML18058A283 ML18058A285
References
NUDOCS 9203230247
Download: ML18058A285 (7)

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• ATTACHMENT I Consumers Power Company Palisades Plant
• Docket 50-255 REVISED PAGES 3-8la AND 3-82 TO THE SEPTEMBER 2, 1988 CORE EXIT THERMOCOUPLE TECHNICAL SPECIFICATIONS CHANGE REQUEST March 17, 1992 2 Pages
• Table 3.17.4 (Cont'd)
• Minimum Minimum Permissible O~erable Dearee of Bypass No Functional Unit c annels Re undanc~ Conditions

8. Pressurizer Wide 2 Cm, n, o) None Not required in Range Water Level Cold or Indication Refueling Shutdown

9. Pressurizer Code 1 ~er None* Not Required Safety Relief Valves Va ve below 325°F Position Indication fAcoustic Monitor or emperature Indication)

10. Power Operated Relief 1 ~er None Not required when Valves (Acoustic Va ve PORV isolation Monitor or Temperature valve is closed Indication) and its indication system is operable

11. PORV Isolation Valves 1 ~er None Not required when Position Indication Va ve reactor is depressurized and vented through a vent ~1.3 sq.in.

12. Subcooling Margin 1 None Not reguired Monitor below 325°F

13. Auxiliary Feed Flow 1 perih) None Not re~uired Rate Indication fl ow below 25°F Control Valve

14. Auxiliary Feedwater 2 per 1 Not reguired Actuation System steam below 325°F Sensor Channels generatorce>

15. Auxiliary Feedwater 2Cf) 1 Not required Actuation Shstem below 325°F Actuation C annels l(g)

16. Excore Detector None Not Re~uired Deviation Alarms Below 5% of Rated Power

17. Axial Shape Index 2Ci) 1 Not Re~uired Alarm Below 5% of Rated Power

18. Reactor Vessel 2Cj,k, l,m) None Not Reguired Water Level Below 325°F

19. Core Exit 4/core None Not re~uired Thermocouples R,~a~,rijlt below 00°F 3-81a Amendment No.~J, ~~' ~~' ))~, ))~, Ji~

• Table 3.17.4 (Cont'd}

                                                 *

3. Restore the system to OPERABLE status at the next scheduled refueling.

(m} The provisions of Specification 3.0.4 are not applicable. (n} With one OPERABLE Pressurizer Wide Range Water Level Channel in lieu of the requirement of 3.17.2, restore the inoperable channel to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours. (o} With no OPERABLE Pressurizer Wide Range Water Level Channels in lieu of the requirements of 3.17.2, either restore at least one of the inoperable channels to OPERABLE status within 48 hours, or be in at least HOT SHUTDOWN within the next 12 hours. (p} The environmentally qualified core exit thermocouples are used in determining the minimum channels operable requirement. (q} With only three OPERABLE Core Exit Thermocouples per core quadrant, in lieu of the requirement of 3.17.2, either restore the inoperable channel to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the Commission within 30 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. (r} With the number of OPERABLE Core Exit Thermocouples less than three per core quadrant, in lieu of the requirements of 3.17.2, either restore three core exit thermocouples per core quadrant to OPERABLE status within 48 hours, or be in HOT SHUTDOWN or below within the next 12 hours. 3.18 (Deleted} 3-82 Amendment No.z~, JJ~, Jl~

*

• ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 MARKED UP PAGES 3-8la AND 3-82 TO THE SEPTEMBER 2, 1988 CORE EXIT THERMOCOUPLE TECHNICAL SPECIFICATIONS CHANGE REQUEST March 17, 1992 2 Pages

No Functional Unit

• Table 3.17.4 (Cont'd)

                             . Mini mum Operable Minimum Degree of Redundanq

• Permissible Bypass Channels Conditions

8. Pressurizer Wide 2 (m.~ None Not required in Range Water Level

                                      ...,o Cold or Refueling                    l Indication                                              Shutdown                            t.

9. Pressurizer Code 1 per None Not Required Safety Relief Valves Valve below 325°F Position Indication (Acoustic Monitor or Temperature Indication)

10. Power Operated Relief 1 per None Not required when Valves (Acoustic Valve PORV isolation Monitor or Temperature valve is closed Indication) and its indication system is operable

11. PORV Isolation Valves 1 per None Not required when Position Indication Valve reactor is depressurized*and vented through a vent ;d.3 sq.in.

12. Subcooling Margin I None Not required Monitor below 325°F

13. Auxiliary Feed Flow I per None Not required Rate Indication fl ow<h> below 325°F Control Valve

14. Auxiliary' Feedwater 2 per 1 Not required Actuation System steam below 325°F Sensor Channels generator<*>

15. Auxiliary Feedwater 2(1) I Not required Actuation System below 325°F Actuation Channels

16. Excore Detector 1(g) None Not Required Deviation Alarms Below 25% of Rated Power

17. Axial Shape Index 2(1) 1 Not Required Alarm Below 25% of Rated Power 2(J ,k, 1,m) Not Required 18 ~ Reactor Vessel Water Level None Below 325°F h'11'r'/i1tp1~cl i

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(*,,~, ) .. 3-Bla Amendment No.,7, '~' ~ JJ,, JJ~. m

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• Table 3.17.4 (Cont'd)
• I

3. Restore the system to OPERABLE status at the next scheduled refueling.

(m) The provisions of Specification 3.0.4 are not applicable .

   .(A;   e)            !HanR:

With one OPERABLE Pressurizer Wide Range Water Level Channel in lieu of the requirement of 3.17.2, restore the inoperable channel to OPERABLE status within 7 days or be in at least HOT SHUTDO~"N within the next 12 hours. (o}~ With no OPERABLE Pressurizer Wide Range Water Level Channels in lieu of the requirements of 3.17.2, either restore at least one of the inoperable channels to OPERABLE status within 48 hours, or be in at least HOT SHUTDOWN within the next 12 hours.

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3.17

• INSTRUMENTATION AND CONTROL SYSTEMS (Contd)
• If the bypass is not effected, the out-of-service channel (Power Removed) assumes a tripped condition (except high rate-of-f,hange power, variable high power and high pressurizer pressure)l which results in a one-out-of-three channel logic. If, in the ~ of 4 logic system of either the reactor protective system or the engineered safeguards system, one channel is bypassed and a second channel manually placed in a tripped condition_, the resulting logic is 1 of 2.

At rated powert the minimum operable variable high power level channels is 3 in order to provide adequate flux tilt detection. If only 2 channels are operable the reactor power level is reduced to 70% rated power which protects the reactor from possibly exceeding design peaking factors due to undetected flux tilts. The engineered safeguards system provides a 2 out of 4 logic on the signal used to actuate the equipment connected to each of the 2 emergency diesel generator units. Two source-range channels are available any time reactivity changes are deliberately being introduced into the reactor and the neutron power is ~ot visible on the wide-range nuclear instrumentation or above 10- % of rated power. This ensures that redundant source-range instrumentation is available to operators to monitor effects of reactivity changes when neutron power levels are only visible on the source-range channels. In the event only one source-range channel is available and the neutron power level is sufficiently high that it is being monitored by both channels of wide-range instrumentation; a startup can be performed in accordance with footnote (d) of Taole 3.17.4. The Recirculation Actuation System (RAS) initiates on a 1 out of 2 taken twice logic scheme. Any one channel declared inoperable shall be placed in a bypass condition to ensure protection from an inadvertent RAS actuation. Since the bypassing of a channel intro-duces the possibility for a failure to receive an automatic RAS actuation signal, the time period in the bypassed condition is 1 imited. The Zero Power Mode Bypass can be used to bypass the low flow, steam generator low pressure, and TM/LP trips for all four Reactor Protective system channels to perform control rod testing or to Qerform low power physics testing below normal operating temperatures. The requirement to maintain cold shutdown boron concentration when in the bypass condition provides additional assurance that an accidental criticality will not occur. To allow low power physics testing at reduced temperature and pressure, the requirement for cold shutdown boron fnOncentration is not required and the allowed power is increased to 10- %. Sixteen (four per core quadrant) environmentally qualified core exit thermocou~les (cable and connectors) with readout from 0 to 2300°F are provided for monitoring the potential approach to inadequate core cooling. The core exit thermocouples are an integral part of the incore detector assembly and are l-0cated at the top of each incore-adsembly to measure primary coolant core outlet temperatures. References {1) Updated FSAR, Section 7.2.7. (2) Updated FSAR, Section 7.2.5.2 3-77 Amendment No. ~' JJ~, Ji~, Jp~}}