ML20107M514

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs 3/4.3.7.7 Re Relocation of Traversing in-core Probe LCO
ML20107M514
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 04/25/1996
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20107M512 List:
References
NUDOCS 9604300428
Download: ML20107M514 (11)
v • d • e


Text

-

I 1

l i

ATTACHMENT 2 UMERICK GENERATING STATION 1

UNITS 1 AND 2

.i Docket Nos.

j 50-352 1 50-353 .

1 i Ucense Nos.

NPF-39 NPF-85

, TECHNICAL SPECIFICATIONS CHANGE REQUEST i NO.95-084 J

l AFFECTED PAGES UNIT 1 UNIT 2 lx lx xix xix 3/43-8 3/43-8 3 3/4 3-89 3/4 3-89 -

B 3/4 3-6 B 3/4 3-6 i

l l

l l

l

)

1 l

9604300428 960425 ]

PDR ADOCK 05000352 .

P PDR  !

I

l Den ~

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS

} SECTION f

ggg 1

INSTRUMENTATION (Continued)

Table 4.3.7.1-1 Radiation Monitoring j

Instrumentation Surveillance Requirements.............................. 3/4 3-66 The infctmation from pages 3/4 3-68 i

4 through 3/4 3-72 has been intentionally omitted. Refer to note on page 3/4 3-68. . . . . . . . . . . . . . . . . . 3/4 3-68 The information from pages 3/4 3-73

'. through 3/4 3-75 has been intentionally omitted. Refer to note on page 3/4 3-73..................

4 3/4 3-73 4

Remote Shutdown System Instrumentation and Controls............. 3/4 3-76 t

Table 3.3.7.4-1 Remote Shutdown System Instrumentation and Controls................ 3/4 3-77 Table 4.3.7.4-1 Remote Shutdown System Instrumentation Surveillance j Requirements.............................. 3/4 3-83 Accident Monitoring Instrumentation............................. 3/4 3-84 i

Table 3.3.7.5-1 Accident Monitoring Instrumen-j i

tation.................................... 3/4 3-85 i \

Table 4.3.7.5-1 Accident Monitoring Instrumenta-l tion Surveill ance Requi rements. . . . . . . . . . . . 3/4 3-87 t

l Source Range Monitors........................................... 3/4 3-88 1

'r=:r: h; Ir-C:r: Pr:t y:te=................................. 3/4 3-89 i Chlorine Detection System....................................... 3/4 3-90 Toxic Gas Detection System...................................... 3/4 3-91

} g DELETED; Refer to note on page..................................

3/4 3-92 he InSoem& fm y614- .7/Y 2~89 M.r feen intenh*w IIy o M iHed-.

j Re.fer 44tW e e m e.

l LIMERICK - UNIT 1 ix Amendment No. 48,75,104 DEC 2 0 E 1

~

~

HDH - .

BASES . .

SECTION pgg INSTRUMENTATION (Continued)

(Deleted).............................................. B 3/4 3-5 (Deleted).............................................. B 3/4 3-5 Remote Shutdown System Instrumentation and Controls....

B 3/4 3-5 Accident Monitoring Instrumentation....................

  • B 3/4 3-5 Source Range Monitors.................................. B 3/4 3-5 ha;;nin; In C: n Pr i

~

t=........................ B 3/4 3-6 Add. Chlorine and Toxic Gas Detection Systems. . . . . . . . . . . . . . .

B 3/4 3-6

(Deleted).............................................. B 3/4 3-6 Loose-Part Detection System............................ B 3/4 3-7 (0eleted).............................................. B 3/4 3-7 Offgas Monitoring Instrumentation...................... B 3/4 3-7 1

3/4.3.8 TURBINE OVERSPEED PROTECTIONSYSTEM....................

B 3/4 3-7 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION........................................ B/3/4 3-7 Bases Figure B 3/4.3-1 Reactor Vessel Water Level........................ B 3/4 3-8 l 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM................................... B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES................................... B 3/4 4-2 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems........................... B 3/4 4-3 Operational Leakage................................. B 3/4 4-3 3/4.4'.4 CHEMISTRY........................................... B 3/4 4-3 LIMERICK - UNIT 1 xix Amendment No. 48,53,69,75, 104 BLG 2 0 WI5

. 1 Y

TABLE 4.3.1.1-1 (Continued) ,

REACTOR PADTECTION SYSTEM INSTillstENTATION SURVEILLANCE REQUIREMENTS t

OPERATIONAL E

m CllANNEL CONDITIONS FOR 6411 011 i CHANNEL FUNCTIONAL CHANNEL X flEICTIGNAL lalli CHECK TEST E8MBRAT10N SURVERL4EE REQUIREQ s

R I

9. Turbine Stop Valve - Closure N.A. Q 3 ,

[ 10. Turbine Control Valve Fast closure. Trip 081 R 1 Pressure - Low N.A. 4

11. Reactor Mode Switch R N.A. 1,2,3,4 S Shutdoun Position N.A. I,2,3,4,5 N.A. W N.A.
12. Manual Scram Neutron detectors may be excluded from CHAl#IEL CALIBRATION.

(a) The IRM and SlWI channels shall be determined to overlap for at least 1/2 decades during each startup after (b) entering OPERAT1011AL ColWITION 2 and the IRN and APRM channels shall be determined to overlap for a least 1/2 w

3 decades during each controlled shutdown, if not performed within the previous 7 days. l w (c) DELETED This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by J. (d) a heat balance during OPERATIONAL CONDITION 1 when THEllMAL POWER 225% of RATED THERMAL POWER. Adjust the AP channel if the absolute difference is greater than 21 of RATED THERNAL POWER.

This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated Dele flow he (e) signal.LPluts shall be calibrated at least once per 1000 effective full power hoursystem. (EfPil).-usdag (f) The Verify measured core flow (total core flow) to be greater than or equal to established core riow at the existing

[ (g) g loop flow (APRM E flow). During the startup test program, data shall be recorded for the parameters listed to g provide a basis for establishing the specified relationships. Comparisons of the actual data in accordance with g the criteria listed shall commence upon the conclusion of the startup test program.

This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 2 (h)

P 3.10.1.

(1) With any control rod withdrawn. Not appilcable to control rods removed per Specification 3.9.10.1 or 3.9.19 2.

(j) If the RPS shorting links are required to be removed per Specification 3.g.2, they may be reinstalled for up to 2 M.=m hours for required survelliance. During this time, CORE ALTERATIONS shall be suspended, and no control rod shall as g ro ;,, be moved from its existing position.

,u .

w (k) Required to be OPERA 8tE only prior to and during shutdown margin demonstrations as performed per Specification

_= 3.10.3.

E' m

f

Instatmetou i

/

f 3:i9i002560

) TP',','E0",I"O I",000E^ M O^uE s...sn p .

'~ . .*

[gaattw enunmnu egg garning3- to j

l - QL a :C ^ .

1 -

/

\.

3.3.7. .!

The traversing in-core prone system snail be OPERA 8tE with:

i'

a. /

and \e novaole cetectors, crives and readout egpipment to map, the c i

i

b. Index\ ing equipment to allow all five o a common location. ctors to be calibrataa in APPt.ICARILITY: When the ing in corp probe is used for:

a.

Recalibration of the L ctors, an6 b.* Monitoring the APLHGR, 74!CPR,orNFLPD.

ACTION:

}

3 With the traversing in can/

forSpecification of the soeve 3.0 applicabWmonitoring or. calibration. The functionsprobe provisions system

are not applicable.

1 l

SURVEILLANC EQUIREMENTS i~

4.3. . '

~ no The traversing in-core probe system shall be demonstrated OPE by use for the LPRM calibration function.lizing each of the above

' (

Md.

S e e k 2 H.3. 7.7 Add 7)ffYlv Mu $

i HM Bgty REtocprco TO 11/G. T~EdH Md4t- %d!nOkdr.

niANUAL ( TR.m) y--- alltk 4 - -

-.s., . , n ,_._m..

., . u _ . . _ _ .

-_n, . . .. ..

_.. , m m s; m , ,,,,,,, #

, LDECK - UMT 1 i

3/4 3 33 "1:r-__;.: . .. 11 m

  • M 4

4

- - - . - . - - - - . - _ - - . _ - - . _ - . - . . -- n i

{ INST 9UMENTATION b

BASES Y heme ~ - --ne-I 3/4.3.7.7 TRO'E;EN;I CORE RGBE 5$7E ( S e i e 5 6 d ) , T N W N T~l @ " '" M -

j 4

QwdECTION RQW TD THE TRM INe unMAntuiT or tne traversing in-core probe system with the specified mi -

complement 4 equipment ensures that the measurements obtained from use o

' equipment accu, j i

Core.

represent the spacial neutron flux distributi he reactor l

)  ;

The TIP system operability is #

l ' detectors) orior to performing an LAP-crThr normalizing all probes (i.e.,

(limitsmayinvolveutilizintindhidualdetectorstofunction. Monitoring core thermal ,

reactor core, thus al ctors may not be required to be or selected areas of the LE. The OPERABILITY

of individual ors to be used for monitoring is demonstrated b aring the
detect output in the resultant heat balance calculation (P-1) with da ained a a orevious heat balance calculation (P-1). '

N 3/4.3.7.8 CHLORINE 'AND T0XIC GAS DETECTION SYSTEMS i

The OPERABILIT( of the chlorine and toxic gas detection systems ensures that an accidental chlorine and/or toxic gas release will be detected promptly 4

and the necessary protective actions will be automatically initiated for chlo-rine and manually initiated for toxic gas to provide protection for control room personnel.

Upon detection of a high concentration of chlorine, the control room emergency ventilation system will automatically be placed in the chlorine

' isolation mode of operation to provide the required protection. Upon detection of a high concentration of toxic gas, the control room emergency ventilation system will manually be placed in the chlorine isolation mode of operation to provide the required protection. The detection systems required by this speci-fication are consistent with the recommendations of Regulatory Guide 1.95, " Pro-taction of Nuclear Power Plant Control Room Operators against an Accidental Chlorine Release," February 1975.

There are three toxic gas detection subsy' stems. The high toxic chemical concentration alarm in the Main Control Room annunciates when two of the three subsystems detect a high toxic gas concentration. An Operate /Inop keylock switch is provided for each subsystem which allows an individual subsystem to be placed in the tripped condition. Placing the keylock switch in the INOP position initiates one of the two inputs required to initiate the alarm in the Main Control Room.

Specified surveillance intervals and maintenance outage times have been determined in accordance with GENE-770-06-1, " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," as approved by the NRC and documented in the SER (letter to R.D.

Binz, IV, from C.E. Rossi dated July 21,1992).

3/4.3.7.9 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE TRM.

DEC 2 0 Wl15 LIMERICK - UNIT 1 FLML%R 68MR h'WhMW

., c 1

13Dil LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS. . -

SECTION

! Edsg l INSTRUMENTATION (Continued)

Table 4.3.7.1-1 4

Radiation Monitoring Instrumentation Surveillance Requirements....................... 3/4 3-66 1 --

1 The information from pages 3/4 3-68 through 3/4 3-72 has been intentionally

omitted. Refer to note on page 3/4 3-68. . . . . . . . . . . . . 3/4 3-68 The information from pages 3/4 3-73 s

through 3/4 3-75 has been intentionally omitted. Refer to note on page 3/4 3-73.............

3/4 3-73 Remote Shutdown System Instrumentation and Controls..... 3/4 3-76 Table 3.3.7.4-1 Remote Shutdown System Instrumentation and Controls....... 3/4 3-77 a

Table 4.3.7.4-1 Remote Shutdown System Instrumentation Surveillance j Requirements....................... 3/4 3-83 Accident Monitoring Instrumentation..................... 3/4 3-84 {

Table 3.3.7.5-1 Accident Monitoring Instruran-tation............................. 3/4 3-85 Table 4.3.7.5-1 Accident Monitoring Inst'.usenta-tion Surveillance Requirements..... 3/4 3-87 Source Range Monitors................................... 3/4 3-88 9:v:rsi ng-In-Cor ."r;h Syst;;;b. . . . . . . . . . . . . . . . . . . . . . 3/4 3-89 Chl orine Detecti on System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-90 Toxic Gas Detection System........................... .. 3/4 3-91 DELETED; Refer to note on page..........................

t 3/4 3-92 l Add c.ihmw+1L &m p9e 3/V J-99 nm heen in%WaHy miHed.

Rele k nok on pn e.

LIMERICK - UNIT 2 ix Amendment No. H 36,68 DEC 2 01995

c l

4 1HD11 i BASES - -

l SECTION  ! Phg j INSTRUMENTATION (Continued)

) (Deleted)................................................. B 3/4 3-5 I

(Deleted)................................................. B 3/4 3-5 Remote Shutdown System Instrumentation and Controls....... B 3/4 3-5 Accident Monitoring Instrumentation....................... B 3/4 3-5 n

B 3/4 3-5 hek)SourceRangeMonitors.....................................

Y Trre:r:i ng Ir.-- Cer; "re'a G;ter.. . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 3-6 g Chlorine and Toxic Gas Detection Systems.................. B 3/4 3-6

( 0el e t ed ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 3 Loose-Part Detection System............................... B 3/4 3-7 (Deleted)................................................. B 3/4 3-7 Offgas Monitoring Instrumentation......................... B 3/4 3-7 l

3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM....................... B 3/4 3-7 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION........................................... B 3/4 3-7 Bases Figure B 3/4.3-1 Reactor Vessel Water  !

Leve1........................ B 3/4 3-8 l 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM.................................... B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES.................................... B 3/4 4-2 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems...............................

B 3/4 4-3 Operati onal Le akage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-3 3/4.4.4 CHEMISTRY............................................... B 3/4 4-3a LIMERICK - UNIT 2 xiX Amendment No. 4 ,42, 9 ,32,5 DEC 2 01995

k

- ?

TABLE 4.3.1.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRIMENTATION SURVEli1 ANCE REQUIREMENTS -

c .

iR CHANNEL OPERA 110NAL iS CHANNEL CONDITIONS FOR WHICli l CHA100EL FUNCTIONAL.

N CHECK- TEST - LALIBR4llonial E!BKittaELHW!IRER fimCTIGNAL INffT t R 1  ;

9. Turbine Stop Valve - Closure N.A. Q

" 10. Turbine Control Valve Fast i Closure, Trip 011 R 1 }

Pressure - Low N.A. Q i

11. Reactor Mode Switch R N.A. 1,2,3,4,5 l Shutdown Position N.A. 1, 2, 3, 4,'5 N.A. N N.A.
12. Manual Scram  ;

Neutron detectors may be excluded from CHANNEL CALIGRATION.

ia) The IRM and SAM channels shall be determined to overlap for at least 1/2 decades during each startup after t'(b) entering OPERATIONAL CONDITION 2 and the IRN and APRM channels shall be determined to overlap for a least 1/2 decades during each controlled shutdown, if not performed within the previous 7 days.

l

'i' c) DELETED This calibration shall consist of the adjustment of the APAN channel to conform to the MNfER. Adjust the APRM zower values calculated by l

" ((d) a heat balance during GPERATIONAL CONDITION 1 when THERMAL PONER 225% of RATED THERNAL r channel if the absolute difference is greater than 2% of RATED THERMAL POWER.

8 g [

y(e) This signal. calibration shall consist of the adjustment of the APRM flow biased channel t t e

LPRMs shall be calibrated at least once per 1000 effective full power hours (EfPH) i Pe (f) The core flow at the existing Verify measured core flow (total core flow) to be greater than or equal to estabitshed .-us ng-4~ (g) loop flow (APRM 5 flow). During the startup test program, data shall be recorded for the parameters listed to

" provide a basis for establishing the specified relationships. Comparisons of the actual data in accordance with  !

om the criteria listed shall commence upon the conclusion of the startup test program. .

This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specificafion M y (h) .g3 l E 3.10.1.

Nith any control rod withdrawn. Not applicable to control rods reamved per Specification 3.9.10.1 or 3.9.10.2.'

m (1) If the RPS shorting links are required to be removed per specification 3.9.2, they may be reinstalled for up to 2 y

(j) hours for required survelliance. During this time, CORE ALTERATIONS shall be suspended, and no control rod shall -

jM be moved from its existing position. j a5 (k) Required to be OPERA 8tE only prior to and during shutdown margin demonstrations as performed per Specification ,

3.10.3.

t

i l

~

. INSTRUMENTATION l

,'j

...........m . . . - - . . . . . - -

.-o.. m owom revo6 maicn .. -

.,,_.....-........-----)

s.m unu wunv4iaun run vrumi ww 0 Q) / E. .j ,

N /

' 3.3.7.7 Thhtraversing in core probe system shall be OPERABLE,with:

l- N

a. Five movable detectors, drives and readout equi

/

nt to map the core, and 'N a

b.

K -

1 Indexing equipment to allow all five detectors to be calibrated in a-cosmon location. /

APPLICABILITY:

N When the traversing in core p / be i.s used for:

- a. Recalibration of the date rs, and

b.

x ACTION: \ '

I N l Withthetraversingin-coreprobesystemino\ perable, suspend use ri the system forSpecification of the above applicable 3.0.3 monitoring or calibratioh functions. Thr provisions

.. .' not applicable. -

SURVEILLANCE RE IREMENTS 4.3.7.7 traversing in-core probe sys' tem shall be demonstrated ERA 8LE by i

norna) zing each of the above required detector outputs within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />'ss prior to/use for the LPRM calibration function. N.

vr

$20.k 3/4I. 3. 7. 7- fy

.ra ,anar ,- ma ruan awwn~

gg ggg,y gtweAMc 10 THL TU.ausem 7&austD*tGH rr

/MphsyA L [ rt.M}, .

%,1y M ^7~~f." l' .

L t M; r'e) ir. C 7:;;id = :;rsat h::ti: ':) := 7 ;;i ; t:

Ot/c.k I

LIMERICK - WlIT 2 3/4 3-89 ME25 2

4

{ .

j @HRUMENTATION 1

BASES / M -V' # s _ _ -- _

l 3/4.3.7.7 T"l,bCP0I"k0 "000:

j YSTE"heldk((((

h [ $g i  % f-. v - w

! ine urtnamn.ui or Ine traversing in-core prese system witn tne spectrienq i

Din mus<omplement of equipment ensures that the measurements obtained from use f this he eqilipment reactor core. accurately represent the spacial neutron flux distribution of {

j The TIP system operability Memonstrated by nomalizing all probes (i.e.,,

detectors) prior to performing an LPR h stibration function. Monitoring core i

thermal limits may involve utilizing indivi j

treas of the reactor core, thus all detectors may ntectors required to monitor selected to be i-3PERABLE. The OPERABILITY of individual detectors to be u r monitoring is

! demonstrated by comparing the detector (s) output in the resultan balance l

calculation (P-1) with data obtained during a previous heat balance ca c on j -

(P-1).

3/4.3.7.8 CHLORINE AND T0XIC GAS DETECTION SYSTEMS The OPERABILITY of the chlorine and toxic gas detection systems ensures 4 - that an accidental chlorine and/or toxic gas release will be detected promptly i l'

and the necessary protective actions will be automattully initiated for chlo-rine and manually initiated for toxic gas to provide protection for control  !

i room personnel. Upon detection of a high concentration of chlorine, the control room emergency ventilation system will automatically be placed in the chlorine

,~

- isolation mede of operation to provide the required protection. Upon detection of a high concentration of toxic gas, the control room emergency ventilation system will manually be placed in the chlorine isolation mode of operation to provide the required protection. The detection systems required by this speci-fication are consistent with the recomunendations of Regulatory Guide 1.95, " Pro-taction of Nuclear Power Plant Control Room Operators against an Accidental

, Chlorine Release," February 1975.

There are three toxic gas detection subsystems. The high toxic chemical concentration alarm in the Main Control Room annunciates when two of the three subsystems detect a high toxic gas concentration. An Operate /Inop keylock switch is provided for each subsystem which allows an individual subsystem to be placed in the tripped condition. Placing the keylock switch in the IN0P position initiates one of the two inputs required to initiate the alarm in the Main Control Room.

Specified surveillance intervals and maintenance outage times have been determined in accordance with GENE-770-06-1, " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," as approved by the NRC and documented in the SER (letter to R.D.

Binz, IV, from C.E. Rossi dated July 21,1992). l 3/4.3.7.9 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE TRM. l l

l 1

DEC 2 01995 LIMERICK - tmIT 2 B 3/4 3-6 Amendment No. 44 25 0 0 33AL 68

Retrieved from "https://kanterella.com/w/index.php?title=ML20107M514&oldid=2814282"