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{{#Wiki_filter:ATTACHMENT I Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST INSTRUMENT  
{{#Wiki_filter:ATTACHMENT I Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST INSTRUMENT &CONTROL SYSTEMS PROPOSED TECHNICAL SPECIFICATIONS PAGES March 18, 1991 8 Pages
& CONTROL SYSTEMS PROPOSED TECHNICAL SPECIFICATIONS PAGES ' ,....1031:3 P.DR-ADOCK  
    '         ,....1031:3 ~    \ \
-PDR p March 18, 1991 8 Pages \ \ 
<i11ri325033~ ~
. 3 .17 INSTRUMENTATION AND CONTROL SYSTEMS Applicability The instrumentation and control systems shall be operable under the following conditions:
P.DR- ADOCK b~00025-
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Objective When the PCS has less than Refueling Boron Concentration and more than one control rod is capable of being withdrawn, except as allowed by the permissible bypass conditions.
                -   PDR p
* When the PCS temperature is 325&deg;F, except as allowed by the permissible bypass conditions.
 
When the PCS is above Cold Shutdown, except as allowed by the permissible bypass conditions.
. 3 .17   INSTRUMENTATION AND CONTROL SYSTEMS Applicability The instrumentation and control systems shall be operable under the following conditions:
At all times, except as allowed by the permissable bypass 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        When the PCS has less than Refueling Boron Concentration and more than one control rod is capable of being withdrawn, except as allowed by the permissible bypass conditions.
To delineate the conditions of the plant i.nstrumentation and control systems necessary to assure reactor safety. Specifications
* Table 3.17.2        When the PCS temperature is ~ 325&deg;F, except as allowed by the permissible bypass conditions.
: 3. 17. 1 Deleted 3.17.2 In the event the number of channels of a particular system in service falls below the limits given in the columns entitled "Minimum.
Table 3.17.3        When the PCS is above Cold Shutdown, except as allowed by the permissible bypass conditions.
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 shutdown condition within 24 hours. TSPR9102 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 continuing operation with certain instrumentation channels out of service since provisions were made for this in the plant design. This specification outlines limiting cohditions 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 Bol'.'on Concentration or *.if only one control rod is capable -of being withdrawn.
Table 3.17.4        At all times, except as allowed by the permissable bypass conditions.
Objective To delineate the conditions of the plant i.nstrumentation and control systems necessary to assure reactor safety.
Specifications
: 3. 17. 1 Deleted 3.17.2   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 ~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 continuing operation with certain instrumentation channels out of service since provisions were made for this in the plant design. This specification outlines limiting cohditions 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 Bol'.'on Concentration or *.if only one control rod is capable -
of being withdrawn.
3-76 Amendment No.
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.
TSPR9102
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 assumptions and shutdown margin requirements will be met. When the reactor power 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 of Load trip is deactivated and the Rate of Power Change is reinstated.
3.17       INSTRUMENTATION AND CONTROL SYSTEMS   (Cont'd)
These switching actions occur automatically.
Refueling boron concentration requires a 5% shutdown margin with all
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.
        . the control rods removed from the core. Therefore, there is no need for automatic control rod insertion.
Almost all reactor protection and engineered safeguards channels are supplied with sufficient.
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 assumptions and shutdown margin requirements will be met.
redundancy to provide the capability for channel test at power. Exceptions are backup channels such as loss-of-load trip.
When the reactor power 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 Lo~s 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.
* When one of the four channels is taken -0ut 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),'
Neither the Rate of Power Change trip nor the Loss of Load trip are relied upon in the safety analyses.
11 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.
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.
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.
* When one of the four channels is taken -0ut 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.
e* 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 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.
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),' 11 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
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 taken twice logic scheme. Any one channel declared inoperable shall be placed in a bypass condition to ensure protection from an inadvertent RAS actuation.
: 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.
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 i$ limited. The Zero Power* Mode Bypass can be used to bypass the 1 ow fl ow, steam generator 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.
3-76a Amendment No. 1J~,
The requirement to maintain cold shutdown boron concentration w_hen in the bypass condition provides additional assurance that an accidental criticality will not occur. Tp allow low power physics testing at reduced temperature and pressure, the requirement for cold shutdown borori 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.
TSPR9102
No. 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. (a) (b) (c) (d) (e) ( f) : e
 
* Table 3.17.l Instrumentation Ogerating Reguirements for Reactor Protective System Minimum Minimum Permissible Degree of Bypass Functional Unit C annels Redundancy Conditions Manual 1 None None (Trip Buttons) Variable High Power Level 2(b,d) 1 (d) None Wide Range 2 1 Below 10-4 3<e> or Above 133 of Channels Rated Power<a> except as noted in ( c) Thermal Margin/ ' 2(b,f) 1 Bel ow 10-4 3 Cel of Rated Power<a> Low-Pressurizer and greater than cold shutdown Pressure boron contentration High-Pressurizer 2(b) 1 None Pressure Low Flow Loop 2(b) 1 Bel ow 10-4 3<e> of Rated Power<*> and greater than cold' shutdown boron concentration.
e*
Loss of Load 1 None Selow 173 of Rated Power<a>
3.17     INSTRUMENTATION AND CONTROL SYSTEMS   (Contd)
* Low Steam 2/Steam I/Steam None Generator Gen<b> Generator Water Level Low Steam 2/Steam I/Steam Bel ow io-4 3<e> of Rated Power<al Generator Gen<b> Generator and greater than cold shutdown Pressure boron concentration.
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.
High Containment 2(b) 1 None Pressure Bypass automatically removed. One of the inoperable channels must be in the tripped condition.
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 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-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.                                       .
Two channels required if TM/LP, low steam generator, or low-flow channels are bypassed.
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 i$
If only two channels are operable, load shall be reduced to 703 or less of rated power. For low power physics testing, io-*3 may be increased to io-1 3 and cold shutdown boron concentration is not required.
limited.
Axial Offset operability requirements are given in Specification 3.11.2. 3-78 Amendment No.
The Zero Power* Mode Bypass can be used to bypass the 1ow fl ow, steam generator l~w 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 w_hen in the bypass condition provides additional assurance that an accidental criticality will not occur. Tp allow low power physics testing at reduced temperature and pressure, the requirement for cold shutdown borori concentration-is not required and the1 allowed power is increased to       *         .
TSPR9102 No 1 a. b. c. 2. a. b.
10- %. .
* Table 3.17.2 Instrumentation Ogerating Reguirements for Engineerea Safety Feature Systems Minimum Minimum Permissible Funct i ona 1 Un it C annels Degree of Redundancy 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 Psi a Cb> Containment Sgray Manua 1 2 None None High Containment 2(a,c) 1 None Pressure Right and left actuation circuits each have 2 channels.
References
Auto removal of bypass above 1700 psia. One of the inoperable channels must be in the tripped 3-79 TSPR9102 Amendment No.
( 1) Updated FSAR, *Section 7. 2. 7.
Table 3.17.3 * *
(2) Updated FSAR, Section 7.2.5.2 3-77 Amendment No. JJ~, J~~,J~~.
* Instrument Operating Conditions for Isolation Functions Minimum Minimum Permissible No Functional Unit C annels of Re Bypass Conditions 1 Containment Isolation
TSPR9102
: a. Containment High 2 (a,c) 1 None Pressure b. Containment Radiation High 2(c) 1 None c. Manual 1 None, None 2 Steam Line Isolation
 
: a. Low Steam Gen 2/Steam<c>
:
1 Below 550 psia<b> Pressure Gen b. Manual I/Steam None None Gen Right and left actuation circuits each have*2 channels.
e          Table 3.17.l
__ Bypass automatically reinstated above 550 psia. -One of the inoperable channels must be in the tripped position.
* Instrumentation Ogerating Reguirements for Reactor Protective System Minimum    Minimum        Permissible O~erable    Degree of      Bypass No.     Functional Unit        C annels    Redundancy    Conditions
3-80 Amendment No. TSPR9102 No 1 2 3 4 5 6 7 (a} (b} <<=> (d} Table 3.17.4 Instrumentation Operating Requirements for Other Safety Feature Functions Minimum Minimum Permissible Functional Unit
: 1.       Manual                1          None          None (Trip Buttons)
* C annel s Degree of Redundancy Bypass Conditions SIRWT Low-Level 4 NA<b> Not required below 325&deg;F. One Switches channel may be inoperable for a period of 7 days Cb> !T -Power 3Cc) 1 Not required at or below Hot Comparator Shutdown {Deleted}
: 2.      Variable High          2(b,d)     1(d)           None Power Level
Air Cooler Service 1 None Not required at or below Hot Water Flow Instruments Shutdown Primary and Secondary Rod Insertion and 1 None NA Out-of-Sequence Monitors Fuel Pool Building l
: 3.       Wide Range            2          1              Below 10- 43<e> or Above 133 of Channels                                          Rated Power<a> except as noted in ( c)
* None As Requested Under Crane Interlocks Administrative Control s<a> Start-Up Channels 2 1 (d) Not Re$uired Above. 10-43 o Rated Power or with no fuel in the reactor. Crane shall not be used to move material
: 4.      Thermal Margin/      ' 2(b,f)     1             Bel ow 10- 43 Cel of Rated Power<a>
Low-Pressurizer                                  and greater than cold shutdown Pressure                                          boron contentration
: 5.      High-Pressurizer      2(b)       1             None Pressure
: 6.      Low Flow Loop          2(b)        1              Bel ow 10- 43<e> of Rated Power<*>
and greater than cold' shutdown boron concentration.
: 7.      Loss of Load          1           None           Selow 173 of Rated Power<a>
: 8.
* Low Steam             2/Steam     I/Steam       None Generator             Gen<b>     Generator Water Level
: 9.      Low Steam             2/Steam     I/Steam       Bel ow io- 43<e> of Rated Power<al Generator             Gen<b>     Generator     and greater than cold shutdown Pressure                                         boron concentration.
: 10.      High Containment       2(b)       1             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 703 or less of rated power.
(e)      For low power physics testing, io-*3 may be increased to io- 13 and cold shutdown boron concentration is not required.
( f)    Axial Offset operability requirements are given in Specification 3.11.2.
3-78 Amendment No. 11~, 1~~' l~~.
TSPR9102
 
Table 3.17.2
* Instrumentation Ogerating Reguirements for Engineerea Safety Feature Systems Minimum     Minimum       Permissible O~erable    Degree of      Bypass No  Funct i ona 1 Un it       C annels     Redundancy   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 Psi a Cb>
: 2. Containment Sgray
: a. Manua 1                   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 c~ndition.
3-79 Amendment No.
TSPR9102
 
Table 3.17.3
          * *
* Instrument Operating Conditions for Isolation Functions Minimum       Minimum       Permissible O~erable      De~ree  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. Manual                 1             None,         None 2   Steam Line Isolation
: a. Low Steam Gen         2/Steam<c>   1             Below 550 psia<b>
Pressure               Gen
: b. Manual                 I/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 O~erable Degree of      Bypass No      Functional Unit
* C annel s Redundancy   Conditions 1      SIRWT Low-Level           4         NA<b>       Not required below 325&deg;F. One Switches                                         channel may be inoperable for a period of 7 days Cb>
2      !T - Power               3Cc)       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       l*         None         As Requested Under Crane Interlocks                                 Administrative Control s<a>
7      Start-Up Channels         2         1(d)        Not Re$uired Above.
10-43 o Rated Power or with no fuel in the reactor.              I*
(a}    Crane shall not be used to move material past the fuel storage pool unless the
* interlocks are available.
* interlocks are available.
past the fuel storage pool unless the . ' If a channel is declared inoperable, it shall be placed in a bypass condition.
              .       '
(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.
Minimum degree of redundancy is not applicable to the SIRWT low-level switches.
If only two channels are operable, load shall be reduced to 70% or less of rated power. Minimum operable channels shall be one fl} 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.
<<=>    If only two channels are operable, load shall be reduced to 70% or less of rated power.
Neutron visibility*will be confirmed through observation of reactivity changes on neutron power level (including a l/M plot during reactor start-up}
(d}    Minimum operable channels shall be one fl} 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 comparison among the three operable channels to ensure their individual
and 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.
* responses are. in agreement.
TSPR9102 3-81 n Amendment No. JiJ, I*
3-81 Amendment No.
Table 3.17.4 (Cont'd) Minimum Minimum Permissible 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&deg;F Position Indication fAcoustic Monitor or emperature Indication)
                                                                              ~~~~~&#xa2;/~~;
: 10. Power Relief 1 per None Not required in cold shutdown Valves osition Indication or when PORV isolation f Acoustic Monitor or . valve is closed emperature Indication) and. its indication system is operable 11. PORV Valves 1 ver None Not required when Position Indication Va ve reactor is depressurized  
JiJ, Ji~.
*and vented through a vent sq. in. J 12. Subcooling Margin Monitor 1 None. Not required below 325&deg;F 13. Auxiliary Feed Flow 1 per None Not required Rate Indication fl ow<h> below 325&deg;F Control Valve 14. Auxiliary Feedwater 2 per 1 Not required Actuation System steam below 325&deg;F Sensor Channels generator<*>
n J~~.
: 15. Auxiliary Feedwater 2(f) l 'Not required Actuation below 325&deg;F Actuation C annels 16. Excore Detector . 1 (g) None Not Required Deviation Alarms Below 25% of Rated Power 17. Axial Shape Alarm In.sJex 2(1) 1 Not Required Below 25% of Rated Power 18. Reactor Vessel 2(j,k,1'.m)
TSPR9102
None Not Required Water Level Below 325&deg;F ---*---3-8la Amendment TSPR9102 ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST INSTRUMENT  
 
& CONTROL SYSTEMS MARKED UP EXISTING TECHNICAL SPECIFICATIONS PAGES March 18, 1991 7 Pages
Table 3.17.4 (Cont'd)
:.:1 .,, ............ ..._. .._ .. 1 -***--
Minimum       Minimum       Permissible O~erable      De~ree  of     Bypass No   Functional Unit           C 2 annels     Re undanc~
Go iastl"'Wleatatiea systems. A ObJective To delineate the conditions ot the plant instrumentation and co?ltrol necessary to assure reactor safety. Seeciticat ions et ple'e eeatFGl systems she?? ia aeeerc!.a!!ee  
(m, p, q) None           Conditions 8."  Pressurizer Wide                                        Not required in Ran~e Water Level                                       Cold or Refueling Indication                                             Shutdown
'iri'h iablea 3.17.1 3 .l T .2 In the event the number ot channels ot a particular system. in service falls belov the limits given 1:1 the columns entitled "Minimum Operable Cb&zu:lel.s" or "Minimum Degree ot Redundancy," except as concil.tioned by the column entitled. "Permissible ay,ass Co::.diticns!" tte reactor sball be ;>laced. in a hot shuttioYU coaditioil within 12 hours. It mini:aum.
: 9. Pressurizer Code           1 ~er        None           Not Required Safety Relief Valves       Va ve                       below 325&deg;F Position Indication fAcoustic Monitor or emperature Indication)
concil.tions are not met withln 24 hours, the reactor shall be placed in a cold shutdoYU concil.tion within 24 hours. Basis During plant operations, the complete iostru:nentation systems will nor:ia.l.ly be in service. Reactor safety is provided by the reactor protection system, vbich automatic&lly initiates appropriate action exceec.ing established limits. Sa!ety is not cc:::pro::dsed, however, by continuing operation with certain cut servi:e *s!nce were 111ade tor tllis in the pl&.llt design. This speciticatioa limiti!lg for o;eration necessar.r to preserve the eftectiveoess ot the reactor control 8..lld system g,ny '.:::.e :ore ot ";lle .:::..a.n.:iels
: 10. Power O~erated Relief 1 per             None           Not required in cold shutdown Valves osition Indication                               or when PORV isolation f Acoustic Monitor or     .                             valve is closed emperature Indication)                               and. its indication system is operable
_ are out ot service.
: 11. PORV Is~lation Valves     1 ver         None           Not required when Position Indication       Va ve                       reactor is depressurized *and vented through a vent ~L3 sq. in.
all reactor protection 8..lld ecgiaeered sa!egu.a.rds channels -"'* u-e 9upp.lied vitti sut!'icient  
J
':o ;ronde the capability for chiim<<l t*est at pover. Exceptions are backup cb.a.anels such as loss-ot-ld.ad trip. W'ben one ot the tour channels is taken out ot service tor maintenance, *the protective system logic can be changed to a two-out-o.t-three coincidence tor a reactor trip by bypassing the* removed channel.
: 12. Subcooling Margin         1             None.         Not required Monitor                                                below 325&deg;F
I ' ; i 1* j' .! () I') --*-.; '>vv 3-76 A The instrumentation and control systems shall be operable under the following conditions:
: 13. Auxiliary Feed Flow       1 per         None           Not required Rate Indication           fl ow<h>                     below 325&deg;F Control Valve
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.
: 14. Auxiliary Feedwater       2 per         1             Not required Actuation System           steam                       below 325&deg;F Sensor Channels           generator<*>
Table 3.17.2 -When the PCS temperature 325&deg;F, except as allowed by the permissible bypass conditions.
: 15. Auxiliary Feedwater       2(f)         l             'Not required Actuation S~stem                                        below 325&deg;F Actuation C annels
Table 3.17.3 -When the PCS is above Cold Shutdown, except as allowed by the permissible bypass conditions.
: 16. Excore Detector         . 1(g)         None           Not Required Deviation Alarms                                       Below 25% of Rated Power
Table 3.17.4 -At all times, except as allowed by the permissible bypass conditions.
: 17. Axial Shape In.sJex       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&deg;F                   ---*- -~ --
3-8la Amendment No.~7, ~~' ~~' 11~, 11~, J~~.
TSPR9102
 
ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST INSTRUMENT & CONTROL SYSTEMS MARKED UP EXISTING TECHNICAL SPECIFICATIONS PAGES March 18, 1991 7 Pages
 
      ~. :.:1                                 .,,............
                                                *~4 ..._. .._ ..
                                                                  ~~*
1 -***- -
  .:J>tSEfll-~ App~ids            Go plaa~ iastl"'Wleatatiea systems.
A             ObJective To delineate the conditions ot the plant instrumentation and co?ltrol syst~ necessary to assure reactor safety.
Seeciticat ions
      ;.i;.~            ~e'~~~aeilhy          et ~he ple'e iast~e~ ~d. eeatFGl systems she??
                        ~e ia aeeerc!.a!!ee 'iri'h iablea 3.17.1 ~hre~ 3,17.~.
3 .l T.2         In the event the number ot channels ot a particular system. in service falls belov the limits given 1:1 the columns entitled "Minimum Operable Cb&zu:lel.s" or "Minimum Degree ot Redundancy,"
except as concil.tioned by the column entitled. "Permissible ay,ass Co::.diticns!" tte reactor sball be ;>laced. in a hot shuttioYU coaditioil within 12 hours.           It mini:aum. concil.tions are not met withln 24 hours, the reactor shall be placed in a cold shutdoYU concil.tion within 24 hours.
Basis During plant operations, the complete iostru:nentation systems will nor:ia.l.ly be in service.                   Reactor safety is provided by the reactor protection system, vbich automatic&lly initiates appropriate action
                        ~c ~reve~t      exceec.ing established limits.                           Sa!ety is not cc:::pro::dsed, however, by continuing operation with certain                                 Uistrui:e~tation
                        ~hannel..s  cut   ~t servi:e *s!nce                 ~roVisioos        were 111ade tor tllis in the pl&.llt design.     This speciticatioa                     ou~lines      limiti!lg cooditio~s      for o;eration necessar.r to preserve the eftectiveoess ot the reactor control 8..lld   ~rotection              system   *J'h!!~ g,ny '.:::.e ~r :ore ot ";lle .:::..a.n.:iels
_   s~f            are out ot service.
    ~ f>~Al.most all reactor protection 8..lld ecgiaeered sa!egu.a.rds channels
                                *~  -"'*
u-e 9upp.lied vitti sut!'icient                   redun~c:r        ':o ;ronde the capability for chiim<<l t*est at pover.                       Exceptions are backup cb.a.anels such as loss-ot-ld.ad trip.
W'ben one ot the tour channels is taken out ot service tor maintenance,
                        *the protective system logic can be changed to a two-out-o.t-three coincidence tor a reactor trip by bypassing the* removed channel.
U"';~.  ''t""~-*
  --*-.;
I     ; i j' .! () I')
1*
                  '>vv 3-76
 
A 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&deg;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.
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 53 shutdown margin with all the control rods removed from the core. Therefore, there is no need for automatic control rod insertion.
Refueling boron concentration requires a 53 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.
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 assumptions and shutdown margin requirements will be met.
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 assumptions and shutdown margin requirements will be met. When the reactor power 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 153 of rated power, the Loss of Load trip is deactivated and the Rate of Power Change is reinstated.
When the reactor power 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 153 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 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.
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)
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), 111 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 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), 111 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 .
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.
    .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.
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 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.
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-~ange channel is available and the neutron power level is sufficiently high that it is being monitored by both channels of wide-range instrum~ntation, a startup can be performed in accordance with footnote (d)* of Table 3.17.4.
Since the bypassing of a channel intro-duces the possibility for a failure* to-receive an automatic RAS actuation signal, the time period in th.e 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...
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 th.e bypassed condition is limited.
testing below normal operating temperatures.
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 mainta:t-n:o: cold shutdown boron concentration when in the bypass condition provtd&sk,add1tional assurance that an accidental criticality will not occur~-~~--l<t' 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 10- 1%.
The requirement to mainta:t-n:o:
* References (1) Updated FSAR, Section 7.2.J.
cold shutdown boron concentration when in the bypass condition provtd&sk,add1tional assurance that an accidental criticality will not 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 10-1%.
(2) Updated FSAR, Section 7.2.5.2.
* References (1) Updated FSAR, Section 7.2.J. (2) Updated FSAR, Section 7.2.5.2. h* * "., :' ** ** 3-JZ-Amendment n-, 136 February 15, 1991
h* * "., :' ** -~ **
'1. 2. 3. 4. 5. 6. 7. 8. 9. 10. (a} (b) (c) (d) (e) ( f) (A) Table 3.17.1 Instrumentation Operating Requirements for Reactor Protective System Functional Unit Manual (Trip Variable Power Level r Wide Thermal Margin/
3-JZ-Amendment N~. J-J~, n-, 136 February 15, 1991
Pressure /V High-Pressurizer Pressure }1lf Low Flow Loop ')'If Loss of Load W Low Steam era tor Water Level Low Steam er a tor Pressure )111 High Containment Minimum Operable Channels 1 2 I 2/Steam Gen<b> 2/Steam Gen<b> Bypass ly removed. Minimum Degree of Redundancy None 1 1 1 I None
 
* I/Steam Generator I/Steam* Generator I Permissible Bypass Conditions None None Be 1 ow 1 o-4% <*> or Above I '3 1-5'% Rated Power <*> Except as Noted in Cc> Be 1 ow 1 o-4% <*> of Rated Power<*> and greater than cold shutdown boron concentration None Be 1 ow 10-4% <*> of Rated Power<*> and greater than cold shutdown boron concentration.
Table 3.17.1 Instrumentation Operating Requirements for Reactor Protective System Minimum      Minimum        Permissible Operable      Degree of      Bypass Functional Unit        Channels      Redundancy      Conditions
N-efl.e. Belew 17 PoU)e.r (a.) None Bel ow 10-4% <*> of Rated Power<*> and greater than cold shutdown boron centration.
'1. Manual (Trip            1            None            None Buttons}~
None One of tlie**_:hioperable channels must be in the tripped condition.
: 2. Variable Hig~                                          None Power Level r
Two channels required if TM/LP, low steam generatorifor low-flow channels are _ bypasse.d.
: 3. Wide  Rang~              2            1               Be 1ow 1o-4% <*> or Above Channels~                                        I '3 1-5'%    Rated Power <*> Except as Noted in Cc>
_ -. prti.:.1.1.rt.  
: 4. Thermal Margin/                       1              Be 1ow 1o-4% <*> of Rated Low-Press~izer                                        Power<*> and greater than Pressure /V                                            cold shutdown boron concentration
*1f only two channels are operable, load shall be reduced to 70% or less of rated power. For low power physics testing, 10-4% may be increased' to 10-1% and.cold shutdown boron concentration is not required.
: 5. High-Pressurizer                      1              None Pressure }1lf
Axial Offset operability requirements are given in Specification 3.Il.2. Required operable if any clutch power supply is energized.
: 6. Low Flow Loop ')'If                   I              Be 1ow 10-4% <*> of Rated Power<*> and greater than cold shutdown boron concentration.
I Automatically bypassed helew 1&sect;% power. .. 3-78 Amendment No.
: 7. Loss of Load   W       I            None            N-efl.e. Belew 17 ~ RQ.t~ PoU)e.r (a.)
* February 19, 1991 e e Table j,.17.2 Instrumentation Operat1.cg Requirements for ?ng1neered Satety P'ea-eure Systems M1n1mmn M1n1mnm Permissible Operable B)'pasa ifo Unit Cbazmel.a Condi tiot:.s 1 S&tetL.!!!J.
: 8. Low Steam Gen-          2/Steam
ect ion 11. Manual (Tr! p l 1fcne Bone
* I/Steam         None era tor Water            Gen<b>       Generator Level ~
: b. High Containment 2 (a,c) l t-Jeire_ Jllr1ng :t.a-Pressure , ' I!. ?ressurizer Low 2 *CI l Pressure Pressure Less 1700 Psia(b 2 Contaimnent Soraz a.. Manual 2 lone ?lone b. High Contaimnent 2 (a,ci) l Pressure (a) Right am len actuation circuits each bave 2 cbam:l.ela  
: 9. Low Steam Gen-          2/Steam       I/Steam*        Bel ow 10-4% <*> of er ator Pressure        Gen<b>        Generator      Rated Power<*> and greater
*. (b) . Auto removal ot b7P&as abow lTOO paia. ( c) One ot the im>perable chazmels must be in the tripped condition*.
      )111                                                    than cold shutdown boron con-centration.
3-79 A men&"'"' t N 0 Taole 3.11.3 Ot:Jerating Conditions tor Isolation  
: 10. High Containment                      I               None Pressure~
?unctions M1njmnm M1n1*1* Penliaaible Oi>erable Degree o't !ype.ae Ne ?uncticnal Unit Chazmela Conditions l Containment Isolation 2 (a,c) Ncne_ a. Containment High l Lea& Teat. Pressure b. Coatailmlent High 2(c) l lone Badiation
(a}  Bypass aut~ti'cal ly removed.
: c. l lloae !one 2 Steam Line Isolation
(b)  One of tlie**_:hioperable channels must be in the tripped condition.
: a. U,v Steam Gen 2/Steam(c)  
(c)  Two channels required if TM/LP, low steam generatorifor low-flow channels are
*l Below 550 Psia (b) Pressure Gen b. Manual l/Stesm lone Bone Gen (a) Right and left actuation circuits each ban 2 clmmela. (b)* Bypass automat1c:aJ.l7 reinstated above 550 paia. (c) One or the inoperable channels must be in tm tripped poeition.
_bypasse.d.           _                  -   .          prti.:.1.1.rt.
3-8o
(d) *1f only two channels are operable, load shall be reduced to 70% or less of rated power.
., 2 Table 3.17.4 Instrumentation Operating Requirements for Other Safety Feature Functions Functional Unit SIRWT Low-Level Switches dT -Power Comparator Minimum Operable Channels 4 Minimum Degree-of Redundancy NA<b> 1 Permissible Bypass Conditions be.low 3Z.5 "!= One channel may be inoperable for a period of 7 days<b> r-6 o-C ct.,t or \,e.low \.tot -f:dc"'" 1 3 (Deleted) 4 5 6 7 (a) Air Cooler Service 1 Water Flow Instruments Primary and Secondary 1 Rod Insertion and_ Out-of-Sequence Monitors Fuel Pool Building 1 Crane Interlocks Source-Range Channels 2 None None None Crane shall not be used to move material past interlocks are available.
(e)  For low power physics testing, 10-4% may be increased' to 10- 1% and.cold shutdown boron concentration is not required.
NGnQ N.t1t.  
( f)
\oe.\., i...> ?. 2-S *r: *A Neit
~)
.::t.c or be.lo...., 1-iet Sh.u. H .. .oco.-, As Requested Under Admi*ni strati ve Controls<*>
(A)
Not Required Above 10-4% of Rated Power (!;)r w 1+-h "o I 11'\ th e.. ,.. "-'--+o ,. the fuel storage pool unless the (b) If a channel is declared inoperable, it shall be placed in* a bypass condition.
Axial Offset operability requirements are given in Specification 3.Il.2.
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) if shutdown neutron power levels indicated on the wide range channels are greater than three times the lowest decade in which neutron visibility can be Neutron visibility will be confirmed through observation of reactivity*
Required operable if any clutch power supply is energized.
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.
Automatically bypassed helew 1&sect;% power.                                                       .
Instrumentation operability will also be verified by comparison among the three operable channels to ensure their individual responses are in agreement.
I 3-78 Amendment No. JJ~, J~~ * .()"~
3-81 --
February 19, 1991
Amendment No. JiJ, *febnJary 15, 1991 0
 
No 8. 9. 10. 11. 12. 13. 14. 15. 16. 17. 18. e Table 3.17.4 (Cont'd) ' Minimum Minimum Permissible Operable Degree of Bypass Functional Unit Channels Conditions Pressurizer Wide 2 (m, p, q) None Not required in Range Water Level Cold or Refueling Indication Shutdown Pressurizer Code 1 per None Not Required Safety Relief Valves Valve below 325&deg;F. Position Indication (Acoustic Moriitor or Temperature Indication) l"r'\ c.o \J s.h.l.l. +J.t,C,()  
e                                  e Table j,.17.2 Instrumentation Operat1.cg Requirements for
.. o r Power perated Relief 1 per None Not required/\when Valve (Acoustic Valve PORV isolation Monitor or Temperature valve is closed Indication) and its indication system is operable PORV Isolation Valves 1 per None Not required when Position Indication Valve reactor is depressurized and vented through a vent sq.in. Subcooling Margin 1 None Not required Monitor below 325&deg;F Auxiliary Feed Flow 1 per None Not required Rate Indication fl ow<h> below 325&deg;F Control Valve Auxiliary Feedwater 2 per 1 Not.required steam below 325&deg;F Actuation System Sensor Channels generator<*>
                            ?ng1neered Satety P'ea-eure Systems M1n1mmn        M1n1mnm            Permissible Operable                              B)'pasa ifo      ~ional      Unit        Cbazmel.a                          Conditiot:.s 1     S&tetL.!!!J. ect ion
Auxiliary Feedwater 2(f) Actuation System Actuation Channels Excore Detector 1 (g) Deviation Alarms
: 11. Manual (Tr! p                l              1fcne                Bone
* Axial Shape Index 2(1) Alarm Reactor Vessel 2 (J. k, 1,m) Water Level 1 None 1 None 3-Sla Not required below 325&deg;F Not Required Below 25% of Rated Power Not Required Below 25% of Rated Pow.er Not Required Below 325&deg;F Amendment No.,7, ''' JJ,,
        ~ttona)
it% September 15,}}
: b. High Containment            2 (a,c) l t-Jeire_Tes~
Jllr1ng :t.a-Pressure I!.   ?ressurizer Low
                                      ,'
2 *CI          l          ~        Pressure Pressure                                                Less  ~      1700 Psia(b 2      Contaimnent Soraz a.. Manual                       2              lone                ?lone
: b.     High Contaimnent            2 (a,ci) l           t\l~ag ~e.!l!es:t Pressure (a) Right am len actuation circuits each bave 2 cbam:l.ela *.
(b) . Auto removal ot b7P&as abow lTOO paia.
( c) One ot the im>perable chazmels must be in the tripped condition*.
                                                                                      ~~'\\\\~\.\.t\\
3-79 Amen&"'"' t     N0  t~~'{
 
Taole 3.11.3 Inst~      Ot:Jerating Conditions tor Isolation ?unctions M1njmnm       M1n1*1
* Penliaaible Oi>erable     Degree o't           !ype.ae Ne     ?uncticnal Unit         Chazmela     ~SI                Conditions l     Containment Isolation (a,c)                           Ncne_
: a. Containment High           2                  l     ~a&    Lea& Teat.
Pressure
: b. Coatailmlent High         2(c)               l               lone Badiation
: c.     .~                        l               lloae               !one 2     Steam Line Isolation
: a. U,v Steam Gen           2/Steam(c)           *l     Below 550 Psia (b)
Pressure               Gen
: b. Manual                 l/Stesm           lone               Bone Gen (a) Right and left actuation circuits each ban 2 clmmela.
(b)* Bypass automat1c:aJ.l7 reinstated above 550 paia.
(c) One or the inoperable channels must be in tm tripped poeition.
3-8o
 
    .,                                 Table 3.17.4 Instrumentation Operating Requirements for Other Safety Feature Functions Minimum Minimum          Permissible Operable Degree- of     Bypass Functional Unit          Channels Redundancy     Conditions
                                                        !\lo~ re<tiu~d be.low 3Z.5 "!=
SIRWT Low-Level          4        NA<b>          One channel may be Switches                                          inoperable for a period of 7 days<b>
2      dT - Power                        1              ~          r-6 o-C c-qu.u*~.c(  ct.,t or Comparator                                        \,e.low       \.tot >~"'- -f:dc"'"
1 3     (Deleted) 4     Air Cooler Service       1         None          NGnQ N.t1t. r-eiu.1r-~
Water Flow Instruments                           \oe.\., i...> ?. 2-S *r:
5      Primary and Secondary   1         None          *A Neit r~tU.lf"Gd .::t.c                or Rod Insertion and_                                be.lo...., 1-iet Sh.u. H . .oco.-,
Out-of-Sequence Monitors 6      Fuel Pool Building      1        None          As Requested Under Crane Interlocks                                  Admi*ni strati ve Controls<*>
7      Source-Range            2                        Not Required Above Channels                                          10-4% of Rated Power (!;)r w 1+-h "o +=~e.. I 11'\  th e.. ,.. ~ "-'--+o ,.
(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) if shutdown neutron power levels indicated on the wide range channels                       ~
are greater than three times the lowest decade in which neutron visibility can be confiniled~ 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 comparison among the three operable channels to ensure their individual responses are in agreement.
3-81
                                                                              -         -     i~~~~&#xa2;/~~JI~
Amendment No. JiJ, Ji~. t~t
                                                                                    *febnJary 15, 1991
 
e 0
No 8.
    "'**:t,~
Functional Unit Pressurizer Wide Table 3.17.4 (Cont'd)
Minimum Minimum Operable Degree of Channels Redundanc~
2 (m, p, q) None
                                                                      '
Permissible Bypass Conditions 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&deg;F.
Position Indication (Acoustic Moriitor or Temperature Indication)
                    ~Pos1-lton J:ndt<<0:lto~                              l"r'\ c.o \J s.h.l.l.+J.t,C,() .. o r
: 10.        Power perated Relief 1 per             None         Not required/\when Valve (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 ~1.3 sq.in.
: 12.        Subcooling Margin         1           None         Not required Monitor                                               below 325&deg;F
: 13.        Auxiliary Feed Flow       1 per       None         Not required Rate Indication           fl ow<h>                   below 325&deg;F Control Valve
: 14.        Auxiliary Feedwater       2 per       1             Not.required Actuation System          steam                     below 325&deg;F Sensor Channels           generator<*>
: 15.        Auxiliary Feedwater       2(f)         1            Not required Actuation System                                     below 325&deg;F Actuation Channels
: 16.        Excore Detector           1(g)         None          Not Required Deviation Alarms                                     Below 25% of
                        * ~o..
Rated Power
: 17.        Axial Shape Index         2(1) 1            Not Required Alarm                                                 Below 25% of Rated Pow.er
: 18.        Reactor Vessel             2(J. k, 1,m) None          Not Required Water Level                                           Below 325&deg;F 3-Sla Amendment No.,7, ''' ~-' JJ,, JJ~, it%
September 15, 198~}}

Revision as of 19:33, 21 October 2019

Corrected Tech Specs Re Instrumentation & Control Sys
ML18057A817
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Site: Palisades Entergy icon.png
Issue date: 03/18/1991
From:
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To:
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Text

ATTACHMENT I Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST INSTRUMENT &CONTROL SYSTEMS PROPOSED TECHNICAL SPECIFICATIONS PAGES March 18, 1991 8 Pages

' ,....1031:3 ~ \ \

<i11ri325033~ ~

P.DR- ADOCK b~00025-

- PDR p

. 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 i.nstrumentation and control systems necessary to assure reactor safety.

Specifications

3. 17. 1 Deleted 3.17.2 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be placed in ~cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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 continuing operation with certain instrumentation channels out of service since provisions were made for this in the plant design. This specification outlines limiting cohditions 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 Bol'.'on 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 assumptions and shutdown margin requirements will be met.

When the reactor power 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 Lo~s 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.

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 -0ut 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),' 11 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.

3-76a Amendment No. 1J~,

TSPR9102

e*

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 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-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 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 i$

limited.

The Zero Power* Mode Bypass can be used to bypass the 1ow fl ow, steam generator l~w 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 w_hen in the bypass condition provides additional assurance that an accidental criticality will not occur. Tp allow low power physics testing at reduced temperature and pressure, the requirement for cold shutdown borori concentration-is not required and the1 allowed power is increased to * .

10- %. .

References

( 1) Updated FSAR, *Section 7. 2. 7.

(2) Updated FSAR, Section 7.2.5.2 3-77 Amendment No. JJ~, J~~,J~~.

TSPR9102

e Table 3.17.l

  • Instrumentation Ogerating Reguirements for Reactor Protective System Minimum Minimum Permissible O~erable Degree of Bypass No. Functional Unit C annels Redundancy Conditions
1. Manual 1 None None (Trip Buttons)
2. Variable High 2(b,d) 1(d) None Power Level
3. Wide Range 2 1 Below 10- 43<e> or Above 133 of Channels Rated Power<a> except as noted in ( c)
4. Thermal Margin/ ' 2(b,f) 1 Bel ow 10- 43 Cel of Rated Power<a>

Low-Pressurizer and greater than cold shutdown Pressure boron contentration

5. High-Pressurizer 2(b) 1 None Pressure
6. Low Flow Loop 2(b) 1 Bel ow 10- 43<e> of Rated Power<*>

and greater than cold' shutdown boron concentration.

7. Loss of Load 1 None Selow 173 of Rated Power<a>
8.
  • Low Steam 2/Steam I/Steam None Generator Gen Generator Water Level
9. Low Steam 2/Steam I/Steam Bel ow io- 43<e> of Rated Power<al Generator Gen Generator and greater than cold shutdown Pressure boron concentration.
10. High Containment 2(b) 1 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 703 or less of rated power.

(e) For low power physics testing, io-*3 may be increased to io- 13 and cold shutdown boron concentration is not required.

( f) Axial Offset operability requirements are given in Specification 3.11.2.

3-78 Amendment No. 11~, 1~~' l~~.

TSPR9102

Table 3.17.2

  • Instrumentation Ogerating Reguirements for Engineerea Safety Feature Systems Minimum Minimum Permissible O~erable Degree of Bypass No Funct i ona 1 Un it C annels Redundancy 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 Psi a Cb>
2. Containment Sgray
a. Manua 1 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 c~ndition.

3-79 Amendment No.

TSPR9102

Table 3.17.3

  • *
  • Instrument Operating Conditions for Isolation Functions Minimum Minimum Permissible O~erable De~ree 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. Manual 1 None, None 2 Steam Line Isolation
a. Low Steam Gen 2/Steam<c> 1 Below 550 psia

Pressure Gen

b. Manual I/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 O~erable Degree of Bypass No Functional Unit

  • C annel s Redundancy Conditions 1 SIRWT Low-Level 4 NA Not required below 325°F. One Switches channel may be inoperable for a period of 7 days Cb>

2 !T - Power 3Cc) 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 l* None As Requested Under Crane Interlocks Administrative Control s<a>

7 Start-Up Channels 2 1(d) Not Re$uired Above.

10-43 o Rated Power or with no fuel in the reactor. I*

(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.

<<=> If only two channels are operable, load shall be reduced to 70% or less of rated power.

(d} Minimum operable channels shall be one fl} 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 comparison among the three operable channels to ensure their individual

  • responses are. in agreement.

3-81 Amendment No.

~~~~~¢/~~;

JiJ, Ji~.

n J~~.

TSPR9102

Table 3.17.4 (Cont'd)

Minimum Minimum Permissible O~erable De~ree of Bypass No Functional Unit C 2 annels Re undanc~

(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 fAcoustic Monitor or emperature Indication)
10. Power O~erated Relief 1 per None Not required in cold shutdown Valves osition Indication or when PORV isolation f Acoustic Monitor or . valve is closed emperature Indication) and. its indication system is operable
11. PORV Is~lation Valves 1 ver None Not required when Position Indication Va ve reactor is depressurized *and vented through a vent ~L3 sq. in.

J

12. Subcooling Margin 1 None. Not required Monitor below 325°F
13. Auxiliary Feed Flow 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) l 'Not required Actuation S~stem below 325°F Actuation C annels
16. Excore Detector . 1(g) None Not Required Deviation Alarms Below 25% of Rated Power
17. Axial Shape In.sJex 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~, J~~.

TSPR9102

ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST INSTRUMENT & CONTROL SYSTEMS MARKED UP EXISTING TECHNICAL SPECIFICATIONS PAGES March 18, 1991 7 Pages

~. :.:1 .,,............

  • ~4 ..._. .._ ..

~~*

1 -***- -

.:J>tSEfll-~ App~ids Go plaa~ iastl"'Wleatatiea systems.

A ObJective To delineate the conditions ot the plant instrumentation and co?ltrol syst~ necessary to assure reactor safety.

Seeciticat ions

.i;.~ ~e'~~~aeilhy et ~he ple'e iast~e~ ~d. eeatFGl systems she??

~e ia aeeerc!.a!!ee 'iri'h iablea 3.17.1 ~hre~ 3,17.~.

3 .l T.2 In the event the number ot channels ot a particular system. in service falls belov the limits given 1:1 the columns entitled "Minimum Operable Cb&zu:lel.s" or "Minimum Degree ot Redundancy,"

except as concil.tioned by the column entitled. "Permissible ay,ass Co::.diticns!" tte reactor sball be ;>laced. in a hot shuttioYU coaditioil within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. It mini:aum. concil.tions are not met withln 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be placed in a cold shutdoYU concil.tion within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Basis During plant operations, the complete iostru:nentation systems will nor:ia.l.ly be in service. Reactor safety is provided by the reactor protection system, vbich automatic&lly initiates appropriate action

~c ~reve~t exceec.ing established limits. Sa!ety is not cc:::pro::dsed, however, by continuing operation with certain Uistrui:e~tation

~hannel..s cut ~t servi:e *s!nce ~roVisioos were 111ade tor tllis in the pl&.llt design. This speciticatioa ou~lines limiti!lg cooditio~s for o;eration necessar.r to preserve the eftectiveoess ot the reactor control 8..lld ~rotection system *J'h!!~ g,ny '.:::.e ~r :ore ot ";lle .:::..a.n.:iels

_ s~f are out ot service.

~ f>~Al.most all reactor protection 8..lld ecgiaeered sa!egu.a.rds channels

  • ~ -"'*

u-e 9upp.lied vitti sut!'icient redun~c:r ':o ;ronde the capability for chiim<<l t*est at pover. Exceptions are backup cb.a.anels such as loss-ot-ld.ad trip.

W'ben one ot the tour channels is taken out ot service tor maintenance,

  • the protective system logic can be changed to a two-out-o.t-three coincidence tor a reactor trip by bypassing the* removed channel.

U"';~. t""~-*

--*-.;

I  ; i j' .! () I')

1*

'>vv 3-76

A 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 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 53 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 assumptions and shutdown margin requirements will be met.

When the reactor power 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 153 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 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), 111 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-~ange channel is available and the neutron power level is sufficiently high that it is being monitored by both channels of wide-range instrum~ntation, 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 th.e 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 mainta:t-n:o: cold shutdown boron concentration when in the bypass condition provtd&sk,add1tional assurance that an accidental criticality will not occur~-~~--l<t' 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 10- 1%.

  • References (1) Updated FSAR, Section 7.2.J.

(2) Updated FSAR, Section 7.2.5.2.

h* * "., :' ** -~ **

3-JZ-Amendment N~. J-J~, n-, 136 February 15, 1991

Table 3.17.1 Instrumentation Operating Requirements for Reactor Protective System Minimum Minimum Permissible Operable Degree of Bypass Functional Unit Channels Redundancy Conditions

'1. Manual (Trip 1 None None Buttons}~

2. Variable Hig~ None Power Level r
3. Wide Rang~ 2 1 Be 1ow 1o-4% <*> or Above Channels~ I '3 1-5'% Rated Power <*> Except as Noted in Cc>
4. Thermal Margin/ 1 Be 1ow 1o-4% <*> of Rated Low-Press~izer Power<*> and greater than Pressure /V cold shutdown boron concentration
5. High-Pressurizer 1 None Pressure }1lf
6. Low Flow Loop ')'If I Be 1ow 10-4% <*> of Rated Power<*> and greater than cold shutdown boron concentration.
7. Loss of Load W I None N-efl.e. Belew 17 ~ RQ.t~ PoU)e.r (a.)
8. Low Steam Gen- 2/Steam
  • I/Steam None era tor Water Gen Generator Level ~
9. Low Steam Gen- 2/Steam I/Steam* Bel ow 10-4% <*> of er ator Pressure Gen Generator Rated Power<*> and greater

)111 than cold shutdown boron con-centration.

10. High Containment I None Pressure~

(a} Bypass aut~ti'cal ly removed.

(b) One of tlie**_:hioperable channels must be in the tripped condition.

(c) Two channels required if TM/LP, low steam generatorifor low-flow channels are

_bypasse.d. _ - . prti.:.1.1.rt.

(d) *1f only two channels are operable, load shall be reduced to 70% or less of rated power.

(e) For low power physics testing, 10-4% may be increased' to 10- 1% and.cold shutdown boron concentration is not required.

( f)

~)

(A)

Axial Offset operability requirements are given in Specification 3.Il.2.

Required operable if any clutch power supply is energized.

Automatically bypassed helew 1§% power. .

I 3-78 Amendment No. JJ~, J~~ * .()"~

February 19, 1991

e e Table j,.17.2 Instrumentation Operat1.cg Requirements for

?ng1neered Satety P'ea-eure Systems M1n1mmn M1n1mnm Permissible Operable B)'pasa ifo ~ional Unit Cbazmel.a Conditiot:.s 1 S&tetL.!!!J. ect ion

11. Manual (Tr! p l 1fcne Bone

~ttona)

b. High Containment 2 (a,c) l t-Jeire_Tes~

Jllr1ng :t.a-Pressure I!. ?ressurizer Low

,'

2 *CI l ~ Pressure Pressure Less ~ 1700 Psia(b 2 Contaimnent Soraz a.. Manual 2 lone ?lone

b. High Contaimnent 2 (a,ci) l t\l~ag ~e.!l!es:t Pressure (a) Right am len actuation circuits each bave 2 cbam:l.ela *.

(b) . Auto removal ot b7P&as abow lTOO paia.

( c) One ot the im>perable chazmels must be in the tripped condition*.

~~'\\\\~\.\.t\\

3-79 Amen&"'"' t N0 t~~'{

Taole 3.11.3 Inst~ Ot:Jerating Conditions tor Isolation ?unctions M1njmnm M1n1*1

  • Penliaaible Oi>erable Degree o't !ype.ae Ne ?uncticnal Unit Chazmela ~SI Conditions l Containment Isolation (a,c) Ncne_
a. Containment High 2 l ~a& Lea& Teat.

Pressure

b. Coatailmlent High 2(c) l lone Badiation
c. .~ l lloae !one 2 Steam Line Isolation
a. U,v Steam Gen 2/Steam(c) *l Below 550 Psia (b)

Pressure Gen

b. Manual l/Stesm lone Bone Gen (a) Right and left actuation circuits each ban 2 clmmela.

(b)* Bypass automat1c:aJ.l7 reinstated above 550 paia.

(c) One or the inoperable channels must be in tm tripped poeition.

3-8o

., Table 3.17.4 Instrumentation Operating Requirements for Other Safety Feature Functions Minimum Minimum Permissible Operable Degree- of Bypass Functional Unit Channels Redundancy Conditions

!\lo~ re<tiu~d be.low 3Z.5 "!=

SIRWT Low-Level 4 NA One channel may be Switches inoperable for a period of 7 days

2 dT - Power 1 ~ r-6 o-C c-qu.u*~.c( ct.,t or Comparator \,e.low \.tot >~"'- -f:dc"'"

1 3 (Deleted) 4 Air Cooler Service 1 None NGnQ N.t1t. r-eiu.1r-~

Water Flow Instruments \oe.\., i...> ?. 2-S *r:

5 Primary and Secondary 1 None *A Neit r~tU.lf"Gd .::t.c or Rod Insertion and_ be.lo...., 1-iet Sh.u. H . .oco.-,

Out-of-Sequence Monitors 6 Fuel Pool Building 1 None As Requested Under Crane Interlocks Admi*ni strati ve Controls<*>

7 Source-Range 2 Not Required Above Channels 10-4% of Rated Power (!;)r w 1+-h "o +=~e.. I 11'\ th e.. ,.. ~ "-'--+o ,.

(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) if shutdown neutron power levels indicated on the wide range channels ~

are greater than three times the lowest decade in which neutron visibility can be confiniled~ 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 comparison among the three operable channels to ensure their individual responses are in agreement.

3-81

- - i~~~~¢/~~JI~

Amendment No. JiJ, Ji~. t~t

  • febnJary 15, 1991

e 0

No 8.

"'**:t,~

Functional Unit Pressurizer Wide Table 3.17.4 (Cont'd)

Minimum Minimum Operable Degree of Channels Redundanc~

2 (m, p, q) None

'

Permissible Bypass Conditions 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 Moriitor or Temperature Indication)

~Pos1-lton J:ndt<<0:lto~ l"r'\ c.o \J s.h.l.l.+J.t,C,() .. o r

10. Power perated Relief 1 per None Not required/\when Valve (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 ~1.3 sq.in.
12. Subcooling Margin 1 None Not required Monitor below 325°F
13. Auxiliary Feed Flow 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 System below 325°F Actuation Channels
16. Excore Detector 1(g) None Not Required Deviation Alarms Below 25% of
  • ~o..

Rated Power

17. Axial Shape Index 2(1) 1 Not Required Alarm Below 25% of Rated Pow.er
18. Reactor Vessel 2(J. k, 1,m) None Not Required Water Level Below 325°F 3-Sla Amendment No.,7, ~-' JJ,, JJ~, it%

September 15, 198~

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