ML18057A765

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Proposed Tech Specs Re Instrumentation & Control Sys & Instrumentation Operating Requirements for Reactor Protection Sys
ML18057A765
Person / Time
Site: Palisades Entergy icon.png
Issue date: 02/27/1991
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18057A764 List:
References
NUDOCS 9103070002
Download: ML18057A765 (18)
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{{#Wiki_filter:.( l ATTACHMENT I Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST INSTRUMENT & CONTROL SYSTEMS PROPOSED TECHNICAL SPECIFICATIONS PAGES February 27, 1991 8 Pages 9103070002 910227' P PDR ADOCK 05000255 ;

  • PDR '. * . ' --..,......_, i. .. '

3.17 INSTRUMENTATION AND CONTROL SYSTEMS -*-Applicability The instrumentation and control systems shall be operable under the following conditions: Table 3 .17 .1 Table 3.17.2 Table 3.17.3 Table 3.17.4 Objective When the PCS has less than Refueling Boron Concentration and more than one control rod is capable of being withdrawn, except as allowed by the permissible bypass conditions. When the PCS temperature is 325°F, except as allowed by the. permissible bypass conditions. When the PCS is above Cold Shutdown, except as allowed by the permissible bypass conditions. At all times, except as allowed by the permissable bypass conditions. To delineate the conditions of the plant instrumentation and control systems necessary to assure reactor safety. Specifications 3.H.l In the event the number of channels of a particular system* in service falls below the limits given in the columns entitled "Minimum Operable Channels" or "Minimum Degree of Redundancy," except as conditioned by the column entitled "Permissible Bypass Conditions," the reactor shall be placed in a hot shutdown condition within 12 hours. If minimum conditions are not met within 24 hours, the reactor shall be placed in a cold shutdown condition within 24 hours. Basis During plant operations, the complete instrumentation systems will normally be in service. Reactor safety is provided by the reactor protection system, which automatically initiates appropriate action to prevent established limits. Safety is not compromised, however, by cont i nurng operation with cer.ta in instrumentation channels out of service since provisions were made for this in the plant design. This specification outlines limiting conditions for * --operation necessary to preserve the effectiveness of the reactor----control and protection system when any one or more of the channels are out of service. TSPR9102 The Reactor Protective system is not required to be operable if there is no fuel in reactor vessel or PCS boron concentration is at Refueling Boron Concentration or if only one control rod is capable of being withdrawn. 3-76 Amendment No. 3.17 INSTRUMENTATION AND CONTROL SYSTEMS (Cont'd) TSPR9102 Refueling boron concentration requires a 5% shutdown margin with all the control rods removed from the core. Therefore, there is no need for automatic control rod insertion. When all CROM clutches are de-energized, no control rods can be withdrawn, and the RPS function has been accomplished. The safety analyses and the Shutdown definition use the assumption that one control rod will fail to insert on a trip. Therefore if only one control rod is capable of withdrawal, the safety analyses and shutdown margin definition will be met. When the reactor powei level indication reaches a nominal 15% of rated power, a bistable in the power range nuclear instrument circuitry deactivates the Wide Range Channel Rate of Power Change reactor trip and activates the Loss of Load reactor trip. When indicated power decreases below a nominal 15% of rated power, the Loss of Load trip is deactivated and the Rate of Power Change is reinstated. These switching actions occur automatically. The bistable which actuates the switching of these two trips is adjusted so that it actuates at an indicated power of 15+/-2%. This allows for to 1 erances in setting and for to 1 eran*ces in setting and for hysteresis in the bistable action. Neither the Rate of Power Change trip nor the Loss of Load trip are relied upon in the safety analyses. . Almost all reactor protection and engineered safeguards channels are supplied with sufficient redundancy to provide the capability for channel test at power. Exceptions are backup channels such as loss-of-load trip. *

  • When one of the four channels is taken out of service for . maintenance, the protective system can be changed to a of-three coincidence for a reactor trip by bypassing the removed channel. If the bypass is not effected, the out-of-service channel (Power Removed) assumes a tripped condition (except high rate-of-change.*

power, variable high power and high pressurizer pressure),<l) which results in a one-out-of-three channel logic. If, in the 2 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 conditioni the resulting logic is *1 of 2; At rated power, the minimum operab e 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. 3-76a Amendment No. 3.17 INSTRUMENTATION AND CONTROL SYSTEMS (Contd) TSPR9102 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 start-up channels are available any time reactivity changes are deliberately being introduced into the reactor and the neutron power is not visible on the wide-range nuclear instrumentation or above io-"% 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 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 Table 3.17.4. The Recirculation Actuation System (RAS) initiates on a 1 out of 2 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 duces the possibility for a failure to receive an automatic RAS actuation signal, the time period in the bypassed condition is limited. 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 perform low power physics testing below normal operating temperatures. The requirement to maintain cold shutdown boron concentration when in the bypass* condition provides additional that accidental criticality will not occur. To allow low power physics testing at reduced temperature and pressure, the requirement for cold shutdown boron concentration is not required and the allowed power is increased to io-1%. References (2 1) Updated FSAR, Section 7.2.7. ( ) FSAR, Section 7.2.5.2 3-77 Amendment No. Table 3.I7.I Instrumentation Operating Requirements for Reactor Protective System No. Functional Unit Minimum Operable Channels Minimum Degree of Redundancy Permissible Bypass Conditions

1. 2. 3. 4. 5. 6. 7. 8. Manual (Trip Buttons) Variable High Power Level Wide Range Channels *. Thermal Low Pres sun zer Pressure High Pressurizer Pressure Low Flow Loop Loss of Load Low Steam Generator Water Level I 2 I 2/Steam Gen -None I I I I None I/Steam Generator None.* None. Bel ow 10-43<*> or Above I3% of Rated Power<a> except as noted in {c). Below 10-43<*> of Rated Power<a> and greater than cold shutdown boron
  • None. Below 10-43<*> of Rated Power<a> greater than cold shutdown boron concentration.

Bel ow I 7% of Rated Power<a>. None. 9. Low Steam Generator Pressure 2/Steam Gen I/Steam Generator Bel ow 10-43<*> of Rated Power<a> and greater than cold shutdown boron concentration.

10. High Containment Pressure 2(b) I None. m (d) .( e) ( f) I Bypass automatically removed.
  • One of the inoperable channels must be in the tripped condition.

if TM/LP, Low-Steam Generator Pressure,. or Low Flow Loop channels are bypassed.

  • If only two channels are operable, load shall be reduced to 70% rated power. For Low Power Physics Testing, Io-43 may be increased to I0-1% and cold shutdown boron concentration is not required.

Axial Offset operability requirements are given in Specification 3.II.2. 3-78 Amendment No. TSPR9I02 I I No 1 a. b. c. 2. a. b. . Table 3.17.2 Instrumentation Ogerating Reguirements for Engineered Safety Feature Systems Minimum Minimum Permissible Functional Unit C annels Dearee of Re undancy Bypass Conditions Safety Injection Manual {Trip Buttons) 1 None None High Containment 2(a,c) 1 None Pressure Pressurizer Low 2<c) .1 Pressure .Pressure Less T an 1700 Psia<bl Containment Sgray Manual 2 None None High Containment Pressure 2(a,c) 1 None Right and left actuation circuits each have 2 channels. Auto removal of bypass above 1700 psia. One of the inoperable channels must be in the tripped condition. 3-79 TSPR9102 Amendment No. No 1 a. b. c. 2 a. b. *. Table 3.17.3 Instrument Operatfoq Condjtions for-Isolation Functions Minimum Minimum Permissible Functional Unit C annels Dearee of Re Bypass Conditions Containment Isolation Containment High 2(a,c) 1 None Pressure Containment Radiation High 2<c) 1 none Manua 1 1 none none* Steam Line Isolation Low Steam Gen 2/Steam<c> 1 Below 550 psia Pressure Gen Manual !/Steam none none Gen . --} Right and left actuation circuits each have 2 channels. Bypass automatically reinstated above 550 psia. One of the inoperable channels must be in the tripped position. 3-80 TSPR9102 Amendment No. No 1 2 Functional Unit SIRWT Low-Level Switches AT -Power Comparator Table 3.17.4 Instrumentation Operating Requirements for Other Safety Feature Functions Minimum Minimum Operable Degree of Channels Redundancy 4 1 Permissible Bypass Conditions Not reguired below 325°F. One channel may be inoperable for a period of 7 days CbJ Not required at or below Hot Shutdown 3 (Deleted) 4 5 6 7 (a).. (b) . (c) . (d) Air Cooler Service 1 Water Flow Instruments Primary and Secondary 1 Rod Insertion and Out-of-Sequence Monitors Fuel Pool Building 1 Crane Interlocks Start-Up Channels 2 None None None 1 (d) -. Not required at or below Hot Shutdown NA As Requeited Under Administrative Control s<aJ Not Required Above 10-43 of Rated Power or with no fuel in the reactor. Crane shall not be used to move material past the fuel storage pool unless the interlocks are available. If a channel is declared inoperable, it shall be placed in a bypass condition. Minimum degree of redundancy is not applicable to the SIRWT low-level switches. If only two channels are operable, load shall reduced to 70% or less of rated power . Minimum operable channels shall be one f 1) and minimum degree of redundancy is -zero* (0) if shutdown neutron power leve s indicated on the wide, channels* are greater than three times the lowest decade in which neutron visibility can be confirmed. Neutron visibility will be confirmed through observation of reactivity changes on neutron power level (including a l/M plot during reactor start-up) and comparing the observed changes to the changes noted on previous similar start-ups. Instrumentation operability will also be verified by comparisqn among the three operable channels to ensure their individual responses are in agreement.

  • 3-81 TSPR9102 Amendment No.

e Table 3.17.4 (Cont'd) Minimum Minimum Permissible Dearee of Bypass . No Functional Unit C annels Re Conditions 8." Pressurizer Wide 2 (m, p, q) None Not required in Water Level Cold or Refueling Indication Shutdown 9. Pressurizer Code 1 None Not Required Safety Relief Valves Va ve below 325°F Position Indication tAcoustic Monitor or emperature Indication)

10. Power Relief 1 per None Not in cold shutdown Valves osition Indication or when PORV isolation tAcoustic Monitor or valve is closed emperature Indication) and its indication system is operable 11. PORV Isolation Valves 1 None Not required when Position Indication Va ve reactor is depressurized and vented through a vent sq. in. 12. Subcooling Margin 1 None Not required Monitor below 325°F 13. Auxiliary Feed Fl ow 1 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(f) 1 Not required Actuation Shstem below 325°F Actuation C annels 16. Excore Detector 1 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 18. Reactor Vessel 2(j,k, 1,m) None Not Required Water Level Below 325°F 3-8la Amendment No.,7, TSPR9102 ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST INSTRUMENT

& CONTROL SYSTEMS MARKED UP EXISTING TECHNICAL SPECIFICATIONS PAGES February 27, 1991 7 Pages '3 * .:. 7 ..

*--l -3.;.,.;i .f*y "f"AJJeJl.f

\...,w ___ ----* ------------ !astrumentatioa !!)"!Items.

.17.1 3.i1.2 ObJective To delineate the conditions ot the plant instrumentation and control systems necessary to assure react.or sa.tety. Soecit1cat ions Defe.'.Q , The epeFabilhy et plant 1aatl'umeat aa.4 eoatr-.i.

ayat m aha 11 be ia aeee*1 0-ee *.rita 3,17.1 3,17,4. In the event the number ot chaa.aels or a particular system in service t&lls belov the limits given in the columns entitled "Mini.mum Operable Channels" or "Minimum Degree ot Redundancy," except as conditioned. by the column entitled. "Permissible Bnass Cc:cilticns." the reactor shall be placed iz1 a e;iot: shutd.ovu coad.itioo vi thin 12 hours. It mini!num conditions are not m.et vi tllin 24 hours, the reactor shall. be placed in & cold. shutdovu conditioo vithin 24 hours. Basis During plant operations, the complete iostru:nentatioo systems vill normally be in service. Reactor safety is provided by the reactor protectioo system, vhich automatica.J..l,y initiates appropriate action tc exceeding established limits. Sa!ety is not co:nproc:lised, hovever, by continuinc operation vith certain instrw!leotation out ot service s!nce vere i11ade tor this in the plant design. This speciticatioo li.mitiag conditions for o;:eration necessary to preserve the effectiveness ot the reactor control a.nd s:rste.m q,ey -:::.e -:r :ore :b.e are out ot service. ::rAJ$£iL.'(' A, __ St .. ,l t i d. i d f ..e. h l B cw. reactor pro ect on a.n ec.g oeere sa. c a.nne s CJ supplled sut!1c1ent redunc!&acy ;rovide the capability for channel test at pover. Exceptions a.re backup clla.nnels such a.s loss-ot-load trip. When oae ot the four channels is taken out ot service tor maintenance, the protective system logic can be changed. to a tvo-out-o.t'-three coincidence tor a reactor trip by bypassing the removed. cb.aru:lel. /(,'C:;:1r1J ,. I I ' .. ") 3-76 A The instrumentation and control systems shall be operable under the following

condtti-ons-:-

*-------------------------

Table 3.17.1 -When the PCS has less than Refueling Boron Concentration and more than one control rod is capable of being withdrawn, except as allowed by the permissible bypass conditions.

Table 3.17.2 -When the PCS temperature 325°F, except as allowed by the permissible bypass conditions. Table 3.17.3 -When the PCS is above Cold Shutdown, except as allowed by the permissible bypass conditions. Table 3.17.4 -At all times, except as allowed by the permissible bypass conditions. B The Reactor Protective System is not required to be operable if there is no fuel in the reactor vessel, or when the PCS boron concentration is at Refueling Boron Concentration or if only one control rod is capable of being withdrawn.*

  • Refueling boron concentration requires a 5% shutdown margin with all the control rods removed from the core. Therefore, there is no need for automatic control rod insertion.

When all CROM clutches are de-energized, no control rods can be withdrawn and the RPS function has been accomplished. The safety analyses and the Shutdown Margin definition use the assumption that one control rod will fail to insert on a trip. Therefore, if only one control rod is capable of withdrawal, the safety analyses and shutdown margin definition will be met. When the reactor power level indication reaches a nominal 15% of rated power, a bistable ih the power range nuclear instrument circuitry deactivates the Wide Range Channel Rate of Power Change reactor trip and activates the Loss of Load reactor trip. When indicated power decreases below a nominal 15% of rated poweY', the loss of Load trip is deactivated and the Rate of Power Change is reinstated. These switching actions occur automatically. The bistable which actuates the switching of these two trips is adjusted so that it actuates at an indicated power of 15+/-2%. This allows for tolerances in setting and for hysteresis in the bistable action. Neither the Rate of Power Change trip nor the Loss of Load trip are relied upon in the safety analyses. 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-change power, variable high power and high pressurizer pressure}, <1> which results in a one-out-of-three channel logic. If, in the 2 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 power, 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 not visible on the wide-range nuclear instrumentation or above 10-4% 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-tange 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 Table 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 limited. The Zero Power -Mode Bypass can be used to bypass the low. fl ow, steam. generator low pressure, and TM/LP trips for all four Reactor Protective system to perform control rod testing or to perform low power below normal operating temperatures. The requirement to shutdown boron concentration when in the bypass condition assurance that an accidental criticality will not .. aJlow low power physiCs testing. at reduced temperature and pressure; the requirement for cold shutdown boron concentration is not required and the allowed power is increased to 10-1%. References (1) Updated FSAR, Section 7.2.7. (2) Updated FSAR, Section 7.2.5.2 3-77 Amendment No. n,, 136 February 15, 1991 '* Table 3 .17 .1 Instrumentation Ooeratinq Requirements for Reactor Protective System . -M.i ni mum*_.:_ _ _ Mf.n:i.mum _ _ __ _____ _ _ _ _ __ __ _____ _ _ _ __ .. 1. 2. 3. 4. 5. 6. 7. 8. 9. Funct i On al .Un 1 1t . :-* ': Manua 1 {Trfp * ;: *-. 1* ' Variable Higl< Power Level )JIN..... Wide Channels Thermal Margin/ Low-Pressurizer Pressure '}l'J.. High-Pressurizer Low Fl ow Loop J<<l. Loss of Load '-'w. Low Steam Gen-<: erator Water -Level )cl.. Low Steam Gen-erator Pressure 10. High Containment Operable *chaririel s' * .'t*: -:-} . ' . 2 (b.d) 2 I 2/Steam Gen 2/Steam Gen (a) Bypass automatically removed. Degree of _ Bypass \Redundancy

  • '} <, Cbnd rtri ons , __ **j ('c:_., '* .. : :-1;** . 'l 1 I I None I/Steam Generator I/Steam Generator I *None . .

'Be-low 13 ¥5% ':Rafeli J *': .. ,__' :* '. .. : .. .

  • 10;*,*c*>
of Rated . :power<*>

and greater than =.*-cold *-shutdown boron -concentration None Bel ow 10-43<*> of -Rated Power<*> and greater than cold shutdown boron concentration. T1 :::> (11.) 111 0 lA..W r-ow<.r . None Bel ow Io-43<*> of as Rated Power<*> and greater than cold shutdown boron centration. None (b) One of the inoperable channels must be in the tripped condition. (c) Two channels required if TM/LP, low steam generator or low-flow channels are bypassed. (d) If only two channels are operable, load shall be reduced to 70% or less of rated power. (e) For low power physics testing, Io-43 may be increased to 10-1% and cold shutdown boron concentration is not required. (f) Axial Offset operability requirements are given in Specification 3.Il.2. (g) eperaele if aAy clutch power supply is (h) Automatically bypassed below 15% power. 3-78 Amendment No. j;'ebruary 15, 199 l ' -e -------TabTe Instrumentation Operatillg Requirements for Engineered S&tety Systems lo ll'um:tional Unit 1 Safety Injection 11.. Manual (Tr! p Minimum Operable Cbazmels l Jttn1nnun lone Permissible J.Vpase Cond.itiocs lone b. High Containment Pressure 2(a.,c) l ibr1ng Leak en Pressurizer I.ow Pressure l Prima1'7 Pres sure 2 Contaiment S'D?'BI a. b. Manual High Containment Pressure - 2 2(a.,c) lone l Lesa lTOO Paia(b !one. No"e. (a.) Right and lef't actuation circ:uits each bave 2 c'bannels. (b) . Auto remaval ot bJ'paae above l 700 paia. (c) One ot the illoperable cbamlela must. be>in the tripped condition. 3-79 No. ;"r,\rrof\\' _ **;,; \ !.\U\.1.\.\J. t\)?'t 'J<<1 n1 znnm MSn1m-Pend.asible Openble Desree ot !Jpaa* No ?uncticml. Unit 0.zmela Jtedttnd"7 Conditions l Isolation

*j.. -*1<>-.

-* 2 (a,c)

  • a. ContaimDlmt Jligh l --!bring f;ee.k'

.. ** .:i, Pressure .. t ..... b. Containment Jligh 2(c) l Jloae Badiation

c. Manual l lone !lone 2 Steam Line Isolation a .. IAJv Steam Gen 2/Steam(c)
  • l Below 550 Paia(b) Pressure Gen b. Manual. l/Stesm lone Bone Gen (a) Right and left actuation circu1 ts each bave 2 cbamiels. (b) * :9ypass autOtDaticall)'

reinstated above 550 psia. (c) One of the inoperable channels must be in the tripped position. 3-SO *;; Table 3.17.4 l* Instrumentation Operating Requirements for Other Safety Feature Functions No Functional Unit Minimum Operabl e Degree of Channels Redundancy Perm-i-ss-i bl e Bypass Conditions 2 SIRWT Low-Level Switches /J.T -Power Comparator 4 NA<bl 1 No+ re.'llu.1r<-&l be.lo....i 3'Z..5°i:::, One channel may be inoperable for a period of 7 days CbJ Nooe Not reiu..1M-d. Q.t OV' b<..l .. U-1 Uot-s 1-\1.d*d ow .... 3 (Deleted) 4 5 6 7 Air Cooler Service 1 Water Flow Instruments Primary and Secondary l Rod Insertion and Out-of-Sequence Monitors Fuel Pool Building 1 Crane Interlocks Source-Range Channels 2 None None None -NeAe l\Lo.f re'Q. '4* J) be.Lo...v "3"2..S f:" -HA N.ot re 0 1L1rcJ A-t-or belou..1 t-{ .. + s>u..tdo...ur. As Requested Under Administrative Cont ro 1 s <*> Not Required Above 10-4% of Rated Power or "o f:u.,_ I l I"\ +-h. re.a.._c_+o r (a) Crane shall not be used to move material past the fuel storage pool unless the interlocks are available. (b) If a channel is declared inoperable, it shall be placed in a bypass condition._ Minimum degree of redundancy is not applicable. to the SIRWT low-level switches. (c) If only two channels are* operable, load shall be reduced to 70% or less of rated power. (d) Minimum operable channels shall be one (1) and minimum degree of redundancy is zero (0). neutron power levels indicated on the wide range channels *are three times the lowest decade in which neutron visibility can be confi_, visibility will be confirmed through observation of reactivit*_. J(ing,s on neutron power level (including a l/M plot during reactor start-up)'. the observed changes to the changes noted on previous similar Instrumentation operability will also be verified by comparison among the three operable channels to ensure their individual responses are in agreement.

  • 3-81 Amendment No. JiJ, February 15, 199+

.. No Functional Unit 8. 9. 10. Pressurizer Wide Range Water Level Indication Pressurizer Code Safety Relief Valves Position Indication (Acoustic Monitor or Temperature Indication) Po.t1h.,...,. !"cLic..i...r'°"" Power(Operated Relief Valves)(Acoustic Monitor or Temperature Indication)

11.
  • PORV Isolation Valves Position Indication
12. 13. 14. 15. 16. 17. 18. Subcooling Margin Monitor Auxiliary Feed Flow Rate Indication Auxiliary Feedwater Actuation System Sensor Channels Auxiliary Feedwater.

Actuation System Actuation Channels Excore Detector Deviation Alarms Axial Shape Index Alarm Reactor Vessel Water Level TSP0889-0176-NL04 Table 3.17.4 (Cont'd) Minimum*----Operable Channels 2 (m, P, q) 1 per Valve 1 per Valve 1 per Valve 1 (h) 1 per flow Control Valve 2 per ste'Fe generator e) ---Mi-nimum--

  • Degree of Redundancy None None None None* None None 1 1 None 1 None ---Permissible-.

Bypass Conditions Not required in Cold or Refueling Shutdown Not Required below 325°F 1 \'\ c.e 16 S or Not requiredAwhen PORV isolation valve is closed and its indication system is operable Not required when reactor is depressurized and vented through a vent sq.in. Not required below 325°F Not required below 325°F Not required below 325°F Not required below 325°F -Not Required Below 25% of Rated Power Not Required Below 25% of Rated Power Not Requiri=d Below 325°F 3-8la Amendment No. f7, f8, 9f, llJ, US. Mi -September 15, 1989 l '-L-}}

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