ML20154L904
| ML20154L904 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 10/09/1998 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20154L871 | List: |
| References | |
| NUDOCS 9810200110 | |
| Download: ML20154L904 (30) | |
Text
{{#Wiki_filter:____ _ _ . _ _ _ _ _ _ _ _ _ _ . . _ .. ___ Exhibit B Technical Specification Pages Marked Up With Proposed Changes Monticello Nuclear Generating Plant Supplement 1 to License Amendment Request Dated July 5,1995 Exhibit B consists of existing Technical Specification pages marked up with the proposed changes. The pages included in this exhibit are as listed below: Pages 30 32 33 34* 42 50* 51 52* 53* 54* 55 59* Addendum to page 59 which creates new page 59a. 60d* 61* 62'
- Contains Supplement 1 changes. Note: Supplement 1 deleted change to page 34, therefore, it is not included in Exhibit C.
Page B-1 9810200110 981009 PDR ADOCK 05000263 ' P PDR , l
Exhibit C Revised Technical Specification Pages
' Monticelh Nuclear Generating Plant Supplement 1 to License Amendment Request Dated July 5,1995 l
Exhibit C consists of revised Technical Specification pages that incorporate the proposed changes. The pages included in this exhibit are as listed below: ! Pages ; 30 32 33 42 50
- 51 52 i 53 i 54 55 59
)
59a 60d 61 62 i l 1 1 I I 1 I I Page C-1 _i_-_., -.%
d 2 m m - - - 4 e -U r .-m.~-A .AK- + - 4J-ad s -- -4 maw *-A @ - Exhibit B Technical Specification Pages Marked Up With Proposed Changes
- Monticello Nuclear Generating Plant Supplement 1 to License Amendment Request Dated July 5,1995 Exhibit B consists of existing Technical Specification pages marked up with the proposed changes. The pages included in this exhibit are as listed below:
Pages
-30 32 33 34*
42 50* 51
.52*
53* 54* 55 59' Addendum to page 59 which creates new page 59a. 60d* 61* ' 62*
- Contains Supplement 1 changes. Note: Supplement 1 deleted change to page 34, therefore, l~ it is not included in Exhibit C .
l l Page B-1 i
f Table 3.1.1 - Continued
- 6. Deleted.
- 7. Trips upon loss of oil pressure to the acceleration relay.
- 8. Limited trip setting refers to the volume of water in the discharge volume receiver tank and does not include the volume in the lines to the level switches.
- 9. High reactor pressure is not required to be operable when the reactor vessel head is unbolted. !
Reauired Conditions when minimum conditions for ooeration are not satisfied.(f tk e lh.\ .5 ) A. All operable control rods fully inserte ,=4c'i_ 0 ...... $5 B. Power on IRM range or below and reactor in Ntartup, Refuel, or Shutdown mode. 8 ' Sej C. Reactor in Startup or Refuel mode and pressure below 600 psig. D. Reactor power less than 45% (798.75 MWt.).
** Allowable Evoass Conditions It is permissible to bypass:
a. The scram discharge volume High Water Level scram function in the refuel mode to allow reactor protection system reset. A rod block shall be appliad while the bypass is in effect. b. The Low 600 is below Condenser psig. vacuum and MSIV closure scram function in the Refuel and Startup modes if reactor pressure i t
- c. Deleted.
d. The turbine stop valve closure and fast control valve closure scram functions when the reactor thermal power is s 45% (798.75 MWt). 3.1/4.1 30 Amendment No. 63, 83, 102 Uk MO __ _ - _ _ _ ____m_ -_ _ _ _ _ - ______-____-____-___m, _ _
TABLE 4.1.1 SCRAM INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREOUENCIES FOR SAFETY INSTRITiiENTATION AND CONT INSTRUMENTATION CHANNEL FUNCTIONAL TEST MINIMUM FREOUENCY (4) High Reactor Pressure Trip Channel and Alarm Quarterly High Drywell Pressure Trip Channel and Alarm Quarterly Low Reactor Water Level (2, 5) Trip Channel and Alarm Quarterly High Water Level in Scram Discharge Volume Trip Channel and Alarm Quarterly i Condenser Low Vac Trip Channel and Alarm Once each month ; Main Steam Line Isolation Valve Trip Channel and Alarm Closure Quarterly Turbine Stop Valve Closure Trip Channel and Alarm Quarterly g, Manual Scram Trip Channel and Alarm Weekly . Turbine Control Valve Fast Closure ' Trip Channel and Alarm Quarterly- ' APRM/ Flow Reference (5) Trip Output Relays Quarterly IRM (S) Trip Channel and Alarm Nara 1 Mode Switch in Shutdown Place mode switch in shutdown
-End r:{2: ling :::cg;v efj O i
3.1/4.1 32 n:" 123 0/10/n / _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ - _ _ - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- ~
L.
. b TABLE 4.1.1 (Continued) g6 \#6
-Note 1: Deleted.
Note 2: A sensor check'shall b performed on low re h unt := ;n cr.;; i:2 ;..lfc water level once per da ~ r' '.igh Note 3: channels overlap at least 1/2 decade prior to every normal shutdown. test prior te.every startup, a Note 4: Functional are tripped.tests are not required when the systems are not required to.be operable or systems to an operable If tests are missed, they shall be performed prior to status. returning the Note 5: A functional test of this instrument means the injection of a simulated signal into the instrument and/or initicting (not primary action. sensor) to verify the. proper instrument channel response, alarm , 3.1/4.1 33
. ""I is: 3/13/s2 7
. ___ ________ _____________ _ .- _ _ _ _ - _ _ _ - _ _ . _ _ _ _ m __ _ _ _ _ _ _ _ _ - _ _ _ - _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ - _ _ _ _ _ _ _ _ . _ - _ _ _ _ _ _ _ _ - _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _
TABLE 4.1.2 SCRAM INSTRUMENT CALIBRATION MINIMUM CALIBRATION FREOUENCES FOR REACTOR PROTECTION INSTRUMENT CHANNELS INSTRUMENT CHANNEL CROUP CALIBRATION METHOD MINIMUM FREOUENCY (2) APRM B Heat Balance once every 3 days (4) IRM High Reactor Pressure B Heat Balance See Note 1 A Pressure Standard Every 3 months High Drywell Pressure A Low Reactor Vater Pressure Standard Every 3 m~onths B Pressure Standard Every Operating Cycle -
- Transmitter High Water Level in Scram Discharge Every 3 months - Trip Unit A or B Water Level Every 3 month.;
Condenser Low Vacuum - A Vacuum Standard Every 3 months Main Steamline Isolation Valve Closure A Observation Every Operating Cycle l Turbine Control Valve Fast Closure A Pressure Standard Every 3 hs Turbine Stop Valve Closure A Observation Recirculation Flow Meters & . Eve erat g Cycle Pressure Standard Ev _ xx. ..: - Flow Instrumentation tN cle. 6 bo noT W M * *Se C bf 6j . O ened]f( 1. h p \ e. - c 1. Perform calibration test during every startup and normal shutdown. 2. Calibration tests are not required when the systems are not required to be operable or are tripped.
- 3. If tests are missed, they shall be performed prior to returning the systems to an operable status.
(Deleted). . 4 , l This calibration is performed by taking a heat balance and adjusting the APRM to agree I ith the heat balance. Alarms and trips will be verified and calibrated if necessary during fu j te . m
- 6. M Sen(or c. heck 3 d\ bc OUPA . vnd oMM .A recirtsd<r\on A Neu3 s gnals once perday, A. Passive type devices.
B. i Vacuum tube or semiconductor devices and detectors that drift or lose sensitivity. t 3.1/4.1 34 L arl 133 0/10/32 i
~
. _ ~ $,)
S d.*
~
~Bsses:
4.1 The' instrumentation in this section will be functionally tested and' calibrated'at regularly d sche'uled intervals. - Specific ~ surveillance intervals and' surveillance and maintenance' outage times have been determined in accordance'with NEDC-30851P, " Technical: Specification Improvement Analysis = for BWR Reactor Protection System," as approved.by the NRC and documented'in the SER dated July 15,1987. (letter to T A Pickens. from A Thadani). Calibration frequency of the. instrument' channel is divided into two groups =as defined on~ Table ~ 4.1.2. Experience'with passive type' instruments indicates that a yearly. calibration;is adequate.. Wh eg E possible,'however, quarterly calibration is performed. For those devices which employ amplif etc., drift specifications' call for drift to be less than 0.St/ month;-i.e., in the' period
.of a month a drift of 0.5% would occur.and thus provide for adequate margin. For'the APRM system:
drift of electronic apparatus is not the only consideration in determining a-' calibration frequency. Change in power distribution and loss of chamber sensitivity dictate a calibration every three days. [ Calibration on this frequency assures plant operation at or below thermal limits. l 4 4 4 4 I 4.1 BASES 42 i- NEXT PACE IS 45 .r; 131 '
/10/02 4
- - _ - _ _ - _ _ m __ . . _ = -
_ _ __ . s_._ _.
/ Lius a}Al - LeewaJ TABLE.3.2.1-(Continued _
M of Operabi
/
V or Operating Instru-Total No. of Instr ment Channels Per Thin.No. ment Channels Per Trip Required Function Trio Settines Trio System System (1.2) Conditions f
- b. Hi h Drywell Pressure s2 psig 2 2 D (5
- 3. Reactor Cleanup System t (Croup 3)
- a. Low Reactor Water 27"(annulus) 2 2 E Level
- b. High Drywell Press'ure s2 psig 2 2 E
- 4. HPCI Steam Lin 6.dro9
.- J j\
t
- a. HPCI High Steam Flow s150,000 lb/hr 2(4) 2 F with s60 second .
j g h, time delay
- b. HPCI High Steak Flow s300,000 lb/hr 2(4) f 2 F HPCI Steam Line s200* F 16(4) 16 F
- c. f i Area High Te
- 5. RCICSteamLinesYprpp
- a. RCIC High Steam ow 545,000 lb/hr 2(4) 2 C with 5 2 see time delay ;
- b. RCIC Steam Line Area s200* F 16(4) 16 C 6.. Shutdowri Cooling Supolv Isolation ,
- a. Reactor Pressure 575 psig 2(4) 2 C Interlock at the reactor
' 50 ;
3.2/4.2 i Amendment 22, 27, 102 ;
[a. S h te1 C b wwed $S conMited one. chnned Table 3.2.1 - Continued (1) "oc Cceup_ 1, 2 aad 2 ere shall be two operable or tripped trip systems for each function. A channel may be p aced lu au status for up to 6 hours for required surveillance without placing the trip system in the tripped condition provided that at least one other operable channel in the same trip system is monitoring that parameter. Fer Cr g e ':, 5 nd Ren'ter Preocure Interlech: ther 2h:11 he tre : perch!: ertripp:dtripk f Enc ti_. . _ _ on discovery that minimum requirements for the number of operable or operating trip (2) For C_ rap; 1. 2 q_nd 3, '
, stems or inscrument channels are not satisfied action shall be initiated as follows:
(.) Vith one required instrument channel inoperable in one or more trip functions, place the inoperable l channel (s) or trip system in the tripped condition within 12 hours, or (b) Uith more than one instrument channel inoperable for one or more trip functions, immediately satisfy the requirements by placing appropriate channels or systems in the tripped condition, or (c) Place the plant under the specified required conditions using normal operating procedures. For Cro s 4, 5 and Reac r Pre ure Int loc s on dis very at m mum r uire nts f. the ber f ope li or op ating ip sysc s or strument channel are n sati ied a ion s be niti ed to: quiree nts by acing a propri e cha els o system in t tri ed cor itio (a Sat sfy the ace th plant der the pecifie requi ed con tions sing rmal erati g proc dures
)
(3) Low pressure in main steam line only need to be available in the RUN position. (4) All instrument channels are shared by both trip systems. (5) May be bypassed when necessary only by closin6 the manual containment iselation valves during purging for containment inerting or de-inerting. Verification of the bypass condition shall be noted in the control room log. Also, need not be operable when primary containment integrity is not required.
- Required conditions when minimum conditions for operation are not satisfied.
A. Group 1 isolation valves closed. B. Reactor Power on IRM range or below and reactor in startup, refuel, or shutdown mode. C. Isolation Valves closed for: Shutdown Cooling System, and Reactor llead Cooling Line. D. Comply with Condition C. above. E. Isolation Valves closed for: Reactor Cleanup System. F. IIPCI steam line isolated. (See specification 3.5 for additional requirements.) C. RCIC steam line isolated. 51 3.2/4.2 :n : t.c nl+/% /
t'.o
\ j Table 3.2.2 Core Cooling. System Instrumentation That Initiates Emergen .
i Minimum N of Oper-f- able or Ope ating Minimum No. of Instrument C. annels ,. Operable or Total No. of Instru- Per Trip Sy 9 Required Operating (. ment Channels Per (6 3) Conditions
- Systems (3R,6 Trio System Trio Setting V I Function l j)
A. Core Sorav and LPCI t
- 1. Pump Start 4 A.
2 4(4)
- a. Low Low Reac r 26'6"s6'10" '
Water Level i and j 2 A. l 2450 psig 2 2(4)
- b. 1. Reactor Pressure .
1 Permissive 1 B. t or 2 1
- 11. Reactor Low 2011 min Pressure Permissive i Bypass Timer s 4 A.
52 psig 2 4(4)
- c. High Drywell Pressure (1) 2 A.
z 50 psig 2 2(4) -
- 2. Low Reactor Pressure i (Valve Permissive) l 2 A.
-- 2 2(2)
- 3. Loss of Auxiliary Power fj f / - -
%um\'/61- hepw e 1 52 i 3.2/4.2 Amendment No. $7. 93
CWe hk Table 3.2.2 Instrumentation That Initiates Emergene ore Cooling Systems
~
1 Minimum No. of Oper-Hinimum No. of able or Operating
~
Operable or Total No. of Instru- Instrument channels Operating p ment Channels Per Per. Trip System Required l
' Systems (3 L> Trio System -(3 Conditions
- Function Trio Settinz _
B. HPCI System 4 4 A. l
- 1. Iligh Drywell s2 psig 1 '
Pressure (1) ! 4 4 A.
- 2. Iow-Low Reactor 26'6"s6'10" 1 Water Level C. Automatic Depres-surization 2 2 { 2 B.
- 1. Low-Low Reactor 16'6"s6'10" '
Water Level and 1 B. s120 seconds 2 1
- 2. Auto Blowdown Timer ; ,
and B. i
- 3. Low Pressure Core 260 psig 2 12(4) 12(4)
Cooling Pumps Dis- s150 psig i Charge Pressure Interlock iN YL '
% [
l[ f MCW d- M W 53 3.2/4.2 Amendment No. 62, 93, 102
h G# g% y e.: .N - Table 3.2.2-fContinued
-{
Instrumentation That Initiates Emerrency - ore Cooline System { 1 ;
~
t Min. No. of Oper- \ Min. No. able or Operating } } of Operable tal No. of Instru- Instrument Channe , or Operating ent Channels Per Per Trip System Required i Function )[ Trio Setting Trio Systems ( L rio System ( )[Otonditions* ;
?
D. Diesel Generator k ' % Degraded or Loss v
- 1. F " V of Voltage Essential ,
Bus (5)
- ;t6 ' 6 "s6 ' 10" 2 4(4) 4- C. :
- 2. ' Low Low Reactor Water Level 2 4(4) 4 C.
- 3. High Drywell Press 52 psig ,
I
~
l I .
}
7 . NOTES:
- 1. High drywell pressure may be bypassed when necessary only by closing the manual containment isolation valves during purging for containment inerting or de-inerting. Verification of the bypass condition shall be noted in the control room log. Also need not be operable when primary containment integrity is not required. ;
- 2. One instrument channel is a circuit breaker contact and the other is an undervoltage relay. l e
r l a i 54 l 3.2/4.2 l Amendment No. 3,93 [
.f & A. _ l
- a. With one required instrument channel inoperable per trip function, place the 'N rnoperable channel or trip system in the tripped condition within 12 hours or 3
- b. With more than one instrument channel per trip system inoperable, immediately O
Table 3.2.2 - Continued Notes:
- 3. Upon discovery that minimum requirements for the number of operable or operating trip systems, or instrument channels are not satisfied action shall be initiated re+ as .Qoi\ p s,; ,
La3 Sgatisfy the requirements by' placing appropriate channels or systems in the tripped condition, or . C,,h Place the plant under the specified required conditions using normal operating procedures.
- 4. All instrument channels are shared by both trip systems.
- 5. See table 3.2.6.
Required conditions when minimum conditions for operation are not satisfied. i A. Comply with Specification 3.5.A. B. Reactor pressure $150 psig. C. Comply with Specification 3.9.B. v N ,
- 6. A channel (a shared channel is considered one channel) may be placed in an inoperable status for up to 6 hours for required survei!!ance without placing
- the trip sys+em in the tripped condition provided that at least one other operable channel in the same trip system is monitoring that parameter.
}
.l A A #'
55 3.2/4.2 Amendment No. 3,93
g M,hb - phhvCT 1-ig 4
~ _
C Table 3.2.4 Instrumentation That Initiates Reactor Building Ventilation Isolation-- # hJ' And Standby Gas Treatment System Initiation
- Min. No..of Operable..
Total No. of Instru-- or Operating Instrument ment Channels Per Trip Channels Per Trip Required System System (Nuin 1. 21 Conditions
- Function Trio Settines l '. Low Low Reactor 26'-6", 56'-10" 2 2(McTesI,3,h A. or B.
l Water Level (Note 2)
- 2. High Drywell Pres- $2 psig 2 2(Nore.s1,3,6,4 A. or B.
sure wv uo _ , ,
- 3. Reactor Building $100 mR/hr 1 1(Not[4) A or B.
Plenum Radiation Monitors 4 Refueling Floor $100 mR/hr 1- 1(Note 3I) A. or B. Radiation Montrors Notes: (1) There shall be two operable or tripped trip systems for each function with two instrument channels per trip systet and there shall be one operable or tripped trip system for each function with one instrument channel per trip systed (2) Upon discovery that minimum requirements for the number of operable or operating trip systetas or instrument channa[ are not satisfied action shall be initiated to: (a) Satisfy the requirements by placing appropriate channels or systems in the tripped condition, or l (b) Place the plant under the specified required conditions using normal operating procedures. (3) Need not be operable when primary containment integrity is not required, aintenance and/or testing. - ! pog PDTE6 FAM b* SEE en A7fdcHEb SMEET misiimm. u.r.diti^ns'for operation are not satisfied. on A. The reactor building ventilation system isolated and the standby gas treatment system operating. B. Esrablish conditions where secondary containment is not required. 59 3.2/4.2 X: l',1 ?l?l?': 7 I 1 l
(5) Upon discovery that minimum requirement; for th9 number of operable or operating trip systems or instrument channels are not satisfici
+
action shall be initiated as follows: (a) With one required instrument channel inoperable per trip function, place the inoperable channel or trip system in the tripped condition within 12 hours, or i, (b) With more than one instrument channel per trip system inoperable, immediately satisfy the requirements by placing appropriate channels or systems in the tripped condition, or (c) Place the plant under the specified required conditions using normal operating procedures.
-(6) A channel may be placed in an inoperable status for up to 6 hours for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.
A A gr ohr oS pqe 53. gmmTw~
[Dc. h N-With one required instrument channel inoperable per trip function, place the +
)
inoperable channel or trip cystem in the tripped condition within 12 hours or O ( b. With more than one instrument channet per trip system inoperable, immediately j p
- , - n s
-Table 3.2.8 rg '.
Other Instrumentation v (, Minimum No. of Oper- W 1 Minimum No. of } equired
~"~
Operable or. Total No. of Instru- able or Operating Function . Trip Setting Operating Trip ment Channels Per Instrument Channels l System (1)( 4 Trio System Per Trio System (1) M .onditions* A. RCIC Initiation t
- 1. Low-Low Reactor Level 26'6"& $6'10" l g4 glf B -4 4
above top of active fuel j l i < B. HPCI/RCIC Turbine a Shutdown v 2 A f
- a. High Reactor Level s14'6" above 1 2 ,
top of active fuel Q , Q x 2 j m , A
'* 4 %
C. HPCI/RCIC Turbine ; f Suction Transfer ,
- a. Condensate Storage 22'0" above 1 2 2 C Tank low Level tank bottom I
l i , i NOTE:
- 1. Upon discovery that minimum requirements for the number ~of operable or operating trip systems or instrument channels are not satisfied, action shall be initiated see A c, .p.gg g. ,
O T'
. Sgatisfy the requirements by placing the appropriate channels or systems in the tripped condition 3
--- t s- 1.._,n_- w .. ___ ._.m__. _r, u,
__ a_ _ _ _ ,. s, , __ c,R Place the plant under the specified required condition using normal operating procedures. ;
- Required conditions when minimum conditions for operation are not satisfied:
A. C Renc_ m g U "Start"p, w h sg_cfuel, u m er e.wrShutde b 3.m5. u.cA_." B. Comply with Specification 3.5.D. C. Align HPCI and RCIC suction to the suppression pool. Restore channels to operable status within 30 days or i place the plant in Required Condition A. foe WPCI. 3.c B bc RC\C. 3.2 4.2
~
~- "
y % 60d
- 2. A channel may be placed in an ino,mrable status for up to 6 hours for required surveillance without placing the trip system in the tn condition) -
provided that at,least one other operable channel in the same trip system is monitoring that parameter. 7mendment No. 37, 93 J' l
^
x0 ~~ MS Sh f
/ .\ ~
$*N (YcAV h
\
Table 4.2.1 Minimum Test and Calibration Frequency for Core Cooli Instrument Channel \ Rod Block and Isolation Instrumentation ) ' Test (3) Calibration (3) Sensor Check (3) ECCS INSTRUMENTATION - g t
- 1. Reactor Low-Low Water Level v Once/ month $ Note 5) Every Operating t Cycle - Transmitter Once/3 months -
i ' g Trip Unit Once/ Shift
- 2. Drywell High Pressure - v
- 3. Reactor Low Pressure (Pump Start) Once/ nth 5 Once/3 months None
- 4. Once nth 5 !
Reactor Low Pressure (Valve Permissive) Once/3 months None 'I
- 5. Undervoltage Emergency Bus (Once nth 5 Once/3 months None
- 6. Low Pressure Core Cooling Pumps R~etue n Outage Refueling Outage None Discharge Pressure Interlock t
- 7. Loss of Auxiliary Power Once/m}onth5 Once/3 months None
- 8. eu ng Outage Condensate Storage Tank Level Refueling Outage None
- 9. Reactor High Water Level Refueling Outage Refueling Outage i
None !
/'TnTe~/^ months (Note Every Operating j
)f _ ]
Cycle - Transmitter Every 3 months - Trip Unit i ROD BLOCKS Once/ Shift N
- 1. APRM Downscale 3
- 2. APRM Flow Variable Once/ onthf Note 5) Once/3 months None 4
- 3. IRM Upscale Once/(onthfNote5) mies (2,s M
Once/3 months None IRM Downscale No Note 2 Note 2 j 5. RBM Upscale 5 Note 2 Note 2 t
- 6. nee /Spnt Note 5)
RBM Downscale Once/3 months None
- 7. SRM Upscale nee / month 9 Note 5) Once/3 months None
- 8. No 2, SRM Detector Not-Full-In Position Note 2 Note 2
- 9. Scram Discharge Volume-High4 Level Notes (2,9) Note 2 y Once/3 months Refueling outage None None MAIN STEAM LINE (CROUP I) IS01ATION
- 1. Steam Tunnel High Temperature ,
- 2. Steam Line High Flow Refueling Outage Refueling Outage None
, Once/3 months Once/3 Months Once/ Shift j
__f , 1 3.2/4.2 NY121 '/15/02 / __..___._.____.__m___ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ - _ _ _ _ . _ _
M*d % e 7gd gg gf
]' 4 Table 4.2.1 - ntinued n i -
Minimum Test cnd Calibration Frequ:ncy For C:re Csoli Rod Block and Isolation Instrumentation )3~ af W , Instrument Channel Test (3) Calibration'(3). Sensor Check (3){ f h Once/3 months once/3 months- None
- 3. Steam Line Low Pressure Every Operating Cycle-Reactor Low Low Water Level Once/3 months (Note 5) Once/ shift i 4. Transmitter f
q Once/3 Months-Trip Unit - I CONTAINMENT ISOLATION (CROUPS 2 & 3) f
- 1. Reactor Low Water Level (Note 10) -
Drywell liigh Pressure (Note 10)
- 2. _
IIPCI (CROUP 4) IS0TATION 3 v Once/ month $ Once/3 months None
- 1. Steam Line fligh FNw None
- 2. Steam Line liigt .emperature .
Once/ onth9 Once/3 months
^
RCIC (GROUP 5) ISOLATION Once/ month s
*h once/3 months None
- 1. Steam Line liigh Flow None
- 2. Steam Line High Temperature f Once/ onth3 Once/3 months l
REACTOR BUILDINC VENTIIATION & STANDBY CAS TR EATMENT
- 1. Reactor Low Low Water Level Once/3 months (Note 5) Every Operating Cycle - Once/ shift q Transmitter Once/3 months - Trip Unit i
- 2. Drywell liigh Pressure (Note 10) -h -
Once/3 months Once/ day
- 3. Radiation Monitors (Plenum) Once/monthf Note 4
- 4. Radiation Monitors (Refueling Floor) [ Once/ months Once/3 months x
RECIRCUIATION PUMP TRIP AND ALTERNATE ROD IN: ECTION 3 once/vmonths Note 5) Once/ Operating Cycle- Once/ Day
- 1. Reactor liigh Pressure Transmitter Once/3 Months-Trip Unit .
h (Note 5) Once/ Operating Cycle- Once/ shift
- 2. Reactor Low Low Water Level [ Once/mont Transmitter .
k / s
\ Once/3 Months-Trip Unit Sil0TDOUN COOLING SUPPLY ISOTATION }
'b v- None
- 1. Reactor Pressure Interlock ] Once/ month 5 Once/3 Honths 3.2/4.2 v 62 ,,
as a_ w a v 6
-f-f -
y
l l Exhibit C Revised Technical Specification Pages Monticello Nuclear Generating Plant Supplement 1 to License Amendment Request Dated July 5,1995 Exhibit C consists of revised Technical Specification pages that incorporate the proposed changes. The pages included in this exhibit are as listed below: Pages 30 32 33 42 50 51 52 53 54 55 59 l 59a 60d 61 62 P . Page C-1 i
.. = . . _ . ..__ _
i Table 3.1.1 - Continued
- 6. Deleted. ,
- 7. Trips upon loss of oil pressure to the acceleration relay.
- 8. Limited trip setting refers to the volume of water in the discharge volume receiver tank and does not include the volume in the lines to the level switches. ;
- 9. High reactor pressure is not required to be operable when the reactor vessel head is unbolted. ;
i
- Reauired Conditions when minimum conditions for coeration are not satisfied. (ref. 3.1.B) I i
A. All operable control rods fully inserted. B. Power on IRM range or below and reactor in Startup, Refuel, or Shutdown mode. C. Reactor in Startup or Refuel mode and pressure below 600 psig. D. Reactor power less than 45% (798.75 MWt.).
** Allowable Bvoass Conditions it is permissible to bypass:
- a. The scram discharge volume High Water Level scram function in the refuel mode to allow reactor protection system reset. A rod block shall be applied while the bypass is in effect.
4
- b. The Low Condenser vacuum and MSIV closure scram function in the Refuel and Startup modes if reactor pressure is below 600 psig.
- c. Deleted. !
- d. The turbine stop valve closure and fast control valve closure scram functions when the reactor thermal power is s 45%
(798.75 MWt). 3.1/4.1 30 Amendment No. 44, 50, 63, 83,102 t
TABLE 4.1.1 SCRAM INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENTATION AND CONTROL CIRCUITS INSTRUMENTATION CHANNEL - FUNCTIONAL TEST MINIMUM FREQUENCY (4) High Reactor Pressure Trip Channel and Alarm Quarterly ; High Drywell Pressure Trip Channel and Alarm Quarterly Low Reactor Water Level (2,5) Trip Channel and Alarm Quarterly High Water Level in Scram Discharge Volume - Trip Channel and Alarm Quarterly i Condenser Low Vac Trip Channel and Alarm Once each month Main Steam Line isolation Valve Closure Trip Channel and Alarm Quarterly Turbine Stop Valve Closure Trip Channel and Alarm Quarterly ! Manual Scram Trip Channel and Alarm Weekly Turbine Control Valve Fsst Closure Trip Channel and Alarm Quarterly APRM/ Flow Reference (5) Trip Output Relays Quarterly IRM (5) Trip Channel and Alarm Note 3 Mode Switch in Shutdown Place mode switch in Every Operating Cycle l shutdown i t 32 3.1/4.1 Amendment No. 40,63,66. 84,83
}
TABLE 4.1.1 (Continued) Note 1: Deleted. Note 2: A sensor check shall be performed ori low reactor water level once per day. l Note 3: Perform functional test prior to every startup, and demonstrate that the IRM and APRM channels overlap at least 1/2 decade prior to every normal shutdown, Note 4: Functional tests are not required when the systems are not required to be operable or are tripped. If tests are missed, they shall be performed prior to returning the systems to an operable status. Note 5: A functional test of this instrument means the injection of a simulated signal into the instrument (not primary sensor) to verify the proper instrument channel response, alarm, and/or initiating action. 33 3.1/4.1 Amendment No. 63,81,83
J
' Bases 4.1: ,
The instrumentation in this section will be functionally test ad and calibrated at regularly scheduled intervab. Specific surveillance intervals and surveillance and msintenance outage times have been determined in accordance with NFCC-30851P, " Technical . Specification improvement Analysis for BWR Reactor Protection System," as approved by the NRC a' documented in the SER dated July 15,1987 (letter to T A Pickens from A Thadani). Calibration frequency of the instrument channe! .s divided into two groups as defined on Table 4.1.2. E::perience with passive type instrumer.ts ind. cates that a yearly calibration is adequate. Where possible, however, quarterly cal; oration is parformed. For those devices which employ amplifiers etc., drift specifications cam for drift to be less than 0.5%/ month; l i.e., in the perbd of a month a drift of 0.5% would cccur and thus provide for adequate margin. For the APRM system, drift of electronic apparatus is not the only conside~ation in determiriing a calibration frequency. Change in power distribution and loss of .[ chamber sensitivity dictate a calibration every three days. Calibration on this frequency assums plant operation at or below thermal limits. P 4.1 BASES 42 NEXT PAGE IS 45 Amendment No. 63,84,100a
Table 3.2.1 (Continued) Min. No. of Operable or Operating instru-Total No. of Instrument ment Channels Required Function Tri p Settings Channels Per Trip System Per Trip System (1,2) Conditions
- b. High Drywell Pressure (5) s 2 psig 2 2 D
- 3. Reactor Cleanuo System (Grouc 3)
- a. Low Reactor Water Level 2 7" (annulus) 2 2 E
- b. High Drywell Pressure s 2 psig 2 2 E
- 4. HPCI Steam Lines (Group 4)
- a. HPCI High Steam Flow s 150,000 lb/hr 2(4) 2 F l with s60 second time delay
- b. HPCI High Steam Flow s300,000 lb/hr 2(4) 2 F
- c. HPCI Steam Line Area High s200 F 16(4) 16 F Temp. g
- 5. RCIC Steam Lines (Group 5)
- a. RCIC High Steam Flow s45,000 lb/hr with 2(4) 2 G l 5 2 sec time delay
- b. RCIC Steam Une Area s200 F 16(4) 16 G
- 6. Shutdown Cooling Suoolv Isolation
- a. Reactor Pressure Interlock s 75 psig 2(4) 2 C at the reactor steam dome 3.2/4.2 50 Amendment No. 24,22,37,102
Table 3.2.1 (Continued) _ NOTES: (1) There shall be two operable or tripped trip systems for each function. A channel (a shared c%nnel is considered one channel) may l be placed in an inoperable status for up to G hours for required surveillance without placing the trip system in the tripped condition provided that at least one other operable channel in the same trip system is monitoring that parameter. (2) Upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels are not sabsiied action shall be initiated as follows: (a) With one required instrument channel inoperable in one or more trip functions, place the inoperable channel (s) or trip system in - the tripped condition within 12 hours, or (b) With more than one instrument channelinoperable fo one or more trip functions, immediately satisfy the requirements by placing appropriate channels or systems in the tripped condition, or (c) Place the plant under the specified required conditions using normal operating procedures. I (3) Low pressure in main steam line only need to be available in the RUN position. M) Allinstrument channels are shared by both trip systems. (9 May be bypassed when necessary only by closing the manual containment isolation valves during purging for containment inerting or de-inerting. Verification of the bypass condition shall be noted in the control room log. Also, need not be operable when primary containment integrity is not required. Required conditions when minimum conditions for operation are not satisfied. A. Group 1 isolation valves closed. B. Reactor Power on IRM range or below and reactor in startup, refuel, or shutdown mode. C. Iso'ation Valves closed for Shutdown Cooling System, and Reactor Head Cooling Line. D. Comply with Condition C. above. E. Isolation Valves closed for: Reactor Cleanup System. F. HPCI steam line isolated. (See specification 3.5 for additional requirements.) G. RCIC steam line isolated. l 3.2/4.2 51 Amendment No. 81,90
Table 3.2.2 Instrumentation That initiates Emergency Core Cooling Systems Minimum N3. of Minimum No. of Oper Operable or Total No. of Instru- able or Operating Operating Trip ment Channels Per Instrument Channels Required Function Trip Setting Systems (3) (6) Trip System Per Trip System (3) (6) Conditions
- l A. Core Sorav and LPCI
- 1. Pump Start
- a. Low Low Reactor 2 6'6* s 6'10* 2 4(4) 4 A.
Water Level and
- b. i. Reactor Low 24S0 psig 2 2(4) 2 A.
Pressure Permissive or ii. Reactor Low 20 1 min 2 1 1 B. Pressure Permissive Bypass Timer
- c. High Drywell s 2 psig 2 4(4) 4 A.
Pressure (1)
- 2. Low Reactor Pressure 2450 psig 2 2(4) 2 A.
(Valve Permissive)
- 3. Loss of Auxiliary Power - - - - - -
2 2(2) 2 A. 3.2/4.2 52 Amendment No. 62,93 _ . - . --___ _ ___ ___ _ _ _ _ _ _ _____ -- _ . _ _ _ _ _ . -.~ -
Table 3.2.2 Instrumentation That Initiates Emergency Core Cooling Systems Minimum No. of Minimum No. of Oper Operable or Total No. of instru- able or Operating Operating Trip ment Channels Per instrument Channels Required Function Trip Setting Systems (3) (6) Trip System Per Trip System (3) (6) Conditions
- l B. HPCI System
- 1. High Drywell Pressure s 2 psig 1 4 4 A.
(1)
- 2. Low-Low Reactor Water 2 6'6" s 6'10" 1 4 4 A.
Level C. Automatic Deoressurization
- 1. Low-Low Reactor Water 26'6* s6'10* 2 2 2 B.
Level and l 2. Auto Blowdown Timer s 120 seconds 2 1 1 B. and
- 3. Low Pressure Core 260 psig 2 12(4) 12(4) B.
Cooling Pumps s150 psig Discharge Pressure Interlock 3.2/4.2 53 Amendment No. 62,93,102
t I Table 3.2.2 - (Continued) , Instrumentation That initiates Emergency Core Cooling Systems Minimum No. of _ Min. No. of Oper: Operable or Total No. of Instru- able or Operating . Operating Trip ment Channels Per Instrument Channels Required Function Trip Setting Systems (3) (6) Trip System Per Trip System (3) (6) Conditions
- l j D. Diesel Generator i 1; ~ Degraded or Loss of i Voltage Essential Bus
.(5)
- 2. Low Low Reactor Water 2 6'6" s 6'10" 2 4(4) 4 C.
Level ,
- 3. High Drywell Press s2 psig 2 4(4) 4 C.
, NOTES: .
- 1. High drywell pressure may be bypassed when necessary only by closing the manual containment isolation valves during purging for containment in9rting or de-inerting. Verification of the bypass condition shall be noted in the control room log. Also need not be ;
operable when primary containment integrity is not required. ,
- 2. One instrurcent channel is a circuit breaker contact and the other is an undervoltage relay.
l i 3.2/4.2 54 ! Amendment No. 3, 93 4
?
_ m ..__ . _____m.. _ - . _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _
'k Table 3.2.2 - Continued l Notes: ,
- 3. Upon discovery that m": mum requirements for the number of operable or operating trip systems, or instrument channels are not satisfied action shall ue initiated as follows:
(a) With one required instrument channel inoperab! pr trip function, place the inoperable channel or trip system in the tripped condition within 12 hours or (b) \Nith more than one instrument channel per trip system inoperable, immediately satisfy the requirements by placing appropriate channels or systems in the tripped condition, or (c) Place the plant under the specified required conditions using normal operating procedures. -
- 4. Allinstrument channels are shared by t'oth trip systems.
- 5. See table 3.2.6.
- 6. A channel (a shared channel is considered one channel) may be placed in an inoperable status for up to 6 hours for required surveillance without placing the trip system in the tripped condition provided that at least one other operable channel in the same trip system is monitoring that parameter.
1 Required conditions when minimum conditions for operation are not satisfied. A. Comply with Specification 3.5.A. B. Reactor pressure s150 psig. C. Comply with Specification 3.9.B. , 3.2/4.2 55 Amendment No. 3,93 i
Table 3.2.4 Instrumentation That initiates Reactor Building Ventilation isolation And Standby Gas Treatment System Initiation Min. No. of Operable Total No. of instru- or Operating Instrument ment Channels Per Channels Per Trip Required Function Trip Settings Trip Sy; tem System Conditions *
- 1. Low Low Reactor Water 2 6'-6", s 6'-10* 2 2 (Notes 1, 3, 5, 6) A. or B.
Level
- 2. High Drywell Pressure s 2 psig 2 2 (Notes 1,3,5. 6) A. or B.
- 3. Reactor Building Plenum s100 mR/hr 1 1 (Notes 1,2,4) A. or B.
Radiation Monitors
- 4. Refueling Floor Radiation s100 mR/hr 1 1 (Notes 1, 2,4) A. or B.
Monitors Notes (1) There shall be two operable or tripped trip systems for each function with two instrument channels per trip system and there shall be one operable or tripped trip system for each function with one instrument channel per trip system. (2) Upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels are not satisfied action shall be initiated to: (a) Satisfy the requirements by p! acing appropriate channels or systems in the inpped condition, or ('o) Place the plant under the specified required conditions using normal operating procedures. (3) Need not be operable when primary containment integrity is not required. (4) One of the two monitors may be bypassed for maintenance and/or testing. 3.2/4.2 59 Amendment No. 40,74,91
- _m _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
t Notes: (cont'd): - (5). Upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels are not satisfied action shall be initiated as follows: (a) With one required instrument channel inoperable per trip function, place the inoperable channel or. trip system in the tripped .
- condition within 12 hours, or
' (b) With more than one instrument channel trip system inoperable, immediately satisfy the requirements by placing appropriate ;
channels or systems in the tripped condition, or-(c) . Place the plant under the specified required conditions using norrr al operating procedures. (6) - A channel may be 'placed in an inoperable status for up to 6 hours for required surveillance without placing the trip rystem in the tripped condition provided that at least one other OPERABLE channel in the same trip system is monitoring that parameter. ,
- Required Conditions when minimum conditions for operation are not satisfied.
A. The reactor building ventilation system isolated and the standby gas treatment system operating. i B. Establish conditions where secondary containment is not required. ; 4 i i I
- 3.2/4.2 59a
- Amendment No.
Table 3.2.8 Other instrumentation Minimum No. of Minimum No. of Operable or Oper- Total No. of Instru- Operable or Operating ating ment Channels Per Instrument Channels Required Function Trip Setting Trip System (1) (2) Trip System Per Trip System (1) (2) Conditions
- l A. RCIC Initiation
- 1. Low-Low Reactor Level 2 6'6" & s 6'10' 1 4 4 8 l
above top of active fuel B. HPCl/RCIC Turbine Shutdown
- a. High Reactor Level s 14' 6" above 1 2 2 A top of active fuel C. HPCl/RCIC Turbine Suction Transfer
- a. Condensate Storage 2 2' 0* above tank 1 2 2 C Tank Low Level bottom NOTE-
- 1. Upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels are not satisfied, action shall be initiated as follows:
- a. With one required instrument channel inoperable per trip function, place the inoperable channel or trip system in the tripped condition within 12 hours, or
- b. With more than one instrument channel per trip system inoperable, immediately satisfy the requirements by placing the appropriate channels or systems in the tripped condition, or
- c. Place the plant under the specified required condition using normal operating procedures.
- 2. A channel may be placed in an inoperable status for up to 6 hours for required surveillance without placing the trip system in the tripped condition provided that at least one other operable channel in the same trip system is monitoring that parameter.
Required conditions when minimum conditions for operation are not satisfied: A. Comply with Specification 3.5.A. l B. Comply with Specification 3.5.D. C. Align HPCI and RCIC suction to the suppression pool. Restore channels to operable status within 30 days or place the plant in Required Condition A for HPCI, or B for RCIC. l 3.2/4.2 60d Amendment No. 37,93
L Table 4.2.1 Minimum Test and Calibration Frequency for Core Cooling, l Rod Block and Isolation Instrumentatiori instrJment Channel Test (3) Calibration (3) Sensor Check (3) ECCS INSTRUMENTATION
- 1. Reactor Low-Low Water Level Once/3 months (Note 5) Every Operating Cycle -Transmitter l Once/3 months -Trip Unit Once/ Shift ,
- 2. Drywell High Pressure Once/3 months Once/3 months None-
- 3. Reactor Low Pressure (Pump Start) Once/3 months Once/3 months None
- 4. Reactor Low Pressure (Valve Once/3 months Once/3 months None Permissive) '
- 5. Undervoltage Emergency Bus Refueling Outage Refueling Outage None
- 6. Low Pressure Core Cooling Pumps Once/3 months Once/3 months None l Discharge Pressure Interlock
- 7. Loss of Auxiliary Power Refueling Outage Refueling Outage None
- 8. Condensate Storage Tank Level Refueling Outage Refueling Outage None
- 9. Reactor High Water Level Once/3 months (Note 5) Every Operating Cycle - Transmitter l
- Every 3 months - Trip Unit Once/ Shift i
ROD BLOCKS
- 1. APRM Downscale Once/3 months (Note 5) Once/3 months None
- 2. APRM Flow Vanable Once/3 months (Note 5) Once/3 months None
- 3. IRM Upscale Notes (2,5) Note 2 Note 2
- 4. IRM Downscale Notes (2,5) Note 2 Note 2 .
- 5. RBM Upscale Once/3 months (Note 5) Once/3 months None
- 6. RBM Downscale Once/3 months (Note 5) Once/3 months None
- 7. SRM Upscale Notes (2,5) Note 2 Note 2
- 8. SRM Detector Not-Fuli-In Position Notes (2,9) Note 2 None
- 9. Scram Discharge Volume-High Level Once/3 months Refueling Outage None MAIN STEAM UNE (GROUP 1) ISOLATION
- 1. Steam Tunnel High Temperature Refueling Outage Refueling Outage None
- 2. Steam Line High Flow Once/3 months Once/3 Months Once/ Shift !
4 3.2/4.2 61 Amendment No. 2,40,37,39,63,66,81 _ __ _ - = _ - _ _ _ _ _ _ _ _ _ _ _ - _ - _ - - _ _ _ _ - - _ _ _ - _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ - _ , - _ _ _ _ - _ _ _ _ - - _ _ - _ _ - _ _ _ - _ - . - _ - _ - - , - _ .
i Table 4.2.1 Continued Minimum Test and Calibration Frequency for Core Cooling, Rod Block and Isolation Instrumentation -l- i instrument Channel Test (3) Calibration (3) Sensor Check (3) '
- 3. Steam Line Low Pressure Once/3 months Once/3 months None
- 4. Reactor Low Low Water Le vel .Once/3 months (Note 5) . Every Operating Cycle-Transmitter Once/ shift Once/3 Months-Trip Unit CONTAINMENT ISOLATION (GROUPS 2 & 3)
- 1. Reactor Low Water Leve' (Note 10) - -
- 2. Drywell High Pressure (Note 10) - - -
HPCI (GROUP 4) ISOLATION ,
- 1. Steam Line High Flow Once/3 months Once/3 months None
~
- 2. Steam Line High Temperature Once/3 months Once/3 months None RClG (GROUP 5) ISOLATION
- 1. Steam Line High Flow Once/3 months Once/3 months None
- 2. . Steam Line High Temperature Once/3 months Once/3 months None REACTOR BUILDING VENTILATION & STANDBY GAS TREATMENT
- 1. Reactor Low Low Water Level Once/3 months (Note 5) Every Operating Cycle -Transmitter Once/ shift ,
Once/3 months - Trip Unit ,
- 2. Drywell High Pressure (Note 10) - - -
.; 3. Radiation Monitors (Plenum) Once/3 months Once/3 months Once/ day
- 4. Radiation Monitors (Refueling Floor) Once/3 months Once/3 months Note 4 r
RECIRCULATION PUMP TRIP AND ALTERNATE ROD INJECTION
- 1. Reactor High Pressure Once/3 tronths (Note 5) . Once/ Operating Cycle-Transmitter Once/ Day g Once/3 Months-Trip Unit
- 2. Reactor Low Low Water Level Once/3 months (Note 5) Once/ Operating Cycle- Transmitter Once/ shift ;
Once/3 Months-Trip Unit ! SHUTDOWN COOLING SUPPL ( ISOLAT_I_Q_N_
- 1. Reactor Pressure Interlock Once/3 months Once/3 Months None .l 3.2/4.2 62 l Amendment No. 74,84,83,91 [
_ _ _ - _ _ _ - _ . -__-_-__ __ _ _______-_ ___ _ - ______-- ___ - .}}