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: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' PDR ADOCK 05000255 

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3.17 INSTRUMENTATION AND CONTROL SYSTEMS Applicability The instrumentation and control systems shall be operable under the following conditions: 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3 .17 .1 When the PCS has less than Refueling Boron Concentration and more than one control rod is capable of being withdrawn, except as allowed by the permissible bypass conditions.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 is ~ 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 permissable bypass conditions. Objective 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 exceedin~ 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. 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. TSPR9102

3.17 INSTRUMENTATION AND CONTROL SYSTEMS (Cont'd) 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 Mar~in 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 1erances in setting and for to 1eran*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 lo~ic can be changed to a two-out-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. 11~, TSPR9102

3.17 INSTRUMENTATION AND CONTROL SYSTEMS (Contd) 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 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 Table 3.17.4.

The Recirculation Actuation System (RAS) initiates on a 1 out of 2 take~ 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 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 assuranc~ that ~n 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 the1 allowed power is increased to io- %. References ( 1) Updated FSAR, Section 7.2.7. ( 2) Updat~d FSAR, Section 7.2.5.2 3-77 Amendment No. 11~, 1i,,1~~' TSPR9102

Table 3.I7.I Instrumentation Operating Requirements for Reactor Protective System Minimum Minimum Permissible Operable Degree of Bypass No. Functional Unit Channels Redundancy Conditions

1. Manual I -None None.*

(Trip Buttons) I

2. Variable High None.

Power Level

3. Wide Range 2 I Bel ow 10-43<*> or Above I3% of Channels *. Rated Power<a> except as noted in {c).
4. Thermal Mar~in/ I Below 10-43<*> of Rated Power<a>

Low Pres sun zer and greater than cold shutdown Pressure boron conce~tration. *

5. High Pressurizer I None.

Pressure

6. Low Flow Loop I Below 10-43<*> of Rated Power<a>
                                                         ~nd greater than cold shutdown boron concentration.
7. Loss of Load I None Bel ow I 7% of Rated Power<a>.
8. Low Steam 2/Steam I/Steam None.

Generator Gen Generator Water Level I

9. Low Steam 2/Steam I/Steam Bel ow 10-43<*> of Rated Power<a>

Generator Gen Generator and greater than cold shutdown Pressure boron concentration.

10. High Containment 2(b) I None.

Pressure I Bypass automatically removed.

  • m One of the inoperable channels must be in the tripped condition.
       ~wo ~hannels~required if TM/LP, Low-Steam Generator Pressure,. or Low Flow Loop channels are bypassed.                *

(d) If only two channels are operable, load shall be reduced to 1 ~ 70% rated power. .( e) For Low Power Physics Testing, Io-43 may be increased to I0- % and cold shutdown boron concentration is not required. ( f) Axial Offset operability requirements are given in Specification 3.II.2. 3-78 Amendment No. JJ~, ,,~, J~~' TSPR9I02

Table 3.17.2 Instrumentation Ogerating Reguirements for Engineered Safety Feature Systems Minimum Minimum Permissible O~erable Dearee of Bypass No Functional Unit C annels Re undancy Conditions 1 Safety Injection

a. Manual {Trip 1 None None Buttons)
b. High Containment 2(a,c) 1 None Pressure
c. Pressurizer Low 2<c) .1 Primar~ Pressure
    .Pressure                                           Less T an 1700 Psia<bl
2. Containment Sgray
a. Manual 2 None None
b. High Containment 2(a,c) 1 None Pressure 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 Amendment No. TSPR9102 

        *.                           Table 3.17.3 Instrument Operatfoq Condjtions for- Isolation Functions Minimum       Minimum        Permissible O~erable      Dearee of     Bypass No   Functional Unit       C annels      Re undanc~    Conditions 1    Containment Isolation
a. Containment High 2(a,c) 1 None Pressure
b. Containment High 2<c) 1 none Radiation
c. Manua 1 1 none none*

2 Steam Line Isolation

a. Low Steam Gen 2/Steam<c> 1 Below 550 psia

Pressure Gen

b. 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 Amendment No. TSPR9102

Table 3.17.4 Instrumentation Operating Requirements for Other Safety Feature Functions Minimum Minimum Permissible Operable Degree of Bypass No Functional Unit Channels Redundancy Conditions 1 SIRWT Low-Level 4 Not reguired below 325°F. One Switches channel may be inoperable for a period of 7 days CbJ 2 AT - Power 1 Not required at or below Hot Comparator Shutdown 3 (Deleted) 4 Air Cooler Service 1 None Not required at or below Hot Water Flow Instruments Shutdown 5 Primary and Secondary 1 None NA Rod Insertion and Out-of-Sequence Monitors 6 Fuel Pool Building 1 None As Requeited Under Crane Interlocks Administrative Control s<aJ 7 Start-Up Channels 2 1(d) - . Not Required Above 10-43 of Rated Power or with no fuel in the reactor. (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 ~e reduced to 70% or less of rated power . .(d) f Minimum operable channels shall be one 1) and minimum degree of redundancy is 

       - zero* (0) if shutdown neutron power leve s indicated on the wide, ran~e 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
                                                                                 ~~~~g¢/~~1n Amendment No. 1~1, 1~~' 1~~'

TSPR9102

e Table 3.17.4 (Cont'd) Minimum Minimum Permissible O~erable Dearee of Bypass . No Functional Unit C annels Re undanc~ 2 (m, p, q) None Conditions 8." Pressurizer Wide Not required in Ran~e Water Level Cold or Refueling Indication Shutdown

9. Pressurizer Code 1 ~er None Not Required Safety Relief Valves Va ve below 325°F Position Indication tAcoustic Monitor or emperature Indication)
10. Power O~erated Relief 1 per None Not req~ired 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 ~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 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, '~' ~ 11~, 11~, Ji~.

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 

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- - - - --...>-~ -=~-.~pp;U** t'3-)Uift~ !astrumentatioa !!)"!Items. ObJective To delineate the conditions ot the plant instrumentation and control systems necessary to assure react.or sa.tety. Soecit1cat ions Defe.'.Q 

            ;.17.1 , The epeFabilhy et ~he plant 1aatl'umeat aa.4 eoatr-.i. ayat m aha 11 be ia aeee* 1 0-ee *.rita ia~lee 3,17.1 iare~ 3,17,4.

3.i1.2 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 ~reveat exceeding established limits. Sa!ety is not co:nproc:lised, hovever, by continuinc operation vith certain instrw!leotation 

                              ~hannels            out ot service s!nce ~revisions vere i11ade tor this in the plant design. This speciticatioo ou~lines li.mitiag conditions for o;:eration necessary to preserve the effectiveness ot the reactor control a.nd             '9rotecti~n     s:rste.m    *1he~ q,ey -:::.e -:r :ore ~~   :b.e  .:~els are out ot service.
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B ~ ~ A, __ St cw. .. ,l reactor pro t ect i on a.n d. ec.g i oeere d sa.f egua.r~ ..e. c ha.nne l s U'~ supplled vit~ 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. CJ /(,'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 is~ 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 ch.~nnels to perform control rod testing or to perform low power physt~i~1:,~:,_sting below normal operating temperatures. The requirement to main*t:§~_jf:col'd shutdown boron concentration when in the bypass condition provi~adcUtional assurance that an accidental criticality will not occur~~-<t~~;. 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. JJ~, n,, 136 February 15, 1991 

           '*                                         Table 3 .17 .1 Instrumentation Ooeratinq Requirements for Reactor Protective System
                                . - M.i ni mum*_.:_ _ _ Mf.n:i.mum ___,;_;:~-:____ :~P-ermts*stble ____ _____ __ _ ___ __ _____ __ ___ .

Operable Degree of _ Bypass Funct i On al .Un11t *chaririel s' *~- \Redundancy *'} <, Cbnd rtri ons 

                                              .'t*: -         , __ **j    ('c:_.,   '*   ..        :    :-1;** .
1. Manua 1 {Trfp * ;: *-.  :-} . '

Buttons)~- 

                        ~ 1*  '
2. Variable Higl< . 2(b.d) *None Power Level )JIN.....
                                                                                         .             . =;_":~;
3. Wide -Rang~_ 2 'l 'Be-low ~;HJ?

Channels ~ 13 ¥5% ':Rafeli as

No.ted*:~\i-n J
                                                                                        *':.. ,__'   :* '.        .. : -~;:i-.;.-::: .. J~ .
4. Thermal Margin/ 1 B~low *10;*,*c*> :of Rated Low-Pressurizer . :power<*> and greater than Pressure '}l'J.. =.*-cold *-shutdown boron
                                                                                      -concentration
5. High-Pressurizer I None Pressure~
6. Low Fl ow Loop J<<l. I Bel ow 10-43<*> of
                                                                                      -Rated Power<*> and greater than cold shutdown boron concentration.
                                                                                       ~llo,                     T1                        :::>    (11.)
7. Loss of Load '-'w. I None ~....., 1110 lA..W r-ow<.r .
8. ~ Low Steam Gen- 2/Steam I/Steam None
   <: erator Water                   Gen              Generator
   - Level )cl..
9. Low Steam Gen- 2/Steam I/Steam Bel ow Io-43<*> of erator Pressure Gen Generator Rated Power<*> and greater
      ~                                                                                than cold shutdown boron con-centration.
10. High Containment I None Pressure~

(a) Bypass automatically removed. (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) Re~ijirea eperaele if aAy clutch power supply is e~ergized (h) Automatically bypassed below 15% power. 3-78 Amendment No. JJ~. J~~. ~ j;'ebruary 15, 199 l 

       ~
                           - - -- - -   -TabTe }~17-;2 e

Instrumentation Operatillg Requirements for Engineered S&tety l'ea~ Systems Minimum Jttn1nnun Permissible Operable J.Vpase lo ll'um:tional Unit Cbazmels Cond.itiocs 1 Safety Injection 11.. Manual (Tr! p l lone lone 

        ~ttons) 2(a.,c)                               Ne"~en
b. High Containment l ibr1ng Leak Pressure
~.      Pressurizer I.ow              2~c)             l        Prima1'7    Pres sure Pressure                                                 Lesa ~ lTOO Paia(b 2        Contaiment S'D?'BI
a. Manual 2 lone !one.

2(a.,c) No"e.

b. High Containment l ~'l"i:l"Ur ~ qt~fl't, Pressure
               -~~ -
ft_~

(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. 

                                                                                      ;"r,\rrof\\'          ~n _
                                                                                      **;,; ;.,:\~ \ !.\U\.1.\.\J.

3-79 /tl'K~fl'\el\.+ No. t\)?'t 

                                'J<<1 n1 znnm       MSn1m-          Pend.asible Openble         Desree ot           !Jpaa*                                  *;;

No ?uncticml. Unit 0.zmela Jtedttnd"7 Conditions l Conta~mr.eut Isolation  ; *j.. -*1<>-. ~~.;.. -* 

                                                                        ~ Cl'\i,;;:,:1_~,,;71. *
a. ContaimDlmt Jligh 2(a,c) l --!bring f;ee.k' fiit~t
                                                                                   **      ~*~~..  .: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 circu1ts 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 Minimum -Mi-nimum- Perm-i-ss-i bl e Operabl e Degree of Bypass No Functional Unit Channels Redundancy Conditions No+ re.'llu.1r<-&l be.lo....i 3'Z..5°i:::, SIRWT Low-Level 4 NA<bl One channel may be Switches inoperable for a period of 7 days CbJ 2 /J.T - Power 1 Nooe Not reiu..1M- d. Q.t OV' Comparator b<..l .. U-1 Uot- s 1-\1.d*d ow .... 3 (Deleted) 4 Air Cooler Service 1 None -NeAe l\Lo.f re'Q. '4* ,..~ J) Water Flow Instruments be.Lo...v "3"2..S f:" 5 Primary and Secondary l None -HA N.ot re 1L1rcJ A-t- or 0 belou..1 t-{ .. + s>u..tdo...ur. Rod Insertion and Out-of-Sequence Monitors 6 Fuel Pool Building 1 None As Requested Under Crane Interlocks Administrative Cont ro 1s <*> 7 Source-Range 2 Not Required Above Channels 10-4% of Rated Power or ~ 1+~ "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). j_t.*'"$~1:1tdown neutron power levels indicated on the wide range channels 

   *are greatl.F~t)an three times the lowest decade in which neutron visibility can be confi_, \~-Neutron visibility will be confirmed through observation of reactivit*_. J(ing,s on neutron power level (including a l/M plot during reactor start-up)'. an~'comparing* the observed changes to the changes noted on previous similar start~ups. Instrumentation operability will also be verified by comparison among the three operable channels to ensure their individual responses are in agreement.
  • 3-81 i~~~~,1~~1n Amendment No. JiJ, Ji~. lZ-~

February 15, 199+

Table 3.17.4 (Cont'd) Minimum*- -- - -- -Mi-nimum-- * ---Permissible-. Operable Degree of Bypass No Functional Unit Channels Redundancy Conditions 2 (m, P, q) None

8. Pressurizer Wide Not required in Range Water Level Cold or Refueling Indication Shutdown
9. Pressurizer Code 1 per None Not Required Safety Relief Valves Valve below 325°F Position Indication (Acoustic Monitor or Temperature Indication) c.e 16 S ~'4.. ~d.<>w"'

l Po.t1h.,...,. !"cLic..i...r'°"" 1\'\ or

10. Power(Operated Relief 1 per None Not requiredAwhen Valves)(Acoustic Valve PORV isolation valve Monitor or Temperature is closed and its Indication) 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 ~1.3 sq.in.
12. Subcooling Margin 1 None Not required Monitor below 325°F (h)
13. Auxiliary Feed Flow 1 per flow None Not required Rate Indication Control below 325°F Valve
14. Auxiliary Feedwater 2 per ste'Fe 1 Not required Actuation System generator e) below 325°F Sensor Channels
15. Auxiliary Feedwater. 1 Not required Actuation System below 325°F -

Actuation Channels

16. Excore Detector None Not Required Below Deviation Alarms 25% of Rated Power
17. Axial Shape Index 1 Not Required Below Alarm 25% of Rated Power
18. Reactor Vessel Water Level None Not Requiri=d Below 325°F L-3-8la Amendment No. f7, f8, 9f, llJ, US. Mi
                                                                    -September 15, 1989 TSP0889-0176-NL04}}
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