NRC-97-0089, Proposed Tech Specs,Relocating Selected Requirements & Bases from TS to Ufsar.Rev of TS Index & List of Tables to Reflect Relocation Requested

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Proposed Tech Specs,Relocating Selected Requirements & Bases from TS to Ufsar.Rev of TS Index & List of Tables to Reflect Relocation Requested
ML20211J204
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Issue date: 09/29/1997
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CON-NRC-97-0089, CON-NRC-97-89 NUDOCS 9710080027
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Text

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NRC.97-0089 i

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i ENCLOSURE 3 - PART 1-  !

. PROPOSED TECHNICAL SPECIFICATION PAGE MARK UP t

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11MITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS ELTJDif P.AE 3/4.S INSTRUMENTATION -

3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION........... 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION................. 3/4 3 9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION..................................... 3/4 3-23 3/4.3.4 ATWS RECIRCULATION PUMP TRIP SYSTEM ACTUATION INSTRUMENTATION..................................... 3/4 3 32 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION..................................... 3/4 3-36 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION................... 3/4 3 41 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation................ 3/4 3 47 t

.Ds.l S:a=dJ u = u = u , :r. = = .ut er................... 3/4 3 si

.h: 0;h:1.".:;t t=b; b:trr:;t:t h;. . . . . . . . . . . 3/4 3 54 Remote Shutdown System Instrumentation and Controls. 3/4 3 57 Accident Monitoring Instrumentation................. 3/4 3 60 Source Range Monitors............................... 3/4 3 64 I  ; h C r: Pr o Sy:t e..................... 3/4 3-65 h44 C:u :t h; 0y;u ;.........................,.

b...hrine 3/4 3 66 Deleted............................................. 3/4 3 67 bshtr4 L:::: P:.t h u:t h; S;;S ......................... 3/4 3 70 Explosive Gas Monitoring Instrumentation............ 3/4 3-76 l 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION........................................ 3/4 3 86 3/4.3.10 RESERVE 0................................................

3/4.3.11 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION ....... 3/4 3 90 FERMI - UNIT 2 v Amendment No. 57, #7, #2,7J, 82 u

s l@ls BASES SECTION g 3/4.0 APPLICABILITY............................................ B J/4 0 1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN............................... B 3/4 1 1 3/4.1.2 REACTIVITY AN0MALIES.......................... B 3/4 1-1 3/4.1.3 CONTROL R0DS.................................. B 3/4 1 2 3/4.1.4 CONTROL ROD PROGRAM CONTROLS.................. B 3/4 1-3 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM................. B 3/4 1 4 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE.......................................... B 3/4 2-1 1

3/4.2.3 MINIMW CRITICAL POWER RAT!0.................. B3/423 3/4.2.4 LINr.AR HEAT GENERATION RATE................... B 3/4 2-4  ;

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION..... B 3/4 3 1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION........... B 3/4 3 2

, 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION............................... B 3/4 3 2 3/4.3.4 ATWS RECIRCULATION PUMP TRIP SYSTEM ACTUATION INSTRUMENTATION............................... B 3/4 3 3 1/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION..................... B3/433 s.

3/4.3.6 CONTROL R00 BLOCK INSTRUMENTATION............................... B 3/4 3 3 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.......... B 3/4 3 3

":: iter' ; ! :ter ::t:t he............ B 3/4 3 4 FERMI - UNIT 2 xii Amendment No. # , 69

i g

t B45ts -

1ECTION .

ggd INSTRUMINTATION (Continued) ,

MONITORINGINSTRUMENTATION(Continued) kMe "et::r:f.gical ."ar.it: rig h:tr.t:tica....... B 3/4 3-4 Remote Shutdown S Controls.........ystem Instrumentation and

............................... B3/43-4 AccidentMonitoringInstrumentation.............B3/434 Source Range Moni tors . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 3 4 hN t.rev: :.ng !r-C:r: .";;i: Sy:t::................. B 3/4 3 4 kbhd C.. . rin: 0:t::t he Sy:t::. . . . . . . . . . . . . . . . . . . . . . . B 3'/4 3 5

.. De l e t e d . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/ 4 3 5 h::b-N..

t 0:t::ti: Sy:t::. . . . . . . . . . . . . . . . . . . . . B 3/4 3 5 -

.. l I e

! Explosive Gas Monitoring Instrumentation........ B 3/4 3 6 l 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEMS ACTUATION .

INSTRUMENTATION................................. B 3/4 3 6 3/4.3.10 RESERVED 3/43.11 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMEhTAT!0N................................. B 3/4 3 6 3/4.# REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM............................ B 3/4 4 1 .

3/4.4.2 SAF ETY/ RELIEF VALVES. . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-la 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems....................... B 3/4 4-2 . -

Operational Le akage. . . . . . . . . . . . . . . '. . . . . . . . . . . . . . B 3/4 4 2 3/4.4.4 CH EM I ST RY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4 2 3/4.4.5 SPECIFIC ACTIVITY............................... B 3/4 4 3 3/4.4.6 PRESSURE / TEMPERATURE LIMITS..................... B 3/4 4 4

, 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES. . . . . . . . . . . . . . . . B 3/4 4 5

/ 3/4.4.8 STRUCTURAL INTEGRITY............................ B 3/4 4 5 3/4.4.9 RES IDUAL HEAT REM 0 VAL. . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4 5 FERMI UNIT 2 x111 Amendment No. /J, JJ JJ. JJ. N , 82-

//

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J LitT OF TAttf5 (Continued) -

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) 4.3.4 1 ATW5 RECIRCULATION PUMP TRIP ACTUATION -

. INSTRUMENTATION SURVEILLANCE REQUIRDENTS ....... 3/4335. .

3.3.5 1 REACTOR CORE 150LAT!0N COOLING SYSTEM ACTUATION .

i INSTRUNENTATION ................................. 3/4 3 37 l 3.3.5 2 * ' REACTOR CORE ISOLATION COOLING SYSTEM ACTUATIM j -

INSTRUMENTATION SETPo!NTS ....................... 3/4 3 39

! 4.3.5.1 1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION i

1 INSTRUMENTATION SURVE!LLANCE REQUIREMENTS ....... 1/4 3 40 l 3.3.5 1 CONTROL R00 BLOCK INSTRMENTATION ............... 3/4 1 42 j 3.3.6 2- CONTROL R3D SLOCK INSTRUMENTATION SETPOINTS ..... 3/4 3 44 I

! 4.3.6 1 CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE I

REQU!REMENTS ....................................* 3/4 3 45 l 3.3.7.1 1 RADI ATION MONITORING IK5TRUMENTATION ............ 3/4 3 45 i- 4.3.7.1-1 RADIATION MONITORING INSTR MENTATION i

SURVEILLANCE REQUIREMENTS ....................... 3/4 3 50 l 3.3.7.2-1 E'

' 3/4 3 52 l 1)CLEYEh .

j 4.3.7.2-1 e .

!"*."!! L L"! "20t'! Pl""! . . . . . . . . . . . . . . . . . . . . . . . 3/4 3 53

'bCLCYgQ,!Cta i;61TE!;;C 1; aZ:;; ;.T10;; .'......

3.3.7.3-1 rii!Gm. 3/4 3 55 4.3.7.3 1 fhff.h,' fy ".' t',qlg31;itT*L'"i'"'T!""

........ _... ,.._ ... ....................... 3/4 3 56 l 3.3.7.4-1 REMOTE SHUTDOW -

SYSTEN INSTRUMENTATION .......... 3/4 3 55 r

l 4.3.7.4-1 REMOTE SNUTDOW MONITORING INSTRUMENTATION j SURVEILLANCE REQUIREMENTS ....................... 3/43-59 3.3.7.5 1 ACCIDENT MONITORING INSTRUMENTATION ............. 3/4 3 51 . .

( 4.3.7.5 1 ' ACCIDENT MONITORING INSTRUMENTATION

  • l SURVEILLANCE REQUIREMENTS ....................... 3/4 3 63 l

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TEUtl . UNIT 2 xxili .

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INSTRUMINTATION 3M. 3. 7. 2. MLE TO SE15MIC MONITORING INSTRUMENTATION LIMITI ONDITION FOR OPERATION 3.3.7.2 The eismic monitoring instrumentation shown in Table 3.3.7.21 all be OPERABLE.

APPLICABILITY: A 11 times.

Ell @

a. With one or mor of the above required seismic itoring instruments inope ble for more than 30 days, spare and submit a Special Report to t Commission pursuant t pecification 6.g.2 within the next 10 da outlining the cau of the malfunction and the plans for restoring heinstrument( to OPERABLE stttus.

! b. The provisions of Specifica on 3.0 are not applicable. l l

l SURVEILLANCE REQUIREMENTS 4.3.7.2.1 Each of the above re # seismic me toring instruments shall be demonstrated OPERABLE by the p fomance of the C EL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL LIBRATION operations a the frequencies shown in Table 4.3.7.2 1.

4.3.7.2.2 Each of th bove required seismic monitoring i truments actuated during a seismic ev greater than or equal to 0.01 g shall restored to OPERABLE status W in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION per within 5 days followin he seismic event. Data shall be retrieved f actuated instruments a analyzed to detemine the magnitude of ths vibrato round motion. A ecial Report shall be prepared and submitted to the C ssion pursuant Specification 6.g.2 within 10 days describing the magnitu frequen . spectrum, and resultant effect upon unit features important to safe .

This pafs kas lun deb U.

FERMI - UNIT 2 3/4 3 51 Amendment No. 83

____~

TABLE 3.3.7.2 1 3EL.ETE3 MINIMUM MEASUREMENT INSTRUMENTS INSTh0MENTS AND SENSOR LOCATIONS RANGE APERABLE

1. A ve Triaxial System
a. Ac ve Triaxial Accelerometers
1) I Room 11 1 j 2) Bass f RPV Pedestal, In Drywell al g 1

, b. Active Seism Recording System *

1) Relay Room, uxiliary Butidi NA 1**
c. Active Seismic Play ek Syste
1) Relay Room, Auxil ry utiding NA NA
2. Passive Triaxial Peak Shock rders
a. HPCI Room *** 1 ry Building
b. Relay Roem, Auxil *** 1
c. Refuel Floor, actor Building *** 1
d. Diesel Gene tor Room, RHR Complex *** 1
e. Pump Roo , RHR Complex
  • 1 f Cooli Tower, RHR Complex *** 1
  • Inchtpgseismictrigger.
    • With eactor control room annunciation.
      • E h passive accelerometer has 12 reeds, each monitoring a diff ent requency. The frequencies correspond to varying accelerations. The widest range is t 90 g.

YN5 pafL b<s lun ct'g./a.-/< /

FERMI UNIT 2 3/4 3 52 4

TABLE 4.3.7.h l

- SEit"!C "0"IT0n!NC INSTRU".E"T!^" EURVEILL*"EE RE001RE"E"T!

DCLcrch CHANNEL CHANNEL FUNCTIONAL CHANNEL INSTRUMENTE AND SENSOR LOCATIONS ,MECL. TEST CALIBRATION

/

1. Active iaxial System I
a. Activ Yriaxial Accelerometers
4) HPC Roon NA SA R
2) Base of PV Pedestal, j

/

In Drywe SA R

b. Active Seismic Rec rding System
  • 1
1) Relay Room, Auxil ry Building ** N(a) SA R
c. Active Seismic Playback Sy em
1) Relay Room, Auxilia Building N SA R ,
2. Passive Triaxial Peak Sho Recorders
a. HPCI Room A NA k
b. Relay Room, A 111ary Building NA NA R
c. Refuel F1 r, Reactor Building NA NA R
d. Diese Generator Room, RHR Comp ex NA NA R
e. P p Room, RHR Complex NA NA R
f. Cooling Tower, RHR Complex NA NA R
  • I luding seismic trigger.
    • ith reactor control room annunciation.

( Except seismic trigger.

7 t7 n p pa kas Secos deleleW.

FERMI - UNIT 2 3/4 3-53

. _ _ _ _ . . . . _ _ . _ . . _ _ _ _ _. _ . _ . . _ . _ _ _ _ . _ _ _ _ . . ~ . _ . . . _ . _ _ _ . _ _ . .

1 .: .

i" INSTRUMENTATION 4

3/4 3.7. 3 JELETE.D

, 0 LOGICAL MONITORING INSTRUMENTATION 1 .

j LIMIT CONDITION FOR OPERATION 3.2.7.3 T meteorologi_ cal monitoring instrumentati channels shown in Table ,

j 3.3.7.3-1 sha be OPERABLE.

APPLICABILITY: A 11 times.

i EIlQli:

I a. With less than th required annels OPERABLE in Table 3.3.7.3-1 for

, more than 7 days, p are nd submit a Special Report to the

Commission pursuant to ocification 6.9.2 within the next 10 days

! outlining the cause t malfunction and the plans for restoring the l instrumentation to ERABL tatus.

l b. The provisions f Specification .0.3 are not applicable. l 1

l' SUR'!EILLANC E0UIREMENTS

/

f 4.3.7.3 Each of the above required meteorological monitor'n instrumentation chann s shall be demonstrated OPERABLE by the perfonnance of CHANNEL CHECK

a HANNEL CALIBRATION operations at the frequencies shown in Ta e 4.3.7.3-1.

l l-1 d5 un tb <

O fRf 4

l i FERMI - UNIT 2 3/4 3-54 Aspendment No. 83

TABLE 3.3.7.3-1 JXL ETE.D METEOROLOGICALMONITQSINGINSTRUNENTAR6N ,'

MINIMUM CHANNELS INSTRUMENT OPERABLE a.' Wind Speed

. 1. Elev. 10 meters 1

2. Elev. 60 meters 1
b. Wind Direction

?. Elev. 10 ters 1

2. Elev. meters 1
c. Air T erature Difference l Elev. 10/60 meters 1 43 l'8 [d e., CC#3 C, E 4 ,

FERMI - UNIT 2 3/4 3-55

e .-

4

, TABLE 4.3.7.3-1. .

METE 0h! CAL MONITORING I SkRNEMION SURVEILLANCE RE6UIREMENTS CH L CHANNEL INSTRUMEFT ECK CALIBRATION

a. Wind Speed
1. Elev. 10 meters D SA
2. Elev. 60 meters D SA
b. Wind Direction
1. Elev. 10 me s SA
2. Elev. 60 ters D SA
c. Air Temp ture Difference 1 lev 10/60 meters 0 This pay b u jeu delaM. -I

/

FERMI - UNIT 2 3/4 3-56

i INSTRUMENTAUQN 3/ . 3. 7. 7 .bct.CTEb TRAK +ER$1NG IN CORE PROBE SYSTEM LIMIT G CONDITION F00 OPERATION 3.3.7.7 The traversing in core probe system shall be DP LE with:

a. ive movable detectors, drives and readout e ipment to map the core, a
b. Ind ing equipment to allow all five date ors to be calibrated in a c location.

APPLICABILITY: en the traversing in-core pro is used for:

a. Reca11 bra ion of the LPRM detectors, nd b.* Monitoring he APLNGR, LHGR, MCPR, r MFLPD.

EI1QH:

With the traversing in-co. probe system noperable, suspend use of the system

.for the above applicable itoring or libratior, functions. The provisions of Specification 3.0.3 are not pplicable jgyEILLANCE REOUIREMENTS 4.3.7.7 The traversing in-core to system shall be demonstrated OPERABLE by normalizing each of the above qui detector outputs within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to use when required for the LP calibra ion function.

%pp i ls Ln Aldd.

  • 0nly the d tector(s) in the required measurement locatio s) are required to

(

be OPERA .

FERMI - UNIT 2 3/4 3-65 Amendment No. 83 m .., . - -

INSTRLMENTATION

.Vs 3 7. 8 Mt-[TEb CHLORINE DETECTION SYSTEM N

LIMITING CONDITION FOR OPERATION

/

3.3.7.8 Two in endent chlorine detectors shal be OPERACLE with their trip setpoints ad,just to actuate at chlorine conce ration of less than or equal to 5 ppa.

APPLICABILITY: All 0 TIONAL CONDITIONS.

EIl0!i:

a. With one chlorine tector i operable, restore the inoperable detector to OPERABLE status thin 7 days or, within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, initiate and maintain isolatio of 11 control room emergency intakes by placing the HVAC syste the chlorine mode of operation,
b. With both chlorine de cto s inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain isolation o all c trol room emergency intakes by placing the HVAC system in e chlor e mode of operation.

I SURVEILLANCE REQUIREME 4.3.7.8 Each of the bove required chlorine det tors shall be demonstrated OPERABLE by perfo ce of a:

a. CHANNE FUNCTIONAL TEST at least once per days, and
b. L CALIBRATION at least once per 18 mont .

Tkis pop bis ben debbtl FERMI - UNIT 2 3/4 3-66 Amendment No. 83

INSTRUMENTATION

.3/f. 3. 7a/0 bCL G7ED '

LOOSE-PART DETECTION SYSTEM LIMITING \0NDITIONFOROPERATION /

3.3.7.10 Th loose-part detection system sha be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 a 2.

ACTION:

a. *With one o more loose-par detection system channels inoperable for more than 3 days, prepar and submit a Special Report to the Commission p suant to S ecification 6.9.2 within the next 10 days outlining the aitse of he malfunction and the plans for restoring the channel (s) o OPE LE status,
b. The provisions o ecification 3.0.3 are not applicable. l SJRVEILLANCE REOUIREME i

4.3.7.10 Each cha el of the loose art detection system shall be demonstrated OPE LE by performance f a: I

a. CHAN CHECK at least once r 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
b. C NEL FUNCTIONAL TEST at leas once per 31 days, and
c. HANNEL CALIBRATION at least once r 18 months.

] O $3 l w /e/l k },

PA}L

.r.

\

FERMI - UNIT 2 3/4 3-70 Amendment No. 83 ,

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INSTRUMENTATION l BASE 5 .

! !ONITORING ;NSTRUMENTAT; ON (Continued) 3.4.3.7.2 UEL5M%J1DNTORING TNSTRUhENTATION .DELc TcD l The DPdRnBILTY si se'seic ring instrumentation ensures it_t suf-ficient capability is avail promptly detemine the magnitude of a seismic -

cvent and evaluate the se o features important to safety. This capa-bility is required mit comparison o measured response to that used in

! the design ba or the unit. This instrumen is consistent with the 7ecom-i sendatioos Regulatory Guide 1.12. " Instrumentation rthquakes," April 1974.

l 3/4.3.7.3 METEOR NIGICAL MONITORING INSTRUMEGATION SgLcrca 1 The OPERABILI"Y oT% meteorologica Itoring Instrumentation ensures

! that sufficient meteorolog data a allsble for estinating potential radia .

! tion doses to the public as a re of routine or accidental M1 ease of radio- .

t cctive saterials to the atso re. capabilt$y is required to evaluate l the need for initiating ective measures rotect the health and safety l cf the public. This trumentation is consiste ith the recommendations of f Regulatory Guide . . "0nsite Meteorological Program , abruary,1972.

l 3/4.3.7.4 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION AND CONT 1 The OPERABILITY of the remote shutdown monitoring instrumentation ensures i that sufficient capability is available to permit shutdown and maintenance of

! HOT SHUTDOWN of the unit from locations outside of the control room. This j capability is required in the event control room habitability is lost and is j consistent with General Design Criterion 19 of 10 CFR Part 50.

l

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3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that l sufficient infomation is available on selected plant parameters to monitor j and assess ir:portant variables following an accident. This capability is con-sistent with the recommendations of Regulatory Guide 2.97 " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During cnd Following an Accident." December 1975 and NUREG-0737, " Clarification of

a. TMI Action Plan Requirements," Nov' ember 1980.

The multiple noble'ga's monitors installed on each division of the standby Gas Treatment.Systen provide the necessary monitoring capabilities to assure .

that the normal and extended monitoring ranges required by NUREG-0737 and

=

Regulatory Guide 1.97 are met.

3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup cnd shutdown. At these power levels, reactivity additions shall not be made without this flux level information available to the operator. When the inter-mediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted.

3/4.3.7.7 TRA?HLSING IN-CORE PROBE SYSRM 7) ELE 7 Ed The OPERABILL f the traverst in-core probe system with the specified cinimum complement of e nt ures that the cimasurements obtained from use of this equipment accurate resent the spatial neutron flux distribution of the reactor core.

The TIP system OPE LITY is nstrated by normalizing all probes (i.e.,

detectors) prict to forming an LPRM c ration function. Monitoring core thermal limits sa nvolve utilizing indivi detectors to monitor selected creas of the tor core, thus all detectors say be required to be OPERABLE.

The OPERABI of individual detectors to te used fo nitoring is dt.nonstrated by compa g the detector (s) output with data obtained du the previous LPRM calib ion.

FERMI - UNIT 2 B 3/4 3-4 Amendment No. 28 i

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- m -m ,...,m -

. 4 INSTRUMENTATIQti BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.7.8 CHL'OfLINE DETECTION SYSTEM DEt E7'ED The OPERABILITY the ch ine and detection system ensures that an accidental chlorine relea 1 be detected promptly and the necessary protective actions will b atically initiated to provide protection for control room personnel. pon de tion of a high concentration of chlorine, the control room emer ncy ventilat system will automatically be placed in the chlorine mode operation to provi he required protection. The

. detection syste equired by this specifica is consistent with the recommendatio of Regulatory Guide 1.95 "Prote on of Nuclear Power Plant Control Roo Operators against an Accidental Chlor Helease", Revision 1, January, 77 3/4.3.7.9 DELETED j 3/4.3.7.10 LOOSE-PART DETECTION SdTEM 36 f E 7 EZ)

The OPERABILITY o e-part detection system ensures that sufficient capability is he)lable to detect loose metallic parts in the primary system and av or m ate damage to primary system components. The allowable out-of-s ict times an "veillance requirements are consistent with the rec ations of Regulator ide 1.133, " Loose-Part Detection Program for Primary System of Light- r-Cooled Reactors," May 1981.

FERMI - UNIT 2 B 3/4 3-5 Amendment No. ES, $2, 82

SA ZHFMMA770N ONLY ADMINISTRAT1VE CONTRotS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional-Office of the NRC within the time period specified for each report.

CORE OPERATING LIMITS REPORT 6.9.3 Selected cycle specific core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR) before each reload cycle

- or any remaining part of a reload cycle. The analytical methods used to detennine the core operating limits shall be those previously reviewed and approved by the NRC in General Electric Company reports NEDE 240ll P-A and l NEDE-23785-1-PA.The core operating limits shall be determined so that all l applicable limits (e.g., fuel thermal mechanical limits, core thermal-hydraulic-limits ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. The COLR, including any mid cycle revisions or supplement thereto, shall be submitted upon issuance to the NRC Document Control Desk, with copies to the Regional Administrator and Resident Inspector prior to use.

6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title lo, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.2 The following records shall be retained for at least 5 years:

a. Records and lo;s of unit operation covering time interval at each power level,
b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety.
c. Ali. REPORTABLE EVENTS.
d. Records of surveillance activities, inspections, and calibrations required by these Technical Specifications,
e. Records of changes made to the procedures required by Specification 6.8.1.
f. Records of sealed source and fission detector leak tests and l results.
g. Records of annual physical inventory of all sealed source material l of record.

FERMI - UHT 2 6 21 Amendment No. JJ, JJ, 57, g

. 4

. Enclosure 3 to NRC-97 0089 ENCLOSURE 3 - PART 2 l

PROPOSED TECIINICAL SPECIFICATION REVISED PAGES

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liiDll llMITING CONDITIONS FOR OPERATION AND SURVElllANCE REQUIREMENTS SECTION PEE 3/_,4. 3 INSTRUMENTATION 3/4.3.1 -REACTOR PROTECTION SYSTEn INSTRUMENTATION........... 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION................. 3/4 3 3/4.3.3 -EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION..................................... 3/4 3-23 3/4.3.4 .ATWS RECIRCULATION PUMP TRIP SYSTEM ACTUATION INSTRUMENTATION..................................... 3/4 3 32 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION..................................... 3/4 3-36 3/4.3.6 CONTROL R0D BLOCK INSTRUMENTATION................... 3/4 3-41 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation................ 3/4'3 47 0eleted............................................. 3/4 3-51 l Deleted............................................. 3/4 3-54 l Remote Shutdown System Instrumentation and Controls. 3/4 3-57 Accident Monitoring Instrumentation................. 3/4 3-60 Source Range Monitors............................... 3/4 3-64 0eleted............................................. 3/4 3-65 l Deleted............................................. 3/4 3 l Deleted............................................. 3/4 3-67 Deleted............................................. 3/4 3-70 j Explosive Gas Monitoring Instrumentation............ 3/4 3-76 3/4.3.9 FEEDWATER/ MAIN TURDINE TRIP SYSTEM ACTUATION INSTRUMENTATION........................................ 3/4 3-86' 3/4.3.10 RESERVED................................................ ,

3/4.3.11 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION........ 3/4 3-90 FERMI - UNIT 2 v- Amendment No. EZ,E9,EE,7J,E2,

INDEX BASES SECTION. A EAGE 3/4.0- APPLICABILITY............................................ B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTOOWN MARGlH............................... B3/41-i '

3/4.1.2 REACTIVITY AN0MAllES..........................

B 3/4 1-1 3/4.1.3 CONTROL R00S.................................. B 3/4 1-2 3/4.1.4 CONTROL R00 PROGRAM CONTR0LS.................. B 3/4 1-3 i

3/4.1.5 STANDBY LIQUID CONTROL SYSTEM................. B 3/4 1-4 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE.......................................... B 3/4 2-1 3/4.2.3 MINIMUM CRITICAL POWER RATI0.................. B 3/4 2-3 3/4.2.4- LINEAR HEAT GENERATION RATE................... _B 3/4 2-4 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION..... B 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION........... B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION' INSTRUMENTATION............................... B 3/4 3-2 3/4.3.4 ATWS RECIRCULATION PUMP TRIP SYSTEM ACTUATION-INSTRUMENTATION............................... B 3/4 3-3 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION..................... B 3/4 3-3 3/4.3.6 CONTROL ROOLBLOCK INSTRUMENTATION...............................- B 3/4 3-3 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.......... B 3/4 3-3 Deleted....................................... B 3/4 3-4 l FERMI - UNIT 2 xii Amendment No. Ef, ES,

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INDEX BASES SECTION .

G PAGE INSTRUMENTATION (Continued)

MONITORING INSTRUMENTATION (Continued)

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0eleted............................... ......... B 3/4 3-4 j Remote Shutdown System Instrumentation and Co n t rol s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/ 4 3 - 4 Accident Monitoring Instrumentation............. B 3/4 3-4 Source Range Monitors........................... B 3/4 3-4 l

Deleted........... ........................... B 3/4 3-4 l Deleted......................................... B 3/4 3-5 j 0eleted......................................... B 3/4 3-5 Deleted......................................... B 3/4 3-5 l Explosive Gas Monitoring Instrumentation. . . . . . . . B 3/4 3-6 3/4.2.9 FEE 0 WATER / MAIN TUP.31NE TRIP SYSTEMS ACTUATION I N ST RUM ENT AT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/ 4 3 - 6 3/4.3.10- RESERVED 3/4 3.11 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTAT ION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B _ 3/4 3 - 6 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-la 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.......................

B 3/4 4-2 Operational Leakage. . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-2 3/4.4.4 CHEMISTRY....................................... B 3/4 4-2

'3/4.4.5 SPECIFIC ACTIVITY...............................

B 3/4 4-3 3/4.4.6 -PRESSURE / TEMPERATURE LIMITS.....................

B 3/4 4-4 3/4.4.7 MAIN STEAM LINE ISOLATION-VALVES................ B 3/4 4-5

' 3/4.4.B STRUCTURAL INTEGRITY............................

B 3/4 4-5 3/4.4.9 RESIDUAL HEAT REM 0 VAL........................... B 3/4 4-5 FERMI - UNIT 2 xiii Amendment No, f9,EE,ES,EE,7J,EE,

INDEX LIST OF TABLES (Continued)

TABLE

_PAGE 4.3.4-1 ATWS RECIRCULATION PUMP TRIP ACTUATION

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INSTRUMENTATION SURVEILLANCE REQUIREMEN15 . . . .-. . 3/4 3-35 3.3.5-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION -

INSTRUMENTATION . . . . . . . . . . . . . . . . . . . 3/4 3 37 3.3.5-2 REACTOR CORE-ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS . . . . . . . . . . . . . 3/4 3 39 4.3.5.1-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . . . . 3/4 3-40 3.3.6-1 CONTROL R0D BLOCK IRSTRUMENTATION . . . . . . . . . .

3/4 3-42 3.3.6-2 CONTROL R00 BLOCK INSTRUMENTATION SETPOINTS . . . . . 3/4 3-44 4.3.6-1 CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS ...,................

3/4 3-45 3.3.7.1-1 RADIATION MONITORING INSTRUMENTATION ........ 3/4 3-48 4.3.7.1-1 RADIATION MONITORING INSTRUMENTATION

-SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . 3/4 3-50 3.3.7.2-1 DELETED . . . . . . . . . . , ,

. . . . . . . . . 3/4 3-52 j 4.3.7.2-1 DELETED . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-53 l 3.3.7.3-1 DELETED . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-55; j 4.3.7.3 DELETED

. . . . . . . . . . . . . . . . . . . . . . ~3/4 3-56  !

3.3.7.4-1 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION ....... 3/4 3-58 4.3.7.4-l~ REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . 3/4 3-59 3.3-7.5 .

ACCIDENT MONITORING INSTRUMENTATION , . . . . . . . . 3/4 3-61 4.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . 3/4 3-63 F

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<3/4.3.7.4 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION-AND CONTROLS '

! The OPERABILITY. of- the. remote shutdown monitoring instrumentation ensures that-' sufficient capability is available-to permit shutdown and maintenance of i HOT SHUTDOWN of.the unit from locations outside of the control room. This-capability-is required in the event control room habitability is lost and'is consistent with General: Design Criterion 19 of 10 CFR Part 50. ,

- 3/4. 3. 7 '. 5 ACCIDENT MONITORING INSTRUMENTATION

-The OPERABILITY of the accident monitoring instrumentation ensees that sufficient information:is available on selected plant parameters to wnitor and

, assess important variables following'an accident. This capability is consistent with the- recommendations of Regulatory Guide 'l 97, " Instrumentation for' Light <

-Water Cooled Nuclear Power Plants- to Assess Plant Conditions' During and Following an Accident," December 1975 and NUREG-0737, " Clarification of TMI Action ~ Plan ~ Requirements," November 1980.

The-multiple noble gas monitors installed on each division of the Standby; .

Gas Treatment System provide the necessary monitoring capabilities to assure that the normal-and extended monitoring ranges required by NUREG-0737 and-l Regulatory Guide-1.97 are met. ~ '

3/4.3.7.6 'SOURCt RANGE MONITORS.

_ The = source range monitors provide the operator _ with information of the status.of-the neutron . level in the core at.very low power levels during startup;

-and shutdown. -l At these. power levels, reactivity additions shall not be-made

without this flux level-information available to the operator. When the intermediate range monitors are on scale, adequate information is available
without'the SRMs_and they can be retracted.

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