ML20116A960

Proposed Tech Specs Re Revision of App A,Ts for Licenses NPF-11 & NPF-18,relocating Fire Protection Requirements of Listed TS Sections

ML20116A960
Person / Time
Site:	LaSalle
Issue date:	07/15/1996
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20116A953	List: ML20116A950 ML20116A960
References
NUDOCS 9607290046
Download: ML20116A960 (88)

Text

_ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _

ATTACHMENT D PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS, FACILITY OPERATING LICENSES NPF-11 AND NPF-18 LASALLE COUNTY STATION UNITS 1 & 2 NPF-11 NPF-18 LICENSE PAGES: LICENSE PAGES:

8 6 9 7 Attachment 1 page 2 Attachment 1 page 3 TECHNICAL SPECIFICATION PAGES: TECHNICAL SPECIFICATION PAGES:

V V Vill Vill Xill Xill XV XV XXil XXil XXill XXill 3/4 3-74 3/4 3-74 3/4 3-75 3/4 3-75 3/4 3-76 3/4376 3/4 3-77 3/4 3-77 3/4 3-78 3/4 3-78 3/4 3-79 3/4 3-79 3/4 3-80 3/4 3-80 3/4 7-11 3/4 7-11 3/4 7-12 3/4 7-12 3/4 7-13 3/4 7-13 3/4 7-14 3/4714 3/4 7-15 3/4 7-15 3/4 7-16 3/4 7-16 3/4 7-17 3/4 7-17 3/4 7-18 3/4 7-18 3/4 7-19 3/4 7-19 3/4 7-20 3/4 7-20 3/4 7-21 3/4 7 21 3/4 7-22 3/4 7-22 3/4 7-23 3/4 7-23 3/4 7-24 8 3/4 3-5 B 3/4 3-5 B 3/4 7-2 B 3/4 7-2 B 3/4 7-3 B 3/4 7-3 6-2 62 9607290046 960715 )

PDR ADOCK 05000373 p PDR

l 1

l l

UNIT 1 LICENSE CONDITIONS - 2.C.(25) l Fire Protection Prooram (Section 9.5. SER. SSER #2. SSER #3 (NUREG-0519)). l l

(a) The licensee shall maintain in effect and fully implement all provisions of the approved fire protection plan. In addition, the licensee shall maintain the fire protection program set forth in Appendix R to 10 CFR Part 50, except for the following deviations:

l (i) Hydrostatic hose tests in accordance with NEPA 1962-1979, and (ii) No automatic fire detection systems in areas 2K/3K and SB4.

This License Ccadition is presently in effect, and will be superseded upon issuance of the

! standard license andition in accordance with the guidance of GLs 86-10 and 88-12.

(b) Prior to initial criticality, the licensee shall install a 1-hour rated barrier on all four sides of a partially protected power cable pan and a general sprinkler system, both located in the diesel-generator corridor.

A general fire sprinkler system and a designed and installed fire protection system were done under Modifications 1-1-82-035, and 1-1-82-055 for the Unit 1 and Unit 2 diesel generator corridors. The NRC staff confirmed, per Section 1.1 of the LaSalle Safety Evaluation Report (NUREG-0519), Supplement 4, that the additional fire protection in the i

diesel generator corridor had been added prior to exceeding 5 percent power as required by this License Condition.

l This License Condition was closed by inspection Report 50-373/88018(DRP) dated 8/16/88.

(c) Prior to startup after the first refueling outage, the licensee shat: provide fire protection systems in fire areas 2C/3C,4C3 and 6E.

This License Condition was tracked by Open item (373/81-00-120(DRP)). The additional fire detection zones were installed under Modification 1-1-82 289. Amendment 44 to License NPF-11 was approved June 20,1986. The NRC inspector verified that fire protection requirements of this License Condition were met. This Open item was closed by inspection Report 50-373/86035(DRP), dated 10/29/86. j l

l (d) Prior to startup after the first refueling outage, the licensee with respect to fire doors, shall implement one of the following:

(i) Perform an engineering review of the manufacturer's certified doors and door frames by a nationally recognized laboratory to certify that the door and frames provide the required fire resistance rating, or (ii) Test a replicate "as installed" door assembly by a nationally recognized laboratory to

determine the door rating, or ,

I l

1 l

UNIT 1 LICENSE CONDITIONS - 2.C.(25)(continued) ,

(iii) Replace manufacturer's labeled doors and door frames with UL rated items.

This License Condition was tracked by Open item (373/8100-130). This Open item was closed by inspection Report 50-373/86046(DRP), dated 2/18/87.

(e) Prior to -tartup after the first refueling outage, the licensee shall demonstrate the adequacy of its fire protection for record storage. ,

The Non-Compliance item was closed by inspection Report 59-373/83-12(DPRP), dated 6/13/83. The License Condition was closed by inspection Report 373/83-25(DPRP), dated 81318 3.

I i

1

- 8- 04/17/82-Lican:o No. NPF-11 I (b) A prelube pump, powered from a reliable direct current power supply, be installed in the system to operate in parallel with the engine-driven lube oil pemp, or an alternative acceptable to the NRC shall be installed to preclude dry-starting of the diesel-engine.

(c) Controls and monitoring instrumentation be removed from the engine and engine skid, except instruments qualified for this location. The non-qualified control and monitoring instruments shall be installed on a free standing floor mounted panel and located on a vibration free floor area. If the floor is not vibration free, the panel shall be equipped with vibration mounts.

gER)

(22) Direct current Power Syst -- fEaction B.3.1.2.

Prior to startup after the first refueling outage for the 125 and 250-volt direct current systems for Divisions 1 and 2 and the 125-volt Division 3 direct current system, the following additional instrumentation shall be provided in the control rooms (1) Battery current (ammeter-charge / discharge), (2)

Battery charger output voltage (voltmeter), (3) Battery charger output current (mumeter), (4) Battery high discharge rate alarm, and (5) Battery charger trouble alarm. In the interim, the licensee shall implement approved procedures to monitor battery current, battery charger output voltage, and batter l

charger output current at the local panels at least once per i eight hour shift..

Cre)

(23) Remeter coneml===nt Electriem1 :Panatrations (Section 8.4.1.

l Prior to startup af ter the first refueling outage, a redundant fault current device (circuit breakers or fuses) shall be provided on each penetrating circuit that would limit a fault current surge to be less than the surge for which the penetration is qualified except for low energy (milliamps) instrument systems.

l (24) Eenarmtlen of class 1E and Non c1 mas 1E cable Trays (Eection 8.4.6.1, nee. gern si, care 42) 1 Prior to startup after the first refueling outage, the licensee i

shall provide adequate separation or barriers between Class 1E l and adjacent non-Class 1E cable trays.

nee, stem 32. Stre 83)

(25) Fire Protection Proaram (section 9.5.

= i v _

(a) The licensee shall maintain in effect and fully implement all provisions of the approved fire protection plan. In i

l addition, the licensee shall maintain the fire protection l program set forth in Appendia R to 10 CFR Part 50, except j )'

} for the following deviations: f l 0011k

- I N.S h T W _

INSERT A The licensee shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Updated Final Safety Analysis Report for LaSalle County Nuclear Station, and as described in the SERs for NUREG-0519, NUREG-0519 Supplement 2, NUREG 0519 Supplement 3, NUREG-0519 Supplement 5, NUREG-0519 Supplement 7, and NUREG-0519 Supplement 8, subject to the following provision:

The licensee may make changes to the approved Fire Protection Program without prior Commission approval only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a firo.

i l

l I

t 1

1 I

i 4

i J

- . . . . - _ . . - . - . . - -. . . - - - . . . . - - - . . . ,- - - . - ~ - - . - . _ . - . . .~ --- . _ - _ .

I l

04/10/89 l License Co. NPF-11 f Hydrostatic hose tests in accordance with NEPA (1) <

1962-1979, and I (ii) No automatic fire detection systems in areas f 2K/3K and 5B4.  ; l f> (b) Prior to initial criticality, the licensee shall install a I

)

l l-hour rated barrier on wil four sides of a partially protected power cable pan and a general sprinkler system, l-

' both located in the diesel- generator corridor. l l

l (c) Prior to startup after the first refuellag outage, the licensee shall provide fire protection systems in fire l areas 2C/3C, 4C3 and 6E.

(d) Prior to startup after the first refueling outage, the licensee with respect to fire doors shall implement one of the followings (1) Perform an engineering review of the manufac-turer's certified doors and door frames by a nationally recognised laboratory to certify that the door and door framos provide the required fire resistance rating, or (ii) Test a replicate "as installed" door assembly by a nationally recognised laboratory to determine  !

the door rating, or (iii) Replace manuf acturer's labeled doors and door frames with UL rated items.

1 (e) Prior to startup af ter the first refueling outage, the l' licensee shall demonstrate the adequacy of its fire protection for record storage.

n _ _ -

j Am. 14 (26) DELETED ,

5/05/83 ,

f (27) ImAustrial Security (Baction 13.6. Efe. nEEe $3) J Am. 65 CECO shall fully implement and maintain in effect all j 4/10/09 provisions of the Commission approved physical security, guard training and qualification, and safeguards contingency plans including unendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 ,

CFR 50.90 and 10 CFR 50.54(p). The plans, which contain l 0011k

,- , _ . ., - - - . , , ~ , , , , - . , ,

4 f  :

i

INDEX j

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i

i

SECTION J

PAGE

~

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRtMENTATION. . . . . . . . . . . . . . . . .3/4 . . . 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION. . . . . . . . . . . . . . . . . . . . . . . . 3/4 . . 3-9

3/4.3.3 EMERGENCY CORE C0OLING SYSTEM ACTUATION INSTRUMENTATION...... 3/4 3-23 1

j 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION lI ATWS Recirculation Pump Trip System Instrumentation.......... 3/4 3-3h i End-of-Cycle Recirculation Pump Trip System Instrumentation.....................................,....... 3/4 3-39 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION............................................ 3/4 3-45 3/4.3.6 CONTROL ROD WITHDRAWAL B LOCK INSTRUMENTATION. . . . . . . . . . . .3/4 . . . 3-50 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation......................... 3/4 3-56 Seismic Monitoring Instrumentation. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-60 Meteorological Monitoring Instrumentation. . . . . . . . . . . . . . . . . . . . 3/4 3-63 Remote Shutdown Monitoring Instrumentation................... 3/4 3-66 Accident Monitoring Instrumentation.......................... 3/4 3-69 Source Range Moni tors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-72 Traversing In-core Probe System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-73 Deleted...................................................... 3/4 3-74 '

(F i re Detection Ins trumentation. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-75 Deleted...................................................... 3/4 3-81 i Explosive Gas Monitoring Instrumentation.................... 3/4 3-82 '

Loose-Part Detection System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-85 3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION............................................. 3/4 3-86 LA SALLE - UNIT 3 V Amendment No. 85 '

1 1

i INDEX

\

l LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION -

PAGE l

3/4.7 PLANT SYSTEMS 3/4.7.1 CORE STANDBY COOLING SYSTEM - EQUIPMENT COOLING WATER SYSTEMS l Residual Heat Removal Service Water System................... 3/4 7-1 Diesel Generator Cooling Water System........................ 3/4 7-2 Ultimate Heat Sink........................................... 3/4 7-3 3/4.7.2 CONTROL ROOM AND AUXILIARY ELECTRIC EQUIPMENT ROOM EMERGENCY FILTRATION SYSTEM.................................. 3/4 7-4 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM........................ 3/4 7-7 3/4.7.4 SEALED SOURCE _ CONTAMINATION.................................. 3/4 7-9 65 FSUPP1ESSI3ii S STC h LETEl> . t . . . . . .. . .. ..... M'l 7 fFire Suppression Water System......... Z .................... 3/4 7-11 Del uge and/or Spru;kler Systems. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-14 t

i CO 2

Systems.................................................. 3/4 7-17 b M ose_ Stations.................................... ..._. 3/4 7-1 3/4.7.6 N RATED ASSEMBU C ................................. h/4_7-lP't h 3/4.7.7 AREA TEMPERATURE MONITORING.................................. 3/4 7-24 i 3/4.7.8 STRUCTURAL INTEGRITY OF CLASS I STRUCTURES................... 3/4 7-26 3/4.7.9 SNUBBERS..................................................... 3/4 7-27 3/4.7.10 MAIN TURBINE BYPASS SYSTEM................................... 3/4 7-33

~

LA SALLE - UNIT 1 VIII Amendment No. 18

1 i

4 i . HDEI )

! marts l

1 SECTION M INETRtY RTATION (Continued)

MONTTORING INSTRUMENTATION (Continued)

Meteorological Monitoring Instrumentation............ B 3/4 3-4a Remote Shutdown Monitoring Instrumentation........... B 3/4 3-4a

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

} L urce Range Monitors................................ B 3/4 3-5 l Traversing In-Core Probe System...................... B 3/4 3-5 1

Deleted.............................................. B 3/4 3- ]

l Fire Detection Instrumentation....................... B 3/4 3-5 L Deleted........_......._............,.................. B3/43-j Explosive Gas Monitoring Instrumentation............. B 3/4 3-6 l

Loose-Part Detection System.......................... B 3/4 3-6 l 1

3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION.................................... B 3/4 3-6 3/4.4 RrACTOR COOLANT EYstrM 3/4.4.1 RECIRCULATION SYSTEM................................. B 3/4 4-1 l

3/4.4.2 SA FETY / R ELI EF VALVES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-2 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 3/4.4.8 STRUCTURAL INTEGRITY................................. B 3/4 4-5 3/4.4.9 RESIDUAL HEAT REMOVAL................................ B 3/4 4-5 LA SALLE - UNIT 1 KIII Ame'ndment No. 104

7 INDEX BASES fDE t: b I SECTION _

b _T _ L.$ PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 CORE STANDBY COOLING SYSTEM - EQUIPMENT COOLING WATER SYSTEMS......................................... B 3/4 7-1 3/4.7.2 CONTROL ROOM AND AUXILIARY ELECTRIC EQUIPMENT ROOM EMERGENCY FILTRATION SYSTEM......................... B 3/4 7-1 3/4.7.3 - REACTOR CORE ISOLATION COOLING SYSTEM. . . . . . . . . . . . . . . . . . . B 3/4 7-1 I' 3/4.7.4 SEALED SOURCE CONTAMINATION.............................

B 3/4 7-2 3/4.7.5 i OIE SUPPRE5510N SYSTFMR...T........................... B 3/4 7-2 1- . - _

3/4.7.6 W E_RATFD A5$EMBLIF U... Z............................. B 3/4 7-3 3/4.7.7 AREA TEMPERATURE MONITORING............................. B 3/4 7-3 3/4.7.8 STRUCTURAL INTEGRITY OF CLASS I STRUCTURES.............. B 3/4 7-3 3/4.7.9 SNUBBERS................................................ B 3/4 7-3 3/4.7.10 MAIN TURBINE BYPASS SYSTEM.............................. B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS.................................... B 3/4 8-1 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES................. B 3/4 8-3 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH..................................... B 3/4 9-1 3/4.9.2 INSTRUMENTATION......................................... B 3/4 9-1 l 3/4.9.3 CONTROL R0D P0SITION.................................... B 3/4 9-1 l l

3/4.9.4 DECAY TIME.............................................. B 3/4 9-1 3/4.9.5 C0mVNICATIONS.......................................... B 3/4 9-1 3/4.9.6 CRANE AND H0IST......................................... B 3/4 9-1 3/4.9.7 CRANE TRAVEL............................................ B 3/4 9-2 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAGE P00L. . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.10 CONTROL ROD REM 0 VAL..................................... B 3/4 9-2 3/4.9.11 RESIDUAL HEAT REMOVAL COOLANT CIRCULATION............... B 3/4 9-2 LA SALLE - UNIT 1 XV Amendment No. 18

LIST OF TABLES (Continued) 18 ELE E8lif 4.3.7.3-1 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ......................... 3/4 3-65  ;

3.3.7.4-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION ........ 3/4 3-67 l 4.3.7.4-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION >

SURvExttANCE REQUIREMENTS ......................... 3/4 3-68 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION ............... 3/4 3-70 l 1

4.3.7.5-1 ACCIDENT MONITORING. INSTRUMENTATION SURVEILLANCE REQUIREMENTS ......................... 3/4 3 -

, - ~ -

(3.3.7.9-1 _ FIRE _ DETECTION INSTRUMENTATION ........._........... 3/4 3-76 3.3.7.11-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION ................................... 3/4 3-83 4.3.7.11-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ......... 3/4 3-84 3.3.8-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION ......................... 3/4 3-87 3.3.8-2 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SETPOINTS ............... 3/4 3-88 4.3.8.1-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS ......... 3/4 3-89 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES .. .3/4 4-9 3.4.4-1 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS ........... 3/4 4-12 4.4.5-1 PRIMARY ~ COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM .................................. 3/4 4-15 i 4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM WITHDRAWAL SCHEDULE ............................... 3/4 4-19 I

LA SALLE - UNIT 1 XXII ,

Amendment No.100

1 lllDfl LIST OF TABLES (Continued)

TABLE PAnf 3.6.5.2-1 SECONDARY CONTAINMENT VENTILATION SYSTEM  !

AUTOMATIC ISOLATION DAMPERS .............................. 3/4 6-39 3

3.7.5.2-1 DELUGE AND SPRINKLER SYSTEMS ..............'............... 3/4 7-16 i

.4-1 FIRE HOS_E STATIONS ....................................... 3/4 7-3.7.7-1 AREA TEMPERATURE MONITORING .............................. 3/4 7-25 4.8.1.1.2-1 DIESEL GEECRATOR TEST SCHEDULE ........................... 3/4 8-7b 4.8.2.3.2-1 BATTERY ' SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-18 3.8.3.3-1 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION ............................................... 3/4 8-27 B3/4.4.6-1 REACTOR VESSEL T0VGHNESS'................................. B 3/4 4-6 5.7.1-1 COMPONENT OYCLIC OR TRANSIENT LIMITS ............... ..... 5-6 i

l l

LA SALLE - UNIT 1 XXIII Amendment No. 102 l

i

i 4

i i

1 Pa3es 3/9 3 5wb k M3-ao Am h\ad) l 9.9 -Ti;; .;; NTENTIONALLY LEFT BLANK l

. LA SALLE - UNIT 1 3/4 3-74 Amendment No. 61 k(Next fme & W13-8l)

n UMENTATION FIRE DETECTI0ff INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.9 As a minimum, the fire detection instrumentation for each fire detection zone of-Unit I and Unit 2 shown -in Table 3.3.7.9-1 shall be i OPERABLE.*

i

! APPLICABILITY: Whenever equipment protected by the fire detection instrument

is required to be OPERABLE.

l ACTION:

I With the number of OPERABLE fire detection instruments less than the Minimum Instruments OPERABLE requirement of Table 3.3.7.9-1:

a. Within I hour, establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instru-ment (s) is located inside the primary containment, then inspect the primary containment at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.7.

b. Restore the minimum number of instruments to OPERABLE status within 14 days or, prepare and submit a Special Report to the Commission pursuant to Specification 6.6.C within 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REOUIREMENTS 4.3.7.9.1 Each of the above required fire detection instruments which are accessible during unit operation sha.11 be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. Fire detectors which are not accessible during unit operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.

4.3.7.9.2 The NFPA Standard 72D supervised circuits supervision associated with the detector alarms of each of the above required fire detection instru-ments shall be demonstrateo OPERABLE at least once per 6 months. Supervised circuits with detectors which are inassessible during unit operation shall be demonstrated OPERABLE during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 5 months. i

• The normal or emergency power source may be inoperable in OPERATIONAL CONDITION 4 or 5 or when defueled.

LA SALLE - UNIT I 3/4 3-75 Amendment No. 94

i i

l .

! TABLE 3.3.7.9-1 FIRE DETECTION INSTRUMENTATION INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE

• l FLAME SMOKE HEAT j A. Unit 1 Fire Detection Instrumentation i 1. Cable Spreading Room 21 i (Dry Pipe Sprinkler System)

2. Diesel Generator Corridor 7 I

j (Dry Pipe Sprinkler System)-

i 3. Unit 0 Cables Over Lab 32 l (Dry Pipe Sprinkler System)

! 4. Diesel Generator (DDG01K) Room 2 (C0 Flooding System) l

) 5. Diesel Generator (IDG01K) Room 2

! (CO Flooding System)

6. HPCS Diesel Generator Room 2 i (CO Flooding System) l 7. Control Room Ventilation (VC) Return i Air Monitor l System A 1

! System B 1 1 8. Control Room Ventilation (VC) Outside 1 Air Monitor

! System A 1 System B 1 i 9. Auxiliary Electric Equipment Room Ventilation (VE) j Return Air Monitor j System A 1 System B 1 i

I 10. SGTS Equipment Train

! (1VG015) 1 (2VG015) 1 i

11. Control Room Emergency Make-up Air Filter Unit (0VC01SA) 1 Filter Unit (0VC0158) 1

12. Control Room HVAC Supply Air I Filter Unit (0VC01FA) 1 l 1

Filter Unit (0VC01FB) 1

13. Auxiliary Electric Equipment Room HVAC Supply Air Filter Unit (0VE01FA) 1 HVAC Supply Air Filter Unit (0VE01F8) 1 LA SALLE - UNIT 1 3/4 3-76 Amendment i I 1

j

1. i

. l l

TABLE 3.3.7.9-1 (Continued)

FIRE DETECTION INSTRUMENTATION INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE

• HEAT FLAME SMOKE Unit 1 Fire Detection Instrumentation (Continued) 14'. Reactor Bldg./ Containment

a. Refuel Floor, Ione 1-26 6 E1. 843'6", Fire Hazard Zone Area 1

b. Reactor Bldg. East, Zone 1-24 11 E1. 820'6", Fire Hazard Zone 2B1 Reactor Bldg. West, Zone 1-23 9 c.

I E1. 820'6", Fire Hazard Zone 2B2

d. Reactor Bldg. South, Zone 1-36 18

E1. 786'6", Fire Hazard Zone 20

e. Reactor Bldg. North, Zone 1-37 17 E1. 786'6", Fire Hazard Zone 20 .

f. Reactor Bldg. South, Zone 1-34 22 E1. 761', Fire Hazard Zone 2E

g. Reactor Bldg. North, Zone 1-35 18 E1. 761', Fire Hazard Zone 2E

h. Containment, Zone 1-16P 7 El. 761' and 777', Fire Hazard Zone 2J Containment, Zone 1-16 9 1.

E1. 740' and 749', Fire Hazard Zone 2J

j. Reactor Bldg., Zone 1-17 5 E1. 740', Fire Hazard Zone 2F

k. Reactor Bldg. North, Ione 1-17P 11 E1. 740', Fire Hazard Zone 2F

1. Reactor Bldg. SW, Zone 1-22 4 E1. 710'6", Fire Hazard Zone ?G Reactor Bldg. NW, Zone 1-22P 6 m.

E1. 710'6", Fire Hazard Zone 2G

n. Reactor Bldg. South, Zone 1-32 17 E1. 694', Fire Hazard Icnes 2H1, 2H2, 2H3

o. Reactor Bldg. North, Zone 1-33 20 E1. 694', Fire Hazard Zones 2H1, 2H4, 2H5

p. Reactor Bldg. South, Zone 1-30 19 E1. 673', Fire Hazard Zones 211, 212, 2I3

q. Reactor" Bldg. North, Zone 1-31 20 E1. 673', Fire Hazard Zones 211, 214, 215 Reactor Bldg. West, Zone 1-40 7 r.

E1. 307', Fire Hazard Zone 2C LASALLE UNIT-1 3/4 3-77 Amendment No.44

n. - , - . - , . , , . . _ . . - .- . . . , ,

i .

! TABLE 3.3.7.9-1 (Continued)

FIRE DETECTION INSTRUMENTATION f

i INSTRUMENT LOC TION MINIMUM INSTRUMENTS OPERABLE

• HEAT FLAME SMOKE I

Unit 1 Fire Detection Instrumentation (Continued)

15. Auxiliary Building / Turbine Bldg f Aux. Bldg. Vent Floor, Zone 1-1 2 1 a.

' l E1. 815', Fire Hazard Zone 4A

b. Aux. Bldg. Vent Floor, Zone 1-2 8 i E1. 786'6", Fire Hazard Zone 4B I c. Control Room, Zone 1-5 15 i E1. 768', Fire Hazard Zone 4C1

d. Computer Room, Zone 1-6 8 E1. 768', Fire Hazard Zone 4C4

! e. Reactor Prot. M-G Set Room, Zone 1-12 12 El. 749', Fire Hazard Zone 403 ,

l f. Cable Spreading Area, Zone 1-18 15 )

E1. 749', Fire Hazard Zone 5A4

g. Div. 2 SWGR Room, Zone 1 3 15 I E1. 731'., Fire Hazard Zone 4E3 I

h. Aux. Electric Equipment Room, Zone 1-27 13 El. 731', Fire Hazard Zone 4E1 '

1. Aux. Bldg. Corridor, Zone 1-3 5  ;

E1. 731', Fire Hazard Zone 5B13 i

j. Aux. Bldg. Corridor, Zone 1-7 12 E1. 731', Fire Hazard Zone SB13

k. Div. 1 SWGR Room, Zone 1-9 17 E1. 710'6", Fire Hazard Zone 4F1 l

1. Aux. Bldg. Corridor, Zone 1-4 9 E1. 710'6", Fire Hazard Zone SC11

m. Div. 3 SWGR Room, Zone 1-10 5 E1. 687', Fire Hazard Zone 501

n. Aux. Bldg. Zone 1-39 10 El. 768', Fire Hazard Zone 4C2

o. Aux. Bldg. Zone 1-38 8 E1. 663', Fire Hazard Zone 6E

16. DG Bldg./DG Bldg. Corridor

a. DG Bldg., Zone 1-29 17 E1. 736'6", Fire Hazard Zones 7A1, 7A2, 7A3

b. DG Bldg. Corridor, Zone 1-25 3 I E1. 710'6", Fire Hazard Zone SC11 j DG Bldg., Zone 1-28 15 l

c. l El. 674' , Fire Hazard Zones 7C4, 7C5, 7C6

- l LASALLE UNIT-1 3/4 3-78 Amendment No.44 l l

i i

TABLE 3.3.7.9-1 (Continued) l FIRE DETECTION INSTRUMENTATION l INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE

• NEAT- FLAME SMOKE l

l Unit 1 Fire Detection Instrumentation (Continued) i 17. Off Gas Building I

a. Off Gas Building, Zone 1-15P 3 l E1. 710'6", Fire Hazard Zone 10A1

b. Off Gas Building, Zone 1-15 6

! E1. 690', Fire liazard Zone 1081 l B. Unit 2 Fire Detection Instrumentation Required For Unit 1

1. Cable Spreading Room 15 (Dry Pipe Sprinkler System)

2. Diesel Generator Corridor 9 (Dry Pipe Sprinkler System)

3. Diesel Generator (2D601K) Room 2 (Coe Flooding System)

4. Auxiliary Building / Turbine Bldg.

a. Aux. Bldg. Vent Floor, Zone 2-1 5 E1. 815', Fire Hazard Zone 4A

b. Aux. Bldg". Vent Floor Zone 2-2 9 E1. 786'6 , Fire Hazard Zone 48

c. Control Roos, Zone 2-5 17 E1. 7EB', Fire Hazard Zone 4C1

d. Record Roon Zone 2-6 3 E1.768',FireHazardZone4C5

e. Reactor Prot. M-G Set Room, Zone 2-12 12 E1. 749', Fire Hazard Zone 404

f. Cable Spreading Area, Zone 2-18 13 El 749', Fire Hazard Zone 5A4

g. Div. 2 SWGR Room, Zone 2-8 15 E1. 731', Fire Hazard Zone 4E4

h. Aux. Electric Equipment Roca, Zone 2-27 12 El. 731', Fire Hazard Zone 4E2

1. Aux. Bldg. Corridor, Zone 2-3 5 E1. 731', Fire Hazard Zone 5B13

j. Aux. B1dg. Corridor, Zone 2-7 12 E1. 731', Fire Hazard Zone 5813 -

LA SALLE - UNIT 1 3/4 3-79

1 .

I j TABLE 3.3.7.9-1 (Continued)

FIRE DETECTION INSTRUMENTATION l INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE *

< HEAT FLAME SMOKE

. Unit 2 Fire Detection Instrumentation Required I

For Unit 2 (Continued)

! k. Div. SWGR Room, Zone 2-9 17 l E1. 710'6", Fire Hazard Zone 4F2 j 1. Aux. Bldg. Corridor, Zone 2-4 . 9 j El. 710'6", Fire Hazard Zone SC11 i

m. Aux. Bldg., Zone 2-39 10 i El. 768', Fire Hazard Zone 4C3 j 5. DG Bldg./DG Bldg. Corridor

a. DG B1dg., Zone 2-29 14 i E1. 736'6", Firs Hazard Zones BA1, BA2

b. DG Bldg. Corridor, Zone 2-25 .

3

) E1. 710'6", Fire Hazard Zone 5C11

! c. DG Bldg., Zone 2-28 11 E1. 674', Fire Hazard Zones 8C3, 8C4, 8C5

6. Reactor Bldg.

a. Refuel Floor, Zone 2-26 6

) E1. 843'6", Fire Hazard Zone 1

b. Reactor Bldg. East, Zone P.-24 11 l

l El. 820'6", Fire Hazard Zone 381

c. Reactor Bldg. West Zore 2-40 7 i E1. 807', Fire Hazard Zone 3C 4

l LASALLE UNIT-1 3/4 3-80 Amendment No. 44

.7.f A 3.7.4 IArrrudo24LLY L. EFT BL44K. Payes 3/4 7-/2 %3k h SYSTEMS \ 3/'l 'F2J gre. le.le.ted.

3/4.7.5 FIRE SUPPRESSION SYSTEM FIRE SUPPRESSION WATER SYSTEM

-,~

LIMITING CONDITION FOR OPERATION j

! 3.7.5.1 The fire suppression water system shall be OPERABLE

• with: l l a. Two OPERABLE fire suppression diesel driven fire pumps, each with a

capacity of 2500 gpm, with their discharge aligned'to the fire suppression header,

~

b. An OPERABLE flow path capable of taking suction from the CSCS water i tunnel and transferring the water through distribution piping with i  !

OPERABLE sectionalizing control or isolation valves to the yard j i hydrant curb valves, the last valve ahead of the water flow alarm )

i ,

device on each sprinkler, hose standpipe, and the last valve ahead I i i of the deluge valve on each deluge or spray system required to be OPERABLE per Specifications 3.7.5.2 and 3.7.5.4.

l

! \ APPLICABILITY: At all times.

t I ACTION:

f- f i

! a. With one fire pump and/or one water supply inoperable, restore the

) inoperable equipment to OPERABLE status within 7 days or, prepare l and submit a Special Report to the Commission pursuant to Specifi-cation 6.6.C within the next 30 days outlining the plans and procedures to be used to restore the inoperable equipment to OPERABLE status or to provide an alternate backup pump or supply.

The provisions of Specification 3.0.3 are not applicable. j

b. With the fire suppression water system otherwise inoperable:

1. Establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and

2. Prepare and submit a Special Report in accordance with Specification 6.6.C; ,

a) By telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, .

b) Confirmed by telegraph, mailgram or facsimile transmission  !

no later than the first working day following the. event, and

c) In writing within 14 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

• The normal or emergency power source may be inoperable in OPERATIONAL TION 4 or 5 or when _defueled. _ - = -- - ---- _ _- _ _ _-

LA SALLE - UNIT 1 b/47-11[ t Amendment No. 94 (Qt is.V47-14)J

.n.

e

~

] [ANTSYSTEMS t r f SURVEILLANCE REQUIREMENTS .

4.7.5.1.1 The fire suppression water system shall be demonstrated OPERABLE:

l i a. At least once per 31 days by verifying that each valve, manual, power operated or automatic, in the flow path is in its correct position.

b. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.

c. At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system throughout its operating sequence, and:

1. Verifying that each automatic valve in the flow path actuates

. to its correct position,

2. Verifying that each fire suppression pump develops at least 3750 gpa at a system head of 205 feet, , {

3. Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and f

4. Verifying that each fire suppression pump starts sequentially to maints.in the fire suppression water system pressure greater then or equal to 118 psig. g

d. At least once per 3 years by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association.

L.7.5.1.2 iach diesel driven . fire suppression pump shall be demonstrated OPERABLE:

a. At least once per 31 days by:

1. Verifying the fuel day tank contains at least 130 gallons of fuel.

2. Starting:,

a) The fuel transfer pump and transferring fuel from the storage tank to the day tank. ,

b) The diesel driven pump from ambient conditions and operating for at least 30 minutes on recirculation flow.

l 3/4 7-12 Amendment No. 18i l LA SALLE - UNIT 1 l

l i

w:.: wi.p:.

fLANTSYSTIMS .

SURVEILLANCE RE0VIREMENTS (Continued)

b. At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM-D270-75, is within the acceptable limits specified in Table 1 of ASTM D975-77 when checked for viscosity, water and sediment.

c. Atleastonceper18 months,duringshutdown,bysubjectingthe diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service.

4.7.5.1.3 Each diesel driven fire pump starting 24-volt battery bank and charger shall be demonstrated OPERABLE: .

a. At least once per 7 days by verifying that:

1. The electrolyte level of each pilot cell is above the plates,

2. The pilot cell specific gravity, corrected to 77'F, is greater -

than or equal to 1.200, and

3. The overall battery voltage is greater than or equal to 24 volts. j l

b. At least once per 92 days by verifying that:

1. The voltage of each connected battery is greater than or. equal to 25 volts under float charge and has not decreased more than 2.8 volts from the value observed during the original test, 2, The specific gravity, corrected to 77'F,'of each connected cell is greater than or equal to 1.200 and has not decreased more than 0.05 frcs the value observed during the previous test, and

3. The electrolyte level of each <:ennected cell is above the plates.

c. At least once per 18 months by verifying that:

1. The battery shows no visual indication of physical damage or abnormal deterioration, and

2. Battery' terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.

1 l

LA SALLE - UNIT 1 3/4 7-13

I i

l r

PLANT SYSTEMS 4

DELUGE AND/OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION l

'4 3.7.5.2 The deluge and sprinkler i

Table 3.7.5.2-1 shall be OPERABLE.gystems of Unit I and Unit 2 shown

+

! APPLICABILITY: Whenever equipment protected by the deluge / sprinkler systems

! are required to be OPERABLE.

1 i ACTION:

I a. With one or more of the deluge and/or srickler systems shown in Table 3.7.5.2-1 inoperable, within 1 ;iour esublish a continuous fire watch with backup fire suppression equipment for those areas in

• which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol. Restore the system to f i l j

OPERABLE status within 14 days or, prepare and submit a Special

- Report to the Connission pursuant to Specification 6.6.C within the

+

next 30 days outlining the action taken, the cause of the inoper-ability and the plans and schedule for restoring the system to OPERABLE status.

i b. The provisions of Specification 3.0.3.are not applicable.

.i i SURVEILLANCE REOUIREMENTS 4

l 4.7.5.2 Each of the above required deluge and sprinkler systems shown in i Table 3.7.5.2-1 shall be demonstrated OPERABLE:

i j a. At least once per 31 days by verifying that each valve, (manual, 1

power-operated or automatic) in the flow path is in its correct i j position.

! b. At least once per 12 months by cycling each testable valve in the j flow path through at least one complete cycle of full travel.

! c. At least once per 18 months:

l ' 1'. By performing a system functional test which includes simulated j

automatic actuation of the system, and:

l a) Verifying that the automatic valves in the flow path l actuate to their correct positions on a test signal, and

b) Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.

I

• The normal or emergency power source may be inoperable in OPERATIONAL

j. ONDITION 4 or 5 or when defueled.

. UNIT 1 3/4 7-14 Amendment No. 94 LA SALLE

-. au - . =. ..= : .a :. .. . . . :t w . ..=. : . - . =:. . .

r .

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (C/.itinued) l

. 2. By a visual inspection of the dry pipe sprinkler and deluge

headers to verify their integrity, and ,

1

3. By a visual inspection of each deluge nozzle's spray area to verify that the spray pattern is not obstructed,

d. At least once per 3 years by performing an air. flow test through each open head spray and sprinkler header and verifying och open head deluge and sprinkler nozzle is unobstructed.

4 9

eeID e

4 0

0 C

9 O

LA SALLE - UNIT 1 3/4 7-15 j

~

. TABLE 3.7.5.2-1 DELUGE AND SPRINKLER SYSTEMS l

Location Elevation Fire Zone l

A. Unit 1 Deluoe and Sorinkler Systems  !

1. Diesel fuel storage tank (OD001T) room 674'0" 7C3 k

2. Diesel fuel storage tank (10001T) room 674'0" 7C2

3. HPCS diesel fuel storage tank (10002T) room 674'0" 7C1 4- HPCS diesel day tank (10004T) room 710'6" 7B4

5. Diesel generator day tank (0D002T) room 710'6" 7B6 l

6. Diesel generator day tank (10002T) room 710'6" 785

7. Cable spreading room 749'0" 4D1 l

8. Standby gas treatment system equipment train 820'6" 2B1 (1VG 015)* ,_

9. Control room emergency makeup filter 786'6" 4B unit (OVC 01SA)*

10. Control room emergency makeup filter 786'6" 48 unit (OVC 015B)*

11. Auxiliary electric equipment room HVAC srpply 786'6" 48 air filter (OVE 01FA)*

, 12. Auxiliary electric equipment room HVAC supply 786'6" 48 i air filter unit (OVE 01FB)*

13. Control room HVAC supply air filter 786'6" 48

- unit (OVC 01FA)*

14. Control room HVAC supply air filter 786'6" 4B unit (0VC 01FB)*

15. Stanaby gas treatment system equipment 820'6" 381 train (2VG015)*

16. Cable areas above laboratories, Unit 0 710'6" 4F3

17. Diesel generator corridor 710'6" SC11

18. Railroad Access Area 710'6" 2G B. Unit 2 Deluce and Sorinkler Systems Recuired For Unit 1

1. Diesel fuel storage tank (20001T) room 674'0" 8C4

2. Diesel generator day tank (20002T) room 710'6" 8B4 2%

3. Cabic spreed'.1; room 72.2 0"

~"

4 Diese: gerer nor corriace T.'." 5C11

" Surveillance Requirements 4.7.5.2.c.1 (a) and (b), 4.7.5.2.c.3 and 4.7.5.2.d are not applicable. Surveillance Requirement 4.7.5.2.c.2 is not applicable j o piping within the charcoal beds. /

LA SALLE - UNIT 1 3/4 7-16

IPLANT SYSTEMS

{Q2 SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.5.3 The following low pressure CO2 systems of Unit I and Unit 2 shall be OPERABLE.*

a. Division I ' diesel generator 0 room.

Division 2 diesel generator IA room.

b.

d I c. Division 3 diesel generator IB room.

d Unit 2 Division 2 diesel generator 2A room.

4 l

APPLICABILITY: Whenever equipment protected by the low pressure CO2 systems i is required to be OPERABLE.

ACTION:

i a. With one or more of the above required low pressure CO2 systems inoperable, within 1. hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant l

systems or components could be damaged; for other areas, establish

' an hourly fire watch patrol. Restore the system to OPERABLE status within 14 days or, prepare and submit a Special Report to the Com-mission pursuant to Specification 6.6.C within the next 30 days l l

outlining the action taken, the cause of the inoperability and the l 3

plans and schedule for restoring the system to OPERABLE status. i

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REOUTREMENTS l 4.7.5.3 Each of the above required low pressure CO2 systems shall be I' demonstrated OPERABLE:

a. At least once per 7 days by verifying CO2 storage tank level to be greater than 50% full and pressure to be greater than 290 psig, and 1

b. At least once per 31 days by verifying that each valve (manual, power operated, or automatic) in the flow path is in the correct position.

c. At least once per 18 months by verifying:

1. The system valves and associated motor operated ventilation dampers actuate, manually and automatically, upon receipt of a simulated actuation signal, and

2. Flow from each nozzle during a " Puff Test."

• The normal or emergency power source may be inoperable in OPERATIONAL G ONDITION 4 or 5 or when defueled.

3/4 7-17 Amendment No. 94 LA SALLE - UNIT 1

PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.5.4 The fire hose stations of Unit I and Unit 2 shown in Table 3.7.5.4-1 shall be OPERABLE.

APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.

ACTION:

a. With one or more of the fire hose stations shown in Table 3.7.5.4-1 l inoperable, route an additional fire hose of equal or greater diameter to the unprotected area (s)/ zone (s) from an OPERABLE hose station within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the inoperable fire hose is the primary means of fire suppression; otherwise, route the additionti hose  :

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Restore the inoperable fire hose station (t) to '

OPERABLE status within 14 days or, prepare and submit a Special Report to the Commission pursuant to Specification 6.6.C within the next 30 days outlining the action taken, the cause of the

! inoperability and the plans and schedule for restoring the system to j OPERABLE status.

1 i b. The provisions of Specification 3.0.3 are not applicable.

t I SURVEILLANCE RE0VIREMENTS

! 4.7.5.4 Each of the above required fire hose stations shown in Table 3.7.5.4-1 shall be demonstrated OPERABLE: i i i

! a. At least once per 31 days by a visual inspection of the fire hose 4

stations accessible during plant operation to assure all required i

{ equipment is at the station.

i

! b. At least once per 18 months by:

i

! 1. Visual inspection of the fire hose stations not accessible

{ during plant operation to assure all required equipment is at

- the station.

2. Removing the hose for inspection and reracking, and d

3. Inspecting all gaskets and replacing any degraded gaskets in the couplings.

l

! c. At least.once per 3 years by partially opening each hose station

valve to verify valve OPERABILITY and no flow blockage,

d. Within 5 years and between 5 and 8 years after purchase date and at least every 2 years thereafter by conducting a hose hydrostatic test j at a pressure of 150 psig or at least 50 psig above the maximum fire J main operating pressure, whichever is greater. _

LA SALLE - UNIT 1 3/4 7-18 Amendment No. 94 1

i _. . . . . .

1 ..

TABLE 3.7.5.4-1 i'

~ FIRE HOSE STATIONS

~

I LOCATION PROTECTED AREA ELEVATION HOSE RACK NUMBER A. Unit 1 Fire Hose Stations ,

I 1. Area 1 Area 1 843'6" F 101 F8 102 4

F 103 F 104 F 105

~

2. Zone 281 Zone 281 820'6" FB 108 F 109 F 111

3. Zone 2B2 Zone 282 820'6" FB 107 i FB 110

~

l 4. Zone 2C Zone'2C 807'0" F 112

! F 113 i F 114 i

! 5. Zone 2D Zone 2D 786'6" FB 115 F 116 .

1 FB 117

F 118 3 6. Zone 2E Zone 2E 761'0" F 119 ,

i F 120 .

F 121  ;

F 122 l

7. Zone 2F Zone 2F 740'0"" FB 123 Zone 2J F 124 i Zone 2K -

F 125 F 126 FB 127

8. Zone 2H1 Zone 2H1 694'6" F 135 Zone-2H2 - .

F 133 Zone 2H3 F 138 Zone 2H4 F 140 Zone 2HS ,

9. Zone 2H2 Zone 2H2 694'6" F 134

10. Zone 2H3 Zone 2H3 694'6" F 136

11. Zone 2H4 Z,one 2H4 694'6" F 139

12. Zone 2H5 Zone 2HS 694'6" F 137

13. Zone 2Il . re :1 673'4" FB M1

.;.e :2 FB 144 Zone 2I3 FB 146 Zone 2I4 FB 148 '

Zone 2I5 LA SALLE - UNIT 1 3/4 7-19

<W TABLE 3.7.5.4-1 (Continue

. FIRE HOSE STATIONS LOCATION PROTECTED AREA ELEVATION IDENTIFICATION HOSE RACK Unit 1 Fire Hose Stations (Continued)

14. Zone 212 Zone 2I2 '673'4" F 142

15. Zone 213 Zone 213 673'4" F 143

, 16. Zone 214 Zone 214 673'4" F 147

17. Zone 2I5 Zone 2I5 673'4" F 145

38. Zone 4A Zone 4A 815'0" FB 149

F 150 l 19. Zone 48 Zone 48 . . . . 786'6" F 151 l FB 152 F 153

20. Zone 4C2 Zone 4C1 768'0" F 154 -

and 5A3 Zone 4C2 FB 175 Zone 4C3 -FB 176 Zone 4C4 .

Zone 4C5

21. Zone 5A4 Zone 5A4 ~749'0" FB 248 Zone 401 FB 253 Zone 4D2 i Zone 403 l

22. Zone 583 Zone 5B13 -731'/735' FB 250 and 5813 Zone 4E1 FB 155 Zone 4E2 Zone 4E3 FB 185 Zone 4E4

23. Zone SC11 Zone SC11 710'6" FB 164 FB 192 Zone 781. 782, 783 FB 156 Zone 784, 785, 786 FB 191 Zone 4F1, 4F3 FB 157

24. Zone 7Al Zone 7Al 736'6" F 162

25. Zone 7A3 Zone 7A2 736'6"

• F 163 Zone 7A3

~

26. Zone 7C4 Zosse 7C1 673' FB 165 Zone 7C4

27. Zone 7C5 Zone 7C2 673' F 166 Zone 7C5

~

28. Zone 7CS Zone 7C3 673' F 367 Zc e 7C5

29. Zone IG Zone G 710 6 F nd

! F 129 l F 330 F 131 F 132 ]

LA SALLE - UNIT 1 3/4 7-20 me

~

. TABLE 3.7.5.4-1 (Continued)

~

l FIRE HOSE STATIONS -

LOCATION PROTECTED AREA ELEVATION IDENTIFICATION HOSE RACK Unit 1 Fire Hose Stations (Continued)

30. Zone 10A1 Zone 10A1 710'6" FB 205 l Zone 10A2 FB 206 FB 256

31. Zone 1081 Zone 1081 690' FB 207

32. Zone 10C3 Zone 10C3 674' F 208 F 209

8. Unit 2 Fire Hose Stations Required For Unit 1

1. Area #1 Area 1 843'6" F 301 FB 302 -

F 303

-F 304

. F 305

2. Zone 381 ZcP- 381 '

820'6" FB 308 -

F 309 ,

F 311 l I

3. Zone 4A ' Zone 4A 815'0" F 349 i F32

- F8 368 FB 450

4. Zone 48 Zone 48 786'6" F 351 F8 352 F 353

5. Zone 4C3 Zone 4C1 768' FB 354 l and 5A3 Zone 4C3 FB 375 Zone 4C4 Zone 4C5

6. Zone SA4 Zone 5A4 749' FB 405 f Zone 402 Zone 404 '

7. Zone 5813 Zone 5813 731' . FB 355 Zone 4E2 Zone 4E4

8. Zone 8Al' Zone 8A2 736'6" F 362 and 8A2 . F 363

' ~

9. Zone SCu Zone SC13 710'6" FB 357 Io e 4F2 F9 ;~1 Zee.r JE2  ? 27 -

Zone 884

10. Zone 8C3 Zone 8C2 674' FB 365 and 8C4 Zone 8C4 F 366 LA SALLE - UNIT 1 ,3/4 7-Z1 h

l PLANT SYSTEMS 3/4.7.6 FIRE RATED ASSEMBLIES LIMITING CONDITION FOR OPERATION

! 3.7.6 All fire rated assemblies, including walls, floor / ceilings, cable tray i

enclosures and other fire barriers separating safety-related fire areas-or j separating portions of redundant systems important to safe shutdown within a fire area, and all sealing devices in fire rated assembly penetrations (fire doors, fire windows, fire dampers, cable and piping penetration seals and

ventilation seals) shall be OPERABLE.

4 APPLICABILITY: At all times.

! ACTION:

l a. With one or more of the above required fire rated assemblies and/or sealing devices inoperable, within I hour either establish a con-l tinuous fire watch on at least one side of the affected assembly (s)

and/or device (s) or verify the OPERABILITY of fire detectors on at l 1 east one side of the inoperable assembly (s) and/or sealing i l

i device (s) and establish an hourly fire watch patrol. Restore the (

inoperable fire rated assembly (s) and/or sealing device (s) to l OPERABLE status within 7 days or, prepare and submit a Special

]

. Report to the Commission pursuant to Specification 6.6.C within the

! next 30 days outlining the action taken, the cause of the inoperable

! fire rated assembly (s) and/or sealing device (s) and plans and schedule for restoring the fire rated assembly (s) and/or sealing

!j device (s) to OPERABLE status. -

b. The provisions of Specification 3.0.3 are not applicable.

i j SURVEILLANCE REOUIREMENTS ,

! 4.7.6.1 Each of the above required fire rated assemblies and sealing devices i shall be verified to be OPERABLE at least once per 18 months by performing a l

visual inspection of:

f a. The exposed surfaces of'each fire. rated assemblies. _

i i b. Each fire window / fire damper and associated hardware.

t

c. At least 10 percent of each type of sealed penetration. If apparent

'! changes in appearance or abnormal degradations are found, a visual inspection of an additional 10 percent of each type of sealed j penetration shall be made. This inspection process shall continue until a 10 percent sample with no apparent changes in appearance or

' abnormal degradation is found.

4 i

4 i

3/4 7-22 Amendment No. 94 LA SALLE - UNIT 1 J.

1 1

PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) i 4.7.6.2 Each of the above required fire doors shall be verified OPERABLE by:

a. Verifying the position of each closed fire door at least once .

per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. l

b. Verifying that doors with automatic hold-open and release mechanisms are free of obstructions at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. Verifying the position of each locked closed fire door at least once per 7 days. .

d. Verify the OPERABILITY of the fire door supervsion system by performing a CHANNEL FUNCTIONAL TEST at least once per 31 days.

e. Inspecting the automatic hold-open, release and closing mechanism and latches at'least once per 6 months. .

O e

4 LA SALLE - UNIT 1 3/4 7-23

d

! INSTRUMENTATION j BASES __

4 f MONITORING INSTRUMENTATION (Continued) f 3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION

- The OPERABILITY of the accident monitoring instrumentation ensures that i sufficient information is available on selected plant parameters to monitor i and assess important variables following an accident. This capability is con-

sistent with the recommendations of Regulatory Guide 1.97, " Instrumentation

for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During l

and Following an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Tem Recommendations."

3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with infomation of the status of the neutron level in the core at very low power levels during startup and shutdown. At these power levels, reactivity additions should 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 TRAVERSING IN-CORE PROBE SYSTEM The OPERABILIT) of the traversing in-core probe (TIP) system with the specified. minimum comolement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core.

The specification allows use of substituted TIP data from symmetric channels if the control rod pattern.is symmetric since the TIP data is adjusted .

by the plant computer to remove machine dependent-and power level dependent bias. The source of data for the substitution may also be a 3-dimensional BWR core simulator calculated data set which is normalized to available real data.

Since uncertainty could be introduced by the simulation and normalization process, an evaluation of the specific control rod pattern and core operating state must be performed to ensure that adequate margin to core operating limits is maintained.

hL Fed

~

3/4.3.7.8 DELETED 3/4.3.7.9 M r nrTrrTION INSTRtiMnTAYIG [

ERKBILITY of the fire detectTon instrumentation ensures that adequate arning, capability is available for the prompt detection of fires. This capa-bility is required in order to detect and locate fires in their early stages.

Prompt detection of-fires will. reduce the potential for damage to safety-related equipmen kprogram.tandisanintegralelementintheoverallfacilityfireprotection In the event that ~a~'p'ortion of the fire detection instrumentation is inoperable, increasing the frequency of~ fire watch patrols in the affected areas is required to' prov~ide' detection capability until the inoperab_le

% trumentation is restored to OPERABILIT ,Y LA SALLE - UNIT 1 B 3/4 3-5 Amendment No. 85

l 1

PLANT SYSTEMS BASES 3/4.7.4 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emmitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.

Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of camege to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism, i.e., sealed sources within radiation monitoring or boron measuring devices, are considered to be stored and need not be tested unless they are removed from the_s Ided mechanism.

3/4. 7. 5 6"a"""" "c

^ -

The I)PERABILITi of in fire suppression systems ensures that adequaT.

~

ire suppression capabi; e.y is available to confine and extinguish fires occurring in any portion of the facility where safety related ecuipment is located. The fire suppression. system consists of the water system, deluge and/or sprinklers, CO, systems, and fire hose stations. The collective capability of the firt suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program. }

In the event that portions of the fire suppression systems are inoperable, j alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service. i When the inoperable fire fighting equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an alternate means of fire fighting than if the inoperable equipment is the primary means of fire suppression. f The surveillance requirements provide assurance that the minimum )

OPERABILITY requirements of the fire suppression systems are met, f In the event the fire suppressioa water system becomes inoperable, immediate corrective measures must be taken since this system provides the I major fire suppression capability of the plant. The requirement for a I twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire Quppression cap _ ability for the cantinued erotectionJ f_the nuclear plant.

l I

1 LA SALLE - UNIT 1 B 3/4 7-2 N

i -

~

I PLANT SYSTEMS

]

i BASES .

l 3/4.7.6 bF RATFD A11FIELIFC l The OPERABILITY of the fire barriers and barrier penetrations ensure hat fire damage will be limited. These design features minimize the

, possibility of a single fire involving more than one fire area prior to detection and extinguishment. The fire barriers, fire barrier penetrations l for conduits, cable trays and piping, fire windows, fire dampers,.and fire I(doors are periodicagted to verify their OPERABILITYv

! 344,.7.7 AREA TEMPERATURE MONITORING i

j The areh temperature limitations ensure that safety-related equipment will i not be subjected to temperatures in excess of their environmental qualification

temperatures. Exposure to excessive temperatures may degrade equipment and can j cause loss of its OPERABILITY. The temperature limits include allowance for an g

instrument error of 7'F.

}~

3/4.7.8 STRUCTURAL INTEGRITY OF CLASS 1 STRUCTURES

! In order to assure that settlement does not exceed predicted and allowable settlement values, a program has been established to conduct a survey at the site. The allowable total differential settlement values are based on criginal i

l settlement predictions. In establin,hing these tabulated values, an assumption i is made that pipe and conduit connection have been designed to safely withstand i the stresses which would develop due to totr.1 and differential settlement.

t 3/4 7.9 SNUBBERS l All snubbers are required OPERABLE to ensure that the structural integrity

of the Reactor Coolant System and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this . inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system. '

Snubbers are classified and grouped by design and manufacturer but not by size. For example, mechanical snubbers utilizing the same design features of the 2-kip,10-kip, and 100-kip capacity manufactured by Company "A" are of the same type. The same design mechanical snubbers manufactured by company "B" for the purpose of this Technical Specification would be of a different type, as would hydraulic snubbers from either manufacturer.

A list of individual ~ snubbers with detailed information of snubbers location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50. The accessibility of each

. LA SALLE - UNIT 1 8 3/4 7-3 Amendment No. 1 8

~ : - - .. . .

ADMINISTRATIVE CONTROLS

1. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In additioa, while the reactor is in OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior Reactor Operator who has been designated by We Shift Supervisor to assume the control room direction responsibilCY shall be in the Control Room.

2. A radiation protection technician" shall be on site Men fuel is in the reactor.

3. All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation. A

= , ~

4.

'be,he.d fat all times". N site Fire Fire Brigade Brigade shallof notatinclude least 5themembe'rs shalT be ma Shift Supervisor,

'the Station Contro: bon Engineer and the 2 other members of the mini-( mte shift crew necessary for safe shutdown of the unit and any personne Wouired for other essential _ functions during a fie= = = =

5. The Onsite Nucisar Safety Group (0NSG) shall function to examine unit operating characteristics,.NRC issuances, industry advisories, Licenssa Event Reports and other sources of plant design and operat-ing experience information, including plants of.similar design, which may indicate areas for improving unit safety. The 0NSG shall be composed of at least three, dedicated, full-time engineers of multi-disciplines located on site and shall be augmented on a part-

- time basis by personnel from other parts of the Commonwealth Edison Company organization to provide expertise not represented in the group. The 0NSG shall be responsible for maintaining gurveillance of unit activities to provide independent verification that these i activities are perfo' sed correctly and that human errors are reduced as much as practical. The 0NSG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activi-  ;

ties, operations activities or other means of improving unit safety l to the Safety Assessment Manager and the Station Manager.  ;

6. The Station Contrcil Room Engineer (SCRE) may serve as the Shift Technical Advisor (STA) during abnormal operating and accident con-ditions. During these conditions, the SCRE or other on duty STA shall provide technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard ,

to the safe operation of the unit.

"The radiation protection tectnician and Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed two hours in >

order to accommodate unexpected absence provided immediate action is taken to fill the required positions.

1. Not responsible for sign-off feature.

6-2 Amendment No. 78 LA SALLE - UNIT 1

= $ p

1 j

03/24/84 4

License D3. CPF-18 +

(1.) ,-...., ., - m . < -... . 1. - .1. - .n  ;

1 e

i Prior to startup after the first refuellag, the licensee shall have made comeitseats-acceptable to the NBC regarding the j gaidelines of Secties 5.1.2 through 5.1.6 of NUREG-0612.

1 (15) Fire Pre *=ati.= Pr - me (" diam 9.R. eso, me** A2. ;- 31.

j arza es. azza e7. sann ca.

j + L = - -

j (a) The licensee shall malatain is affoct all provisions of the approved fire protecties program.

(h) Prior to initial criticality, the licensee shall replace the 3 diesel fire pump engine and perform a test in i

accordance with Sections 11-2.3, 11-2.3 and 11-2.5 of l EFFh30/1983.

2 r

. ., . ~

{ - -

a l -

1 '.' .

'. (' .E b Prior the fire to protecties initial critioality,, leep flew the 11oemsoe teet la ecoordance shall revise *

• l - <

$'J*with.Section 11.3 of EFPb 20/1983 and be condseted om

- 'f

. up . - inter.aie.

. s.

l

' (of Prior to ialtial criticality, the licensee shall revise j

r the fire protecties loop flow test la accordesco with j ., .g Cheyter 5. Secties 11 of the Fire Pteocties Emedbook, leth j ..

.. p,4, Epities' published by the Natiemal Fire Protectica

. , .  ? . d i heessiaties.- .f

,. n.. K.W , ;.a . : .

. .-i ' - 2' L. < ; .. +

4 "' ' T

• N' " VUF.; Prior te startuy'atter the first refueling ostage, the

- ".' N' liesesse shall replace appresimetely 110 foot of fear-inch j ,

pipe deeding the syrinkler system in the cable spreedlag l4 a; , . - %, .

- room with sia-lack-pipe to offestively redmos the friction

! . ~

I (EP, Prior to -__ n-ai five peroest power, the licemose shall provide a history of the deviations abeerved la operaties

, 'of the diesel fire yeaps.

. ( -

, g);',3ewride the ressats of as analysis of the service waterPrior to - :

,'.!%CT.'

79E'*4.g'g'Afsystem'sosymbilitytoperformasahock a

up water supply

':r .7 g'*'*25 sr%he fire protection. This assaysis will include a

.. "? h g , *esseriytion of the surveillames precedares for the service A ,,1'gf'Qrg-45:'WC- { '.= ester pump erstam whomofmoed as a fire on protecties water

- supply, med an evaluaties limitations the service water system due to the use of these pumps as a fire water '

seyply.

0011k c-INSERT W

,. . . . , , s . . r . . w m .-~, w re.. n e . v. ; y ..-

u .o~r .. --

~, --

INSERT A The licensee shall implement and maintain in effect all provisions of the ap;, roved Fire Protection Program as described in the Updated Final Safety Analysis Report for LaSalle County i Nuclear Station, and as described in the SERs for NUREG-0519, NUREG-0519 Supplement 2, NUREG4519 Supplement 3, NUREG-0519 Supplement 5, NUREG-0519 Supplement 7, and NUREG-0519 Supplement 8, subject to the following provision:  ;

i The licensee may make changes to the approved Fire Protection Program without prior Commission approval only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. i i

8

. .? -

04/10/09 i License No. NFF-18 1

-7 .-

j

_ i I

(h) Prior to escoeding five percent power, the licensee shall provide a surveillance program for NBC staff approval to ensure operability,of the fire dampers. This progr e will incando a periodic operability test of a sample popuisties of accessible dampers.

(1) Prior to escoedlag five percent power, the licensee shall assure, la a mammer. acceptable to the NBC staff, that a fire la a single fire some will not result in the j landeesl test opening of all three high/ low pressure j interface valves between the reece.er core isolation cooling and residual heat removal systems.

(3) Prior to startup after the first refueling estage, the

~

liosasse shall provide the suppression peel level and f

,A. . temperature mesitoring instrumentation at the remote .

^

' .7 . T.ekstdows yemel which are electrically isolated frem the

(? L ir osotrol team, and assure the instrumentation are operabia '

• #~

r with the necessary surveillanee precedures is place.

'(k) - Frier te st.artup after the first refueliag estage, the liosmose shall assure, is a mammer acceptable to tho'NBC staff, that a fire is any slagle some will not affect

, a eentrol of the feel oil tremster pumpe for diesel

. . ' -' -ists "O"'and "2&". _

. .... * ( , . .- ' - ,,7 ,

(16V 1memmerial Bacarity_LEastian 121.3EL REER 82. EEE1..R.51 Am. 4e . .

4/10/89 CBCe shall fully' implement and malatain la effect all provisions of the Commission approved physical security, guard I training and qualificaties, and saieTuards n _-a _-i plass insinding ====a===ta made pursuant to provisions of the Miscellaneous Amenhests and Search metairements revisions to 10 CFR.73.55 (51 FR 27817 and 27833) and to the motherity of 10

, .CFR 50.90 and 10 CFR 50.54(p). The plans, which costala Safeymards Information protected under 10 CFR 73.21, are entitled "LaSalle County Esclear Staties. Security Flas," with

- .'- e #,k asvisaans submitted threagh June 1, 19863 "t. mantle Cosmty

17. [.J.Beslees: Power Staties Security Persommel Training and igl'OmatificatiesFlam,"withrevisionssubmittedthroughJune13, ,

.. c

,,,;g.h.1996r'and:"LaSalle Cessty Buclear y,'.E -? . -i Flea," with-revisions Power through submitted Station February Safefmares it, N '. . . '.1984./, Change made is accordanes with 10 CFR 73.55 shall he kaplemented la accordance with the schedale set forth thereia.

. (17) Initial Tmat Prepram (Emetian 14. EER. EEER 97)

The licessee shall conduct the ialtial.startup test progren (set forth im Section 14 of the licensee's Final Safety Analysis Report, as amended) without making modifications of this program unlese such modifiestloas are la accordance with provisions of 10 CFR Section 50.59. In addition, the licensee 0011k

4 1-2

- . TMFO ON LY N C) C H AtJ GES .

J 12/16/83 l 1

a l

! . ATTAG --x 1 TO ' Amatt W " -11 tHrff 2 OPenATTEC LI GIfSE EFF-18 i

i i

• This attachment identifies sertain preoperational tests, system demonstrations and other items which must be completed to the Commission's i satisf action la assordance with the operational plateaus as identified '

l below:

)'

A. The following items must be soupleted prior to proceeding to i operational mode 2 (initial criticality):

l

1. The following Prooperational Tests shall be sempleted, including l

T all rerlows:

) a) Coatsinnset monitoring System (PT-CE-201) l Post LOCA Contalment Monttoring System (PT-QB-202) f b) c) mata Steen Isolation Yalve LaaksSe Contrel System 3 (PT-MS-201A) 2 d) usin Steam Isolation Yelves and usia Steen system J Instrumentation ..(FT-us-tels)

I e) off-cas systen (PT-00-201)

I i

> f)

Weseter unairculation System (PT-ER-201) g) Post LOCA Rydrogen Recombiners (PT-TP-202) h) Transverse Incore Probe System (PT-uR-202).

2. Personnel energency ocaipment shall be installed in the taastor I

Building.

i 3. The Prooperational Test for the Coatsinnent Ventilation System -

j (PT-Vp-203) shall be soupleted, incinding all retteus prior to i

exceeding a primary system temporsture of 200er in Operational mode 1

2. .

C. The Prooperational Test for the Automatic Depressurisation System and l Maia Steen System safety /Ralief Yalves (PT-MS-1d1C) shall be 1

completed prir to exceeding a primary system pressure of 350 peig in l

Operational mode 2. All reviews of this test shall be acepleted

{

4 within one week of sempleted. testing.

D. The System Demonstration for Pipe Vibration monitoring (SD-81-201) shall be completed, including all reriows prior to exceeding 5% of rated full power operation.

e 4

4 a .

I =

- 12/1s/ss J

i  ;

i i

a  !

~# '

) 3. The felleuias itene met be sempleted fer the Fire Pretestaan program j prior to enseedias 95 of rated full pesar operations

1. The lisensee shall sendast a varies of the eseguesy of its fire l detester system lastallaties. This evalastica shnu spesifissily address the mueber and leesties of fire detesters, and weattle-i tism effeste en the ab uity of the detesters to sense a fire.

l The liseases shall initiate sempenestery measures is areas found defisiest to soeurs adequate ftre detestica sepobility. These l

seepenestery measures d al reasia in pleae until permansat

! modifiestiaans to serrest say defisionsies are made to the fire l k '

detestian system.

2. The H- shall demonstrate that Georgency Mghting smite 4

)

with at least en g-hour tattery pesar supp1r have team lastened l

end are functieaany operable la the control Asea, in thepenet, ammutary Stestrie assipasst ases et the nemete shota i

i and en a dedisated eseems reste from the conteel noen to the hesiliary Elastrie agolpaaet seem ubich util lasande tem agrees 1 deers from the control assa.

i s. The u manese shan have la ylees approved precedores defiaias esswee rentes for omstrel roen eveemstian to the remote skateses ,

pens 1.

l 4. The 11eensee shall insta n the rolley door la the Wait 2 d uary siestris aqui,a.st as

^

The 11eemose cha n have is p1ese approved H::- for - 1 l S.

l 2

override of those vestilaties deepere identified in LaSalle Omit

! 2 3c5-5-763-84 and Less11e sait 1 undificatism 5-1-1-82-S u as  ;

requiring such operation darias eartein fires.

s. The useasee shnu aset the breathing ' air supply regdremente spesified la 10 spE Se, dypendia 1, Sestaan III.E.

7, The useases shall provies a redendent fire step for the pometentions identified as amoeeding esteh1Lahed and tested emble density criteria.

8. The usense shall have la plass approved surveillense F:n ^ m for fire terrier penetraties sesis, insinding detailed essertense eriteria.

9. The base messies en the refuellag fleer du be rep 1 eses dth asesles appropriately rated.

4 .

O, -

i

. '.. l 12/14/33

- 3-s -

10. The 11sensee aball he la seaferusmas to the fire esteh qualifi-eaties requiremmate of EFFA $13.

11. The liseasee shall provide , :::' w for maistalaims the "W" and "aa" diesel e ter day tanks et the monimal futi positten.

y. The following itene mest be seaposed prior te et utep fellesing the

! first refvalias autage .

1 i 1.' The 11 senses shall aseplete all modifiestions to the firs detesties erstem identified as being required.

1 l 2. The 11eensee shall rories the performance of the fire protesties system Josher heester passes and agtensat ear eherses required j wy this series.

x e

i i -

j 4

3 7995 I

l t

(

l

• , l

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION , PAGE 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 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATIDN INSTRUMENTATION. . . . . . 3/4 3-23 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS Recirculation Pump Trip System Instrumentation. . . . . . . . . . 3/4 3-35 End-of-Cycle Recirculation Pump Trip System Instrumentation............................................ 3/4 3-39 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION............................................ 3/4 3-45 3/4.3.6 CONTROL R0D WITHDRAWAL BLOCK INSTRUMENTATIDN. . . . . . . . . . . . . . . . . 3/4 3-50 3/4.3.7 MONITORING INSTRUNENTATION Radi ation Monitori ng Instrumentation. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-57 Sei smi c Monitoring Instrumentation. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-60 Meteorological Monitori ng Instrumentation. . . . . . . . . . . . . . . . . . . . 3/4 3-63 Remote Shutdown Monitoring Ins trumentation. . . . . . . . . . . . . . . . . . . 3/4 3-66 Acci dent Monitori ng Instrumentation. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-69 l

So u rc e Ra nge Mon i to rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-72 Trave rs i ng In-co re Probe Sys tem. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-73 )

1 Deleted..................................................,.... 3/4 3-74 M

[Fi re Detecti on Instrumentation. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/43-75j De l e te d . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-81 Explexive Gas Monitoring Instrumentation. . . . . . . . . . . . . . . . . . . . . 3/4 3-82 Loo se- Pa rt De tecti on System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-85 3/4.3.8 FEEDWATER/ MAIN TUR8INE TRIP SYSTEM ACTUATION INSTRUMENTATIDN............................................. 3/4 3-86 LA SALLE - UNIT 2 V Amendsment No. 69

INDEX l

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l

SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 CORE STANDBY COOLING SYSTEM - EQUIPMENT COOLING WATER SYSTEMS Residual Heat Removal Service Water System................... 3/4 7-1 l Diesel Generator Cooling Water System........................ 3/4 7-2 Ultimate Heat Sink........................................... 3/4 7-3 3/4.7.2 CONTROL ROOM AND AUXILIARY ELECTRIC EQUIPMENT ROOM EMERGENCY FILTRATION SYSTEM.................................. 3/4 7-4 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM........................ 3/4 7-7 3/4.7.4 SEALED SOURCE CONTAMINATION..................................

- - = -

3/4 7-9

. _ - . _ G1 h_4.7.5 - W hiDlD 6 n_" E?E] & N GL M b . . .............V47-lQ

= _

l Fi re Suppres'si on iTaTer System. . . . 2. . . . . . . . . . . . . . . . . . .T. . . . . ~ 3/4 7-1 Del uge and/or Sprinkler Systems. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-14 l

C0 p Systems.................................................. 3/4 7-17 i lhELETED EireHoseStations._....................._.....................

i l

3/4 7-18) l

~

3/4.7.6 RE RATED 3SSFMB lid. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . h4 7 3/4.7.7 AREA TEMPERATURE MONITORING.................................. 3/4 7-25 1

3/4.7.8 STRUCTURAL INTEGRITY OF CLASS 1 STRUCTURES................... 3/4 7-27

3/4.7.9 SNUBBERS..................................................... 3/4 7-28 3/4.7.10 MAIN TURBINE BYPASS SYSTEM................................... ,

3/4 7-34 l

l l

i i

VIII LA SALLE - UNIT 2

2EDIX i i

mAsrs i '

1 i srcTTON , PAGE , i l

l INST}tUMENTATION (Continued) ..

MONITORING INSTRUMENTATIOd (Continued)

Meteorological Monitoring Instrumentation............... B 3/4 3-4a i

I '

Remote Shutdown Monitoring Instrumentation.............. B 3/4 3-da l Accident Monitoring Instrumentation..................... B 3/4 3-5  !

I Source Range Monitors................................... B 3/4 3-5 l Traversing In-Core Probe System......................... B 3/4 3-5

l bleted.......... Z ............. 2 .......~n........ m 3/4 375 l Fire Detection Instrumentation.......................... B 3/4 3-5 geleted.....m..... 2 ................._............... m 1/1 b L)

Explosive cas Monitoring Instrumentation................ B 3/4 3-6 Loose-Part Detection System............................. B 3/4 3-6  !

3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION l INSTRUMENTATION.................................. B 3/4 3-6 l 3/4.4 RrAc?OR COOLANT sYsTrM 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 4-2 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 i

3 / 4 . 4 . "1 MAIN STEAM LINE ISOLATION VALVES.. .............. B 3/4 4-5  !

3/4.4.8 STRUCTURAL INTEGRITY............................... B 3/4 4-5 3/4.4.> RESIDUAL HEAT REMOVAL.............................. B 3/4 4-5 l

l LA SALLE - UNIT 2 ~ XIII Amendment No. 90 l

l i

I l

INDEX i

BASES hCTION PAGE 3/4.7 PLANT SYSTEMS

' I 3/4.7.1 CORE STANDBY COOLING SYSTEM - EQUIPMENT COOLING  !

WATER SYSTEMS......................................... B 3/4 7-1 l 3/4.7.2 CONTROL ROOM AND AUXILIARY ELECTRIC EQUIPMENT ROOM EMERGENCY FILTRATION SYSTEM........................... B 3/4 7-1 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM................... B 3/4 7-1

. 3/4.7.4 , SEALED SOURCE CONTAMINATION.............................

B 3/4 7-2 3/4.7.5 T IRF ST1PPliFC% inn SYSTEM 5T..Z ........................... B 3/4 7-2 3/4.7.6 M RF RATED ASSEMRITF .'.............................. B 3/4 7-3 3/4.7.7 AREA TEMPERATURE MONITORING............................. B 3/4 7-3 .

3/4.7.8 STRUCTURAL INTEGRITY OF CLASS 1 STRUCTURES.............. B 3/4 7-3 l 1

3/4.7.9 SNUBBERS................................................ B 3/4 7-3 1 3/4.7.10 MAIN TU'RBINE BYPASS SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS.................................... B 3/4 8-1 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES................. B 3/4 B-3 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH..................................... B 3/4 9-1 3/4.9.2 INSTRUMENTATION......................................... B 3/4 9-1 3/4.9.3 CONTROL ROD P0SITION.................................... B 3/4 9-1 3/4.9.4 DECAY TIME.............................................. B 3/4 9-1 3/4.9.5 COMMUNICATIONS.......................................... B 3/4 9-1 3/4.9.6 CRANE AND H0lST......................................... B 3/4 9-1 3/4.9.7 CRANE TRAVEL............................................ B 3/4 9-2 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAGE P00L............... B 3/4 9-2 3/4.9.10 CONTROL ROD " RE.0 VAL..................................... B 3/4 9-2 3/4.9.11 RESIDUAL HEAT REMOVAL COOLANT CIRCULATION............... B 3/4 9-2 LA SALLE - UNIT 2 XV Amendment No. 69

.. ._ .-- - - -. . -. - -.-. - - . - - - . . - _ - _ _ - ~ . ..

lHDil

! LIST OF TABLES (Continued)

IABLE PKiE 3.3.7.4-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION ......... 3/4 3-67 4.3.7.4-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ......................... 3/4 3-68 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION ......:.......... 3/4 3-70 4.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ........................ 3/4 3-71 ,

FIRE DETECTION _ INSTRUMENTATION 1 .................... 3/4 3-76 [

i 3.3.7.11-1 EXPLOSIVE GAS MONITORING l INSTRUMENTATION .................................. 3/4 3-83 4.3.7.11-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ........ 3/4 3-84 3.3.8-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM .

ACTUATION INSTRUMENTATION ......................... 3/4 3-87 3.3.8-2 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION., INSTRUMENTATION SETPOINTS ............... 3/4 3-88 1

i 4.3.8.1-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS ......... 3/4 3-89 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES ... 3/4 4-10 3.4.4-1 -REACTOR COOLANT S,YSTEM CHEMISTRY LIMITS . . . . . . . . . . . . 3/4 4-13 l

4.4.5-1 PRIMhRY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM................................... 3/4 4-16 4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM WITHDRAWAL SCHEDULE .............................. 3/4 4-20 l

t l

! LA SALLE - UNIT 2 XXII Amendment No. 87

~

i l -

i

1ND.El LIST OF TABLES (Continued) -

IAB.LE E 3.6.5.2-1 ' SECONDARY CONTAINMENT VENTILATION SYSTEM

~

AUTOMATIC ISOLATION DAMPERS ....................... 3/4 6-42 A

.7.5.2-1 j dei.UGEANDSPRINKLERSYSTEpiS...................... 3/4 7-1,6 l 3.7.5.4-1,/ _ FIRE HOSE _ STATIONS ..............................._._ 3/47-h 3 . 7 . '7- 1 AREA TEMPERATURE MONITORING ....................... 3/4 7-26 4.7.9-1 SNUBBER VISUAL INSPECTION INTERVAL................. 3/4 7-33a 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE .................... 3/4 8-7b

~

4.8.2.3.2-1 BATTERY SURVEILLANCE REQUIREMENTS ................. 3/4 8-18 3.8.3.3-1 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION ......................................... 3/4 8-27 B3/4.4.6-1 REACTOR VESSEL TOUGHNESS .......................... B 3/4 4-6 5.7.1-1 COMPONENT CYCLIC OR TRANSIENT LIMITS .............. 5-6 ,

s LA SALLE - UNIT 2 XXIII .' Amendment No. 75

_haA ,- %_a_,s, - u. - - - . _ - - _ _ _ , , ._.

- e l'

l l

l

~%

~

Q v4.sau ~- _ IrretrIoNAuY LEFT suus:

6 9

a s.

O

~^ o i

i 0

i r' LA SAME - UNIT 2 3/4 3-74 heen6 ment No. 42 I

l 4 eet P y u. ?w 3-g i) .

TRUMENTATION

[

l FIRE DETECTION INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION 3.3.7.9 As a minimum, the fire detection instrumentation for each fire u l detection zone of Unit 1 and Unit 2 shown in Table 3.3.7.9-1 shall be OPERABLE.*

APPLICABILITY:

Whenever equipment protected by the fire detection instrument is required to be OPERABLE.

ACTION:

With the number of OPERABLE fire detection instruments less than the Minimu Instruments OPERABLE requirement of Table 3.3.7.9-1:

a. Within I hour, establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the primary containment, then inspect the primary containment at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the con-tainment air temperature at least once per hour at the locations f l

listed in Specification 4.6.1.7.

b. Restore the minimum number of instruments to OPERABLE status with 14 days or, prepare and submit a Special Report to the Commission pursuant to Specification 6.6.C within 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status. ,

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REOUIREMENTS 4.3.7.9.1 Each of the above required fire detection instruments which are accessible during unit operation sha11 be demonstrated OPERABLE at least once Fire detectors which per 6 months by performance of a CHANNEL FUNCTIONAL TEST performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN excee '

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.

4.3.7.9.2 The NFPA Standard 72D~ supervised circuits supervision associated with the detector alarms of each of the above required fire detection instru-ments shall be demonstrated OPEn.ABLE at least once per 6 months. Supervised circuits with detectors which are inassessible during unit operation shall be demonstrated OPERABLE during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.

w

• The normal or emergency power source may be inoperable in OPERATIONAL ONDITION 4 or 5 or when defueled.

3 3-75 Amendment No. 78 LA SALLE - UNIT 2

4 TABLE 3.3.7.9-1

1. .

FIRE ptTECTION IltSTRLSOffATION Destaself LOCATION NItIMUN INSTRUMENTS OPERA 8LE" l M f,.kelE M '

A. Unit 2 Fire Detection Instrumentation .

Cable Spreading Room 15 j 1.

(Dry Pipe Sprinkler System) l

• 9 i 2. Diesel Generator Carrider

} (0 7 Pipe Sprinkler System) __

3. Unit 0 Cables Over Lab 31 ,

l .

(Dry Pipe sprinkler system) ,

4. Diesel Generator (00001K) Room 1 l

(C0: Flooding Systan) l , ,

j . 5. Diesel Generator (20001K) Ross 1

' (CO Flooding System)

~

6. WC5 Diese1'Generster Asen 1 l

(conF1eeding Systan). .

! 7. Centrol Reen Ventilation (VC) Return '

Air Monitse j l

Systar A 1 System 8 _

1

8. Control Reen Ventilation (VC) Outside Air Nanitor System A 'I system a ,

I

s. Aemiliary Electric Equipment asas Ventilation (VE)

Astern Air Manitor '

System A 1

- System 8 1 E E TS Equissent. Train - ~-

v;: Q:L '- (1  ? 1 L

. $R:.( ...

%L? Central Been Emergency Make-up Air .

JCr. . Pf1 tar. Unit (0VC015A) 1 Ffiter Unit (OVC01st) 1

11. Control Aeon MVAC Supp1lr Air' Filter Unit (OVC01rA) 1 Filter Unit (OVCD1FB) 1

13. Auxiliary Electric Equipment Room MVAC Supply Air Filt=r LY.it (OVEDIFA) .1 .

NWAC Supply Air Filter Unit (OVE01FB) 1 m

ti sAu.E - unrr 1 v A s-7s e

i E

1l .

1 TABLE 3.3.7.9-1 (Continued) i i FIRE DETECTION INSTRUMENTATION 4

l INSTRtMENT t,0 CATION MININN INSTRLMENTS OPERA 8.E*

i g, M 5 NOM

~

f Unit 2 Fire Detection Instrumentation (Continued)

! 14. Reactor Bldg./ Containment 4 a. Refuel Floor Zone 2-26 6

. D. 84386, Fire Hazard Zone Area 'l l

b. Reactor 51ds. East, Zone 2-24 11 D. 320'6*, Fire Hazard Zone 3iiC,

c. Reactor 814g. idest Zone 2-D 9 E. 320'E*, Fire Hazard Zone 382 l '

. 4. Reactor Olds. South, Zone 2-36 25 ,

D. 78E'6*, Fira Hazard Zone 30 - , , ,

! s. Reactor 31dg. North, Zone 2-37 17 j E. 735'8", Fire Hazard Zone 30

f. Reactor 51dg. South, Zone 2-34' 23 E . 751' , Fire Hazard Zone 3E

~

g. Reactor 51dg. Herthc Zone 2-3E M

! D. 781', Fire Hazard Zone 3E l h. Containment, Zone 2-15F

E. 761'- and 777', Fire Hazard Zoos 3J

1. Containment, Zone 4-15 9 I

E . 740' and 749', Fire Hazard Zone 3J

,1 Reactor 51du., Zone 2-17 5 U. 740', F're Hazard Zone 3F

k. Reactor 814g. North, Zone 2-17F . 11 E . 740', Fire Hazard Zone 3F 1.. Reactor 81ds. SW, Zone 2-22 4 - --

E, 730'8*, Fire Hazard Zone 3G

, s. . Reactor B1dg. lei, Zone 2-22F -

6-D . 738'8"; Fire Hazard Zone 3G t- n. Reactor B1dg. South, Zone 2-32 17 U . 694', Fire Hazard Zones 3H1, 3H2, 3H3

e. Reactor 51ds. Herth, Zone 2-33 20 B. 894' , Fire Hazard Zones 3H1, 3H4, 3H5 ,

p. Reactor R1ds. South, Zone 2-30 19 E1. 573', Fire Hazard Zones 3II, 312, 3I3

g. Reactar Bldg. North, Zone 2-31 20 D. 573', Fire Hazard Zones.3II, 3I4, 315 s

r. Reactor 51d0. idest Zone 2-40 7

El. 807', Fire Hazard Zone 3C LA 5ALLE - UNIT 2 3/4 3-77 ,

~ * *

.~

i

• j .

)

i TABLE 3.3'7.9-1 (Continued) l FHE DETECTION INSTRUMENTATION i

j. mstauMENT LOCATION MImeN INSTNMENTS OPERA 8LE*

{ . - -

.NE. fJE M l Unit 2 Fire Detection Instrumentation (Continued) -

j 15. Auxiliary Building /rustine 51ds

a. Aux. 81ds. Vent Floor, Zone 2 5

! E1. 815', Fire Nazard Zone 4A

) b. Aum. 31ds. Vent Floor. Zone 2-2 9 E. 788'P , Fire Hazard Zone 48

c. Castrel Ases, Zone 2-5 17 E. 7ss', Fire H.zard Zo 4C1 .

d. Record Room. Zone 2-6 3 -

E. 758', Fire Hazard Zone 4C5

e. Reactor Prot. H Set Room, Zone 2-12 12 E1. 740', Fire Hazard Zone 404 f'. Cable Spreading Ares . Zone 2-13 13 E 7.40', Fire Nazard Zone 5A4

g. . Div.'2 SWER Ases, Zone 1-5 15 i

. ET. 731', Fire NazartZone 4E4

h. Aus. Eactric Equipment Room, Zone 2-27 12 ET. 731', Fire Nazard Zone 4E2

1. Aum. 814g. Corridor, Zone 2-3 5 E1. 73L', Fire Nazard Zone 5E13

j. Aum.' B1ds. Corridor, Zone 2-7 12 E1. 731', Fire Nazard Zone 5813 k Div. 1.5WER Room, Zone 2-9 17 E. 71&'.P , Fire Nazard Zone 4F2 .

T. Anar.- B1dg. Corridor,' Zone 2-4 S ET. 710'6*, Fire Nazard Zone SC11 m Ofv. 3 5 WOR Room, Zone 2-10 .

5 E1. 687' , Fire Nazard Zone 502

e. Auz.Blais., Zone 2-39 10 E1. 758'0", Fire Hazard Zone 4C3 ~

~

e.< Aux. 51dg. , Zone 2-38 8

. E1. 853'0", Fire Nazard Zone EE

' ' ' ~

15. OE EldB./DG B1dg. Corridor .

a. OE B1dg., Zone 2-29 14 '

- E1. 736'8*, Fire *Nazard Zones SA1, SA2 J LA SALLE - UNIT 2 1/4 3-78

/

. r. -- i . : + , , .

• l l

. TABLE 3.3.7.9-1 (Continued).

FIRE DETECTION INSTRLMENTATION INSTRUMENT LOCATION NDrMM INSTEMENTS OPERAS .E*

HI. - Id5 EE5i i

Unit 2 Fire Detection Instrumentation (Continuest)

b. DG 81dg. Corridor, Zone 2-25 3 l i E1. 710'8", Fire Hazard Zone SC11

! c. DG Bldg., Zone 2-28 11 j E. 874', Fire Hazard Zones SC3, SC4, SC5 1:r. Off Gas aut1 ding l

! a. Off Gas Guilding, Zone 1-15P 3 i E1. 710'8", Fire. Hazard Zone 10A1 -

b. ~ Off Gas Building, Zone 1-15 8 -

l' i

E1. 6908, Fire Hazard Zone 1981 ,

L Unit 1 FfM Detection Instnamentation #

Receired For Unit 2

1. Cable Spreading Soes 21 (Dry Pipe Sprinkler systan) .

~

4

2. Diesel Generator Corridor - 7 l (Dry Pipe Sprinkler System) 1 3. Diesel Generator (IDB01F) Room 2 I (COs Flooding Systm0 I -

4. Auxiliary Build *ng/ Turbine B1dg.

, f a. - Aus. B1dg. Vent Floor, Zens 1-1

• 2

! E1. 815', Fire Hazard Zone 4A .

Auz. 41d's. Vent Floor, Zone 1-2 8 l

! b.

! D. 788'8", Fire Hazard Zone 48 . _.

e. Centroi Room, Zone 1-5 15 1

' O. 788', Fire Hazard Zone 4C1 I

d Caeputer Room Zone 1-8 8 E. 788', Fire Hazard Zone 4C4

e. Reactor Prot. M-G 5et Room, Zone'l-12 12 D. 749', Fire Hazard Zone 403 ,,

f.- Cable Spreading Area, Zone 1-18 15 ,

El 749', Fire Hazard Zone 544-

g. Div. 2 SWBR Roos, Zone 1-8 15 E1. 731', Fire Hazard Zone 4E3

h. Aum. Electric Equipment Room, Zone 1-27 13 E1. 731', Fire Hazard Zone 4E1 ,

LA SALLE - UNIT 2 3/4 3-79

\

• ~.

^

i l' .

TABLE 3.3.7.9-1 (Continued) .

- FIRE DETTCTION IMsTRLMENTATION

! INSTRe p T LOCATION MDtIM M INSTRUNENTS OPERA 8.E*

j . . . . . . ~ g g g j Unit 1 Fire Detection Instrumentation Reevived For Unit 2 (Continued)

i. Aux. 51dg. Corridor, Zone 1-3 5 E1. 731', Fire Hazard Zone 5813

j. Aux. 81dg. Corridor, Zone 1-7 1Z l

j E1. 731', Fire Hazard Zone 5813

k. Div. AdBE Ross, Zone 1-9 17 l

j D . 710'8*, Fire Hazard Zone 4F1 .

! 1. Aum. B14g. Carrider, Zone 1-4 -

,- t E . 710'6", Fire Hazard Zone SC11 j 5. OE 81ds./DG B1dg. Corrfder 4

i s.. 08 Bidg., Zone 1-29 17 E1. 73&'P, Fire Hazard Zones 7A1, 7A2, 7A3 4

b. OS Eldg. Corrider, Zone 1-25 . 3 l -

D. 722'F, Fire Hazarmt Zone SC11. .

l

! c. X Bids., Zone 1-28 15 1

D. 574', Fire Hazard Zones 7C4, 7C5, 7C5

~

! 5. Reactor Sids.

i s. Refuel Floor, Zone 1-25 6 j U . 843'8", Fire Hazard Zone Area 1

b. Reactor 814g. EastiZone 1-24 11 l l

i E. 820'8*, Fim Hazard Zone 2B1 l

• 1 1 .  ;

1 1 . . , . 2.s A --

l f

.; ..: .... P.5; D..,.

.-[? '. '% ..~'*ji l

~.

j -

..?- TABLE NOTATION i .

"The firar detection instruants located within the primary containment are not

required to be OPERABLE during the performance of Type. A Containment Leakage j

{RataTests. .

1

. 2. ...

l . .. ,.

' s. .

1 -

LA SALLE - MIT Z 3/4 3-30 3

L7.5~ M 17,6 TNTEWTIONNLLY SYSTEMS LEFT BLAMK. Pap M 7-12 3/4.7.5 FIRE SUPPRESSION SYSTEMS Nh * *-

FIRE SUPPRESSION WATER SYSTEM [

LIMITING CONDITION FOR OPERATION 3.7.5.1 The fire suppression water system shall be OPERABLE

• with:

a. Two OPERABLE fire suppression diesel driven fire pumps, each with a capacity of 2500 gpm, with their discharge aligned to the fire j I

suppression header,

b. An OPERABLE flow path capable of taking suction from the CSCS water f tunnel and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves, the last valve ahead of the water flow alarm device on each sprinkler, hose standpipe, and the last valve ahead of the deluge valve on each deluge or spray system required to be OPERABLE per Specifications 3.7.5.2 and 3.7.5.4. j APPLICABILITY: At all times.  !

l ACTION:

i With one fire pump and/or one water supply inoperable, restore the i

a.

inoperable equipment to OPERABLE status within 7 days or, prepare and submit a Special Report to the Commission pursuant to Specifi-  !

cation 6.6.C within the next 20 days outlining the plans and procedures to be used to restore the inoperable equipment to OPERABLE status or to prov.ide an alternate backup pump or supply.

The provisions of Specification 3.0.3 are not applicable.

b. With the fire suppression water system otherwise inoperable:

1. Establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and ,

2. Prepare and submit a Special Report in accordance with Specification 6.6.C; a) By telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b) Confirmed by telegraph, mailgram or facsimile transmission i no later than the first working day following the event, and f c) In writing within 14 days following the event, outlining the action taken, the cau,e of the inoperability and the plans and schedule for re storing the system to OPERABLE status.

• The normal or emergency power source may be inoperable in OPERATIONAL CONDITION 4 or 5 or when defueled. _

. LA SALLE - UNIT 2 3/47-ll(Me Amendment No. 78

. *is 3/'l 7-25) y 1

~

f, PLANT SYuu6 --

SURVEILLAM REQUIREMDffS i . . _

i j 4.7.5.L1 The fire suppression water system shall be demonstrated OPERABLE:

1 = *t least once per 31 days by verifying that each valve Omanush_- __

-"" operated, or automatic)~ in the flow path is in its correct position.

b. At least once per 12 months by cycling each testable valve in the

- flow path through at least one completa cycle of full travel.

i c. At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system throughout its operating

!. . and:

Verifying that each automatic valve in the flow path actuates l L to its correct position, ,

j . L Verifying that each fire suppression pump develops at least -

1 3750 gpm at a systas head of 205 feet, -

1

] 3. Cycling each valve in the flow path that is not testable during

plant operation through at least one completa cycle of full

trev.i, and 3

j 4. Verifying that each fire suppression pep starts sequentially j

to maintain the fire suppression water system pressure greater than or equal to 128 psig.

d. At least once per 3 years by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Pr wion Association. l 4.7.5.L1 Each diesel-driven fire suppression pump sht ' a demonstrated OPERABLE:

i

a. At least. once per 31 days by: )

-~

L Verifying'the fuel day tank contains at least 130 gallons of fuel.  !

. 8  ; ...

..E Starting: .  ;

.,. a) The fuel transfer pump and transferring fuel from the ,

. storage tank to the day tank. l b) The diesel-driven pump from ambient conditions and operating for at least 30 minutes on recirculation flow. ,

e

'LA SALLE - UNIT 2 ,

3/4 7-12

1 . ,,

J

) s x

! PUWIT SYSTEMS

. SullVEIL.LAllCE REDUIRBeff5 (Continued) 1 .

. h. At least once per 92 days by verifying tipt a sample of diesel fuel

. from the fusi storage tank, obtained in accordance with ASTM-0270-75, is within the acceptable limits specified in Table 1 of ASTM Og75-77 when checked for viscosity, water and sediment.

c. At least once per la months, duMag shutdown, by subjecting the

diesel to an inspection in accordance with procedures prepared in

] conjunction with its manufacturer's recommendations for the class of j servica.

i i 4.7.5.1.3 Each diesel driven fire pump starting 24-volt kii.ri bank and charger i shall be demonstrated OPERABLE: .

l a. At least once per 7 days by veMfying that:

.1. The electrolyte level of each pilot cell is above the plates, l 2. The pilot cell specific gravity, corrected to 77'F, is greater

! than er equal to L200, and .

i 1 3. The everall bettery voltags is greater then or equal to 24 volts.

a

6. At least once per 92 days by veMfying that:

j 1. The weltage of each connected battery is greater then or equal

! to 25 volta under flest charge as=8 has not decreased more than LS volts from the value abeervw duMng the oMginal test,

2. The specific gravity, corrected to 77'F, of each connected cell is gmatar than er egus1 to L200 and has not decreased more then 0.05 from the value absorved duMng the previous test, and

3. The electrolyte level of each connected cell is above the plates.

c_ . At least once per 18 months by verifying that:

' 1.~.The bettery shaus ne visual indication of physicai damage or 7

. - shmom al detaM oration, and

2. Battery taminal connections are clean, tight, free of corrosion and costed with anti-corrosion material.

l l

i l

l LA SALLE - UltIT 2 ,

3/4 7-13

LANT SYSTEMS DELUGE AND/OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.5.2 The deluge and sprinkler systems of Unit I and Unit 2 shown in Table 3.7.5.2-1 shall be OPERABLE.*

APPLICABILITY: Whenever equipment protected by the deluge / sprinkler systems are required to be OPERABLE.

ACTION:

a. With one or more of the deluge and/or sprinkler systems shown in Table 3.7.5.2-1 inoperable, within I hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol. Restore the system to OPERABLE status within 14 days or, prepare and submit a Special Report to the Commission pursuant to Specification 6.6.C within the next 30 days outlining the action taken, the cause of the inoper-ability and the plans and schedule for restoring the system to OPERABLE status.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REOUIREMENTS 4.7.5.2 Each of the above required deluge and sprinkler systems shown in Table 3.7.5.2-1 shall be demonstrated OPERABLE: {

a. At least once per 31 days by verifying that each valve, (manual, l power-operated or automatic) in the flow path is in its correct  !

position,

b. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.

l

c. At least once per 18 months:

1. By performing a system functional test which includes simulated automatic actuation of the system, and:

a) __ Verifying. that the automatic valves in the flow path actuite to their correct positions on a test signal, and b) Cycling each valve in the flow path that is not testable durino plant operation through at least one-complete cycle of full travel.

• The normal or emergency power source may be inoperable in OPERATIONAL CONDITION 4 or 5 or when defueled.

LA SALLE - UNIT 2 3/4 7-14 ,

Amendment No. 78

~

=_-

LAffT SYSTBt5 SURVEILLw esmIRDerTS (Continued)

2. By a visual inspection of the dry r,ipe sprinkler and deluge

' headers ta veMfy their intagMty, and

3. By a visus 1 inspection of each deluge nozzle's spray area to verify that the spray pattern is not obstructed.

d. At least once per 3 years by performing an air flow test through each open head spray and spMnkler header and veHfying each open head deluge and spHirjer nozzle is unobstructed.

g .

I .

i 1

e b .

,e P.

• ,a 4

4 g

LA 5ALLE - LBIIT 2 3/4 7-15

'. l l

l

.- l'.T .. TABLE 3.7.5.2-1 _ _ . . _ .

DELUBE AIG SPRINELER SYSTEMS l

Elevation Fico Zone l

• gggggn i A. Unit 2.0elues and Sorinkler Systans

1. Diesel fuel storece tank (00001T) room 574'0" 7C3

2. Diesel fuel storage tank (200017) room 574'0" SCZ

3. HPC5 diesel fuel storage tank (200027) room 674'0" SC1 .

)

WCS diesel day tank (200047) ream 710'r 883 j 4.

5. Ofesel generator day tank (000027) room 710'r 7m Diesel generater day tank (200027) roes 710'r ass-8.

Cable spreading room 749'0" 402 7.

Staney gas treatment system equipment train 420'8" 231 -

8.

(IVS 015)* ,

S. Centrei roes emergency makeup filter 7as's" 45 unit (OWC' 015A)*

10. Centrol veen emergency maksep filter 736'8" 45 unit (OWC 015B)*

11. Auxiliary eleci M equipment room WAC supply 785'6" 48 air filter (OVE Ga)"

12. Auxiliary electric equipment roes WAC supply 785'6" 48 air filter unit (OVE 01FB)"

13. Centrol roes WAC supply air filter 736'5" 45 unit (OVC 01FA)*

14. Centrol team WAC supply air filter 736'6" 45 unit (OWC.01FB)* ,

1sf stoney gas treatment system equipment 420's" sal

trate (2We01s)= . ,

18. Cable arees above latereterfes, Unit 0 710'8" 4F3

17. Diesel generator corrider 710'6" SC11 ,

S. Unit 1 Delues and Sorinkler Systans Roouired For Unit 2

1. Diesel fuel storage tank (20001T) room 574'0" 7C2 1 Diesel generater day tank (200027) room 710'r 7s5

2. 743'0" 401

3. Cable spreading room

4. Diesel generator corrider 710'6" SC11 "5ervet11ance Requirements 4.7.5.Lc.1 (a) and (b), 4.7.5.2.c.3 and 4.7.5.2.d are not applicable. Surveillance Requirement 4.7.5.2.c.2 is not applicable ta etsing within the charcoal beds.

LA SALLE - LNEI7 2 3/4 7-15

ANT SYSTE CO SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.5.3 The following low pressure CO2 systems of Unit I and Unit 2 shall be OPERABLE.* .

a. Division 1 diesel generator 0 room.

b. Division 2 diesel generator 2A room.

c. Division 3 diesel generator 2B room.

d. Unit 1 Division 2 diesel generator IA room.

APPLICABILITY: Whenever equipment protected by the low pressure CO2 systems is required to be OPERABLE.

ACTION:

a. With one or more of the above required low pressure CO2 systems inoperable, within I hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant i systems or components could be damaged; for other areas, establish an hourly fire watch patrol. Restore the system to OPERABLE status within 14 days or, prepare and submit a Special Report to the Com-mission pursuant to Specification 6.6.C within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule .for restoring the system to OPERABLE status.

b. The provisions of Specification 3.0.3 are not applicable. J SURVEILLANCE REQUIREMENTS I

4.7.5.3 Each of.the above required low pressure CO2 systems shall be demonstrated OPERABLE:

a. - At least once per 7 days by verifying CO2 storage tank level to be greater than 50% full and pressure to be greater than 290 psig, and

b. At least once per 31 days by verifying that each valve (manual, power operated, or automatic) in the flow path is in the correct position.

c. At least once per 18 months by verifying:

1. The system valves and associated motor operated ventilation dampers actuate, manually and automatically, upon receipt of a simulated actuation signal, and

2. Flow from each nozzle during a " Puff Test."

f

• The normal or emergency power source may be inoperable in OPERATIONAL CONDITION 4 or 5 or when defueled.

i LA SALLE - UNIT 2 3/4 7-17 Amendment No. 78

NT SYSTEMS FIRE HOSE STATIONS g ING CONDITION FOR OPERATION 3.7.5.4 The fire hose stations of Unit I and Unit 2 shown in Table 3.7.5.4-1 l

shall be OPERABLE.

Whenever equipment in the areas protected by the fire hose APPLICABILITY:

stations is required to be OPERABLE.

ACTION:

a. With one or more of the fire hose stations shown in Table 3.7.5.4-1 i inoperable, route an additional fire hose of equal or greater l diameter to the unprotected area (s)/ zone (s) from an OPERABLE hose '

station within I hour if the inoperable fire hose is the primary means of fire suppression; otherwise, route the additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Restore the inoperable fire hose station (s) to OPERABLE status within 14 days or, prepare and submit a Special Report to the Commission pursuant to Specification 6.6.C within the next 30 days outlining the action taken, the cause of the l inoperability and the plans and schedule for restoring the system to , )

OPERABLE status.

b. The provis' ions of Specificatten 3.0.3 are not applicable. )

i SURVEILLANCE RE0VIREMENTS 4.7.5.4 Each cf the above required fire hose stations shown in Table 3.7.5.4-1 shall be demonstrated OPERABLE:

a. At least once per 31 days by a visual inspection of the fire hose stations accessible during plant operation to assure all required equipment is at the station.

b. At least once per 18 months by:

1. Visual inspection of the fire hose stations not accessible during plant operation to assure all required equipment is at the station.

2. Removing the hose for inspection and reracking, and

3. Inspecting all gaskets and replacing any degraded gaskets in the couplings.

c. At least once per 3 years by partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.

i d. Within 5 years and between 5 and 8 years after purchase date and at least every 2 years thereafter by conducting a hose hydrostatic test I

at a pressure of 150 psig or at least 50 psig above the maximum fire -

l main operating pressure, whichever is greater.

I' l LA SALLE - UNIT 2 3/4 7-18 Amendment No. 78

! .~~ '

u . a. ..

..4_, >.. tig: c . c... .

!t 4

i t

I.

i i

i TABLE 3.7.5.4-1

} ~~ ~

FIN DOSE STAT 10fts

- ~ ~ ~ ~ - ~ ~ ' ~ "-~

MM M E W WD' 't i A. Unit 2 Fire Noso Stations .

1. Aree 1 Arme 1 843'6" F 301

/ FB. 302__

j p F 304 i' F 305 a'

Zone 34 832'0" F306 5 2. Zone 3A Zone M 1 830'8" FB 308

3. Zone M1 F 309 1

. . FM .

Zone 382 ' Zone M2 .830'6" .

FB 307

.4. . .

3 FB 310 4

5. Zone 3C Zone 3C -

807'0" F 312 j F 313 l -

< F 314 -

~<

5. Zone 30 Zone 30 - 735'S* FB 315

' F 315

^ PB 317 .

FM

~

7. Zone M Zone 3E 781'0" F 319

! F 32tr ,

F 321 l

' F 322 Zone 3F 740'0" PB 323

8. Jane 3F F 324 Zone 3J

. Zone at F 325 F 326

- . FB 327

-r Zone M 710'8" F 328

9. Zone M F 329

. a

~

F 331 F 332-F 453 Zone 3N1 GM' 8" F 333

18. Zone 3H F 334

'Zane 3H2 F 335 Zone 3NS Zone 3H4

,F 335 .

. F 337 Zone 3N5 F 338 F 339 l

- F 340 LA siu.E - unti 2 3/4 7-19

4

.k,:21. . ~~ ..;. .% -.  !

.:: .. : ; . .a< i. .

i i

i 4

]

~

! TABLE 3.7.5. 41 (Continued) <

i 4 .

FIRE HOSE STATIONS l

l 4

i l M PR TIETED ARIA M IDENTIFICATTON Hose RACK 1

l: _ ,_

unit 2 Fire Mose Statio'ns (Continued) ,

!

• 22. Zone 3 G Zone 3 G 573'4" El 341. .

I.

F5 344 *

! Zans 312 Zone 313 .F5 344

! Zone 314 PB 344 I

' Zone 315 .

Zone 315

12. Zone 312 Zone 311 -573'4" F 342 i 13. Zone 3D Zone SI2 673'4* F 343 l i '

14. Zone 314 Zone 314 573'4" '

F 347 l l

15. . Zone 3IS Zone 315 573' 4" F 346 .

15. Zone 4A Zone 44 815'0" F5 349 l -

F 350 .

1 i '

' F 388 i

! 17. Zone 48 Zone 48 785'5' F 351 FB 352 F 353 I

18. Zone 4C3 Zone 4C1'

'~

758'0" FB 354

. and 5A3 Zone 5A1 FR 372 Zone 4C3 FB 451 Zone 543 FB 373 i

Zone 4C5 ~ ~

FB 374 F5 370 F 371

._. 75 375 F 377 i

! FB 452 I

IS. Zana 544' Zone 401 749'0* FB 454 i

l ~

. ' Zone 404_ - t " ' :' . , f.- FB 405 - - -

j ,

Zone 544 -

. an. Innerser. Zone ast3 731'n35' Ft.355 l . an. = = Z.no m 3 .

~

Zone 4EZ i Zone 4E4 I 21. Zone SC11' Zone EC11 ...' .-710 t E".; ..

~

. F5 357 Zane 881, att, 883- F 354 l i

1 Zone m e, FE 385 Zone 4F2, 4r3 Fa 3s7

) rs 3as

- FB 390 F5 391 4

l ~ .

A J

j u saur - wrr z 3/4 7-20 i

2 l i

j TABLE 3.7.5.4-1 (Continued)'

i FIRE HOSE STATIONS '

j LOCATION PROTECTED AREA ELEVATION IDENTIFICATION HOSE RACK l l Unit 2 Fire Hose Stations (Continued) l 22. Zone 8A1 Zone SA1 736'6" F 362 j 23. Zone 8A2 Zone SA2 -

736'6"

' F 363

24. Zone 8C3 Zone 8C3 673'0" -

FB 365 Zone 8C1 j .

8C5

25. Zone 8C4 Zone 8C4 673'0" F 366 l Zone 8C2

! 26. Zone 6E Zone GE 663'0" F 359 <

i F 360 .

F 399 F 403

' F 404 B. Unit 1 Fire Nose Stations Reevived For Unit 2 -

j g

1. Area 1 Area 1 843'6" F 101 FB 102 -  !

l^

F 103

F 1M F 105 j 2. Zone 281 Zone 2B1 820'6"

~ FB 108 l i F 109 l F 111 '

l -

3. Zone 4A Zone 4A 815'0" F 150 j 4 FB 149

4. Zone 48 Zone 48 786'6" F 151 FB 152

[ F 153 1 5. Zone 4C2 Zone 4C1 768'0" F 154 i and 5A3 Zone 4C2 i

FB 175

' Zone 4C3 FB 176 1

Zone 4C4 l Zone 4C5 i ' 6. ' Zone 544 Zone 5A4 749'0" FB 248 -

I Zone 401 FB 253 Zone 402

Zone 403 i 7. Zone 5813 Zone 5813 731'0" FB 250

' Zone 521 FB 155 i Zone 4E3 FB 185 i 'Ione 4E2 Zone 4E1 .

)

LA SALLE - UNIT Z 3/4 7-21 Amendment No.14

4 l l a  :

. i 1

i ,

i l i . ~

i '

1 j .

TABLE 3.7.5.4-1 (Continued) l FIRE HD$f STATIONS ,

1 M

2 i

r M -- .

P W ICTED AREA IDENTIFICATION MOSE RACK, j 1

~' -

Unit 1 Fire Hose Stations Reauired for Unit 2 (Continued) ~ - -

l S. Zone 7A3 Zone 7AS 738'S' F 153 i Zone 7AZ

! 9. Zone Scal Zone SC11 710'8" FB 157 i Zone 4F1 FB 191 l Zane 73Z FB 154 i

Zone 755 FB 192

! Zone 733 FB 155

} Zone 736

10. Zone 7C5 Zone 7CE '

$73'0"

~

FB 158 i and 7CS Zone 7C3 '

F 158 i

4 Zane 7C5

• Zane 7CE -

% 9 j u l

l i

i

)

l

. . y;

~ '"

9 , e e eg, e ss

. 8 m

e #

LA SALL.E - UNIT Z 3/4 7-ZZ

3 NT SYSTEM [

3 /4.7.6 FIRE RATED ASSEMBLIES LIMITING CONDITION FOR OPERATION

)

3.7.6 All fire rated assemblies, including walls, floor / ceilings, cable tray enclosures and other fire barriers separating safety-related fire areas or i separating portions of redundant systems important to safe shutdown within a i fire area, and all sealing devices in fire rated assembly penetrations (fire j doors, fire windows, fire dampers, cable and piping penetration seals and i ventilation seals) shall be OPERABLE.

j APPLICABILITY: At all times.

i ACTION:

a. With one or more of the above required fire rated assemblies and/or j sealing devices inoperable, within I hour either establish a con-i tinuous fire watch on at least one side of the affected assembly (s)

! and/or device (s) or verify the OPERABILITY of fire detectors on at least one side of the inoperable assembly (s) and/or sealing device (s) and establish an hourly fire watch patrol. Restore the j

inoperable fire rated assembly (s) and/or sealing device (s) to OPERABLE status within 7 days or, prepare and submit a Special i

Report to the Commission pursuant to Specification 6.6.C within the

• next 30 days outlining the action taken, the cause of the inoperable fire rated assembly (s) and/or sealing device (s) and plans and i

schedule for restoring the fire rated assembly (s) and/or sealing j device (s) to OPERABLE status.

b. The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE RE0VIREMENTS l 4.7.6.1 Each of the above required fire rated assemblies and sealing devices shall be verified to be OPERABLE at least once p.er 18 months by performing a i

visual inspection of:

i

a. The exposed surfaces of each fire rated assemblies.

4

b. Each fire window / fire damper and associated hardware.

At least 10 percent of each type of sealed penetration. If apparent c.

changes in appearance or abnormal degradations are found,.a visual inspection of an additional 10 percent of each type of sealed penetration shall be made. This inspection process shall continue until a 10 percent sample with no apparent changes in appearance or abnormal degradation is found.

3/4 7-23 Amendment No. 78

$ LA SALLE - UNIT 2

t '

n 1 i

- mm .

\

1

! SURVEILLANCE REQUIREMENTS (Continued)

• 1 1 4. 7. 6. 2 Each of the above required fire doors shall be verified OPERABLE

try:  !

I a. Verifying the position of each closed fire door at least once

{ per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

! b. Verifying that doors with automatic hold-open and release mechanisms i are free of obstructions at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

I

! c. Verifying the position of each locked closed fire door at least l once per 7 deys.

d. Verify the OPERASILITY of the fire door supervsion system by

performing a CHANNEL RMCTIONAL TEST at least once per 31 days.

e. Inspecting the automatic hold-open, release and closing mechanism and latches at least once per 6 months.

i s.. -

1 1

0 0

. e 0

e e_- . .,

. 9

,.- , .s *

..-7 .

W8 O

O 4

e d

G t

LA SALLE - UNIT 2 3/4 7-24 -

INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.7.5 ACCIDENT' MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an accident. This capability is con-sistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Tern Recommendations".

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 and shutdown. At these power levels, reactivity additions should 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 TRAVERSING IN-CORE PROBE SYSTEM The OPERABILITY of the traversing in-core probe (TIP) system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux dis-tribution of the reactor core.

The specification allows use of substituted TIP data from symmetric channels if the control rod pattern is symmetric since the TIP data is adjusted by the dependent bias.The plant sourcecomputer of datatofor remove machine may the substitution dependent also be and a power level 3-dimensional BWR core simulator calculated data set which is normalized to available real data. Since uncertainty could be introduced by the simulation and normalization process, an evaluation of the specific control rod pattern and core opetating state must be performed to er.sure that adequate margin to core operating limits is maintained. -

3/4.3.7.8 DELETED f 3/4.3.7.9 EIn U m rn M M TDM M ATT0lO PERABIL11Y oT the fire detection instrumentation ensures that adequatei  %

arning capability is available for the prompt detection of fires. This i l

capability is required in order to detect and locate fires in their.early  !

Prompt detection of fires will reduce the potential for damage to stages.

safety-related equipment and is an integral element in the overall facility ,

i fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, increasing the frequency of fire watch patrols in the affected l areas is required to provide detection capability until the inoperable j instrumentation is restored to OPERABILITY.;

i 3/4.3.7.10 DELETED l

l

. LA SALLE - UNIT 2 B 3/4 3-5 Amendment No. 69 l

-i ~

J l ,

I 4

1 j '

3 PUUIT SYSTEMS BASES j

l 3/4.7.4 SEA Lan SOURCE CONTAMINATION -

i The limitations on removable contamination for sources requiring leak j testing, including alpha emmitters,~1s based on 10 CFR 70.39(c) limits for l plutonium. This limitation will ensure that leakage from byproduct, source, j and special nuclear material soumas will not exceed allowable intaka values.

Sealed sources are classifi.ed into three groups according to their use, with

! surveillance requirements commensurate with the probability of damage to a j source in that group. Those sources which are frequently handled are required

! ta be tastad'more oftan than those which are not. Sealed sources which are .

3 continuously enclosed within a shielded mechanise,1.e., sealed sources within i

radiation monitoring or baron measuring devices, are considered to be stored and need not be tastad unless they are removed from the shielded mechanism.

l' 3/4.7.5.Ess L;;rwin. w U.db.Ud m 5 OPERABILITY of ther fire suppression systems ensures that adequata re suppressier capability is available to confine and extinguish fires ng in any portion of the facility where safety related equipment is located. The fire suppression systas consists of the water system, deluge and/or sprinklers, CD, systmas, and. fire hose stations. The collective capatdlity of the fire suppression systems is adequata to minimiza potential i

damage to safety related equipment and is a major element in the facility fire protection program.

i In the event that portions of the fire suppression systans are inoperable, .. -

J alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.

i When the inoperable fire fighting equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an l alternata means of fire fighting than if the (noperable equipment is the 4

orimary means of fire suppression.

t The surveillance requiremrits provide assurance that the minimum '

OPERASILITY rMuirements of the fire suppression systans are met.

l

. In the event the fire suppression water systas becomes insperable, immediata corrective amasures must be taken since this systam'provides the i

major fire suppression capability of the plant. The requirement for a j

twenty-four hour report to the Commission provides for prompt evaluation of j

the acceptability of the corrective measures to provide adequate fire j ression capability for the continued protection of the nuclear plant.

1 i

4 LA SALLE - UNIT 2 B 3/4 7-2

. .. . _. ............5.

~.

Pt.AN1' SYSTDt5 magsc 3/4.7.5 Giui RAfffl A--- i m OP6 ABILITY of the fire barriers ~and barrier i bi. ionstheensure]j fire damage will be limited. These design features sinimize sibility of aextinguishment.

ion and single fire involving more than one fire area prior toThe fire barriers, fire bar Por conduits, cable trays and piping, fire windous, fire dampers, and fire >

1 egg _ men nertedically inspected ta verify their OP9tARILITYg

)

3/4.7.7 ' AltEA TBWWATUltE ICIInvaina ,

The area temperature limitations ensure that safety-related equipment will not Da subjected to temperatures in encass of their environmental qualification tamperatures. Esposure to excessive tamperatures may degrada equipment and can causerless of ita OptRASILITY. The tamperature limits include allemance for an instrument. error of a 7'F.

3/4.7.8 STituCTURAL ikiusuTC 0F CLASS I STituCTultES .

In order to assure that settlement does not encoed predicted and allowable settlement values, a progrant has been established to conduct a survey at the site. The allouable total differential settlement values are based on original settlement predictions. In establishing these tabulated values, an assumption is made that pipe and conduit connection have been designed to safely withstand the stresses which would develop due to total and differentia,1 settlement.

3/4. T.9 SIRBBBtf All snubbers are required OPERA 8LE to ensure that the structural integrity of the Reactae Caelant System and all other safety related systems is maintained during and following a seismic or other event initiating (ynamic loads. Snuebers excluded from this inspection program are.these installed on nonsafety-related _ ..

systems and them only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related systas.

Snubbers are classified and grouped by design and manufacturer but not by size. For summple, mechanical snubbers utilizing the same design features of the 2 kip,10-kip, and 100-kip capacity manufactured by Caguny "A" are of the sama type. The same design mechanical snubbers manufactured by Company "B" for the purpose of this Technical Specification would be of a different type, as would hydraulic snubbers from either manufacturer.

LA 5ALLE - UNIT 1 8 3/4 7-3 1

l l

! ADMINISTRATION CONTROLS l

! 1. At 1. east one licensed Reactor Operator 'shall be in the control room i l when fuel is in the reactor. In addition, while the reactor is in l

OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior i Reactor Operator who has been designated by the Shift Supervisor to i assume the control room direction responsibility shall be in the i Control Room.

! 2. A radiation protection technician

• shall be on site when fuel is in j the reactor.

! 3. All CORE ALTERATIONS shall be observed and directly supervised by i either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities i Dqdtk. during this operation.

l 4. f site Fire Brigade of at least 5 members shall be maintainad onsite

at all times". The Fire Brigade shall not include the Shift Supervisor ,

,the Station Control Room Engineer and the 2 other members of the mini- l

! mun shift crew necessary for safe shutdown of the unit and any person-qwl required for other essential functions durina a fire ==araency

5. The Onsite Nuclear Safety Group (0NSG) shall function to examine i unit operating characteristics, NRC issuances, industry advisories,

! Licensee Event Reports and other sources of plant design and operat-l ing experience information, including plants of similar design,-

which may indicate areas for improving unit safety. The ONSG shall be composed of at least three, dedicated, full-time engineers of i g multi-disciplines located on site and shall be augeanted on a part-j time basis by personnel from other parts of the Commonwealth Edison

Company organization to proyide expertise not represented in the i group. The 0NSG shall be responsible for maintaining gurveillance l

of unit activities to provide independent verification that these  !

i activities are performed correctly and that human errors are reduced

! as much as practical. The ONSG shall make detailed recommendations i for revised procedures, equipment modifications, maintenance activi-

! ties, operations activities or other means of improving unit safety ,

j to the Safety Assessment Manager and the Station Manager.

! 6. The Station Control Room Engineer (SCRE) may serve as the Shift

Technical Advisor (STA) during abnormal operating and accident condi- ,

j tions. During these conditions, the SCRE or other on duty STA shall  !

provide technical support to the Shift Supervisor in the areas of I themal hydraulics, reactor engineering and plant analysis with regard l

to the safe operation of the unit. .

l f st i The radiation protection technician and Fire Brigade esaposition may be less j than the minimum requirements for a period of time not to exceed two hours in

order to accommodate unexpected absence provided immediate action is taken to j fill the required positions.

1. Not responsible for sign-off feature.

4 j

s- -

!' 6-2 Amendment No. 62 l LA SALLE - UNIT 2

. . _ . _ -_ _ _ _ _ . _ - _ - ___ . __ _ -. _ _._ . .y_ _. _ _ . - _ _ _ -

1 i

UNIT 2 LICENSE CONDITIONS - 2.C.(15)

Fire Protection Proaram (Sei lion 9.5. SER. SSER #2 SSER #3. SSER #5. SSER #7. SSER #8 (NUREG-051911.

~

(a) The licensee shall maintain in effect all provisions of the approved fire protection program.

This License Condition is presently in effect, and will be superseded upon issuance of the standard license condition in accordance with the guidance of GLs 86-10 and 88-12.

(b) Prior to initial criticality, the licensee shall replac* the B diesel fire pump engine and perform a test in accordance with Sections 11-2.3 and 11-2.5 of NFPA-20/1983.

This License Condition was tracked as Open item (374/81-00-41(DPRP)). The SSER, Supplement 8, page 1-2, states that the B diesel fire pump engine was replaced and tested in accordance with Sections 11-2.3,11-2.4, and 11-2.5 of N'*9A-20/83.

This Open item was closed by inspection Report 50-374/84-05(DPRP) dated 4/18/84.

i (c) Prior to initial criticality,the licensee shall revise the fire protection loop flow test in accordance with Section 11.3 of NFPA-20/1983 and be conducted on 18-month intervals.

This License Condition was tracked as Open item (374/81-00-42(DPRP)). The SSER, Supplement 8, page 1-2, states that the fire pump surveillance tests are in accordance with Section 11.3 of NFPA-20/1983 and will be conducted on 18-month intervals.

This Open item was closed by inspection Report 50-374/84-05(DPRP), dated 4/18/84.

Note: the above stated " loop flow test" is an error in nomenclature, it is actually a fire protection pump flow test in accordance with Section 11.3 of NFPA-20/1983, which is conducted on 18-month intervals.

(d) Prior to initial criticality, the licensee shall revise the fire protection loop flow test in accordance with Chapter 5, Section 11 of the Fire Protection Handbook,14th Edition published by the National Fire Protection Association.

This License Condition was tracked as Open item (374/81-00-43(DPRP)). The SSER, Supplement 8, page 1-2, states that the fire protection loop test has been revised in accordance with Chapter 5, Section 11 of the Fire Protection Handbook,14th Edition published by the National Fire Protection Association.

This Open item was closed by inspection Report 50-374/84-05(DPRP), dated 4/18/84.

(e) Prior to startup after the first refueling outage, the licensee shall replace approximately 110 feet of four-inch pipe feeding the sprinkler system in the cable spreading room with six-inch  !

pipe to effectively reduce the friction loss.

This License Condition was tracked by Open item (374/81-00-44(DPRP)). The Open item )

was closed by inspection Report 50-374/84-05(DPRP), dated 4/18/84.

I

. - - - - - _ - . - _ _ _ . _ - . ~ . - - - - - - . _ _ _ - -

1 UNIT 2 LICENSE CONDITIONS - 2.C.(15)(continued)

(f) Prior to exceeding five percent power, the licensee shall provide a history of the deviations <

observed in operation of the diesel fire pumps.

! This License Condition was tracked by Open item (374/81-00-45(DPRP)). A letter to Mr.

i Harold R. Denton (NRC) from C.W. Schroeder (Licensee), subject, "LaSalle County Station Units 1 and 2, Deviation Report History for LaSalle County Station's Diesel Fire Pumps from April 17,1982 to January 1,1984, NRC Docket Nos. 50-373 and 50-374", dated February 9, 1984, transmitted the history of deviations observed in operation of the diesel fire pumps.

! The SSER, Supplement 8, page 1-2 states that this License Condition is satisfied.

This Open item was closed by inspection Report 50-374/84-05(DPRP), dated 4/18/84.

)

j (g) Prior to exceeding five percent power, the licensee shall provide the results of ar, analysis  !

l of the service water system's capability to perform as a backup water supply for the fire . '1

! protection. This analysis will include a description of the surveillance procedures for the service water pump system when used as a fire protection water supply, and an evaluation of limitations on the service water system supply due to the use of these pumps as a fire j water supply.

This License Condition was tracked by Open item (374/81-00-46(DPRP)). Supplement 8 of the SER, pages 1-2 and 1-3 indicates resolution of this License Condition. The NRC staff's review is provided in Section 9.5.1.1 of this Supplement.

This Open item was closed by inspection Report 50-374/84-05(DPRP), dated 4/18/84.

(h) Prior to exceeding five percent power, the licensee shall provide a surveillance program for NRC staff approval to ensure operability of the fire dampers. This program will include a periodic operability test of a sample population of accessible dampers.

This License Condition was tracked by Open item (374/81-00-47(DPRP)). Supplement 8 of the SER, Section 9.5.2.2, page 9-4, provides the NRC staff's review of the surveillance program submitted by LaSalle Station in a letter dated March 15,1984. This submittal i satisfies this License Condition. I This Open item was closed by inspection Report 50 374/84-05(DPRP), dated 4/18/84.

' (i) Prior to exceeding five percent power, the licensee shall assure, in a manner acceptable to the NRC staff, that a fire in a single fire zone will not result in the inadvertent opening of all three high/ low pressure interface valves between the reactor core isolation cooling and residual heat removal systems.

This License Condition was tracked by Open item (374/81-00-48(DPRP)). A letter to Mr.

Harold R. Denton (NRC) from C.W. Schroeder (Licensee), subject "LaSalle County Station Units 1 and 2, Fire Protection System Analysis RCIC - RHR, High/ Low Pressure Interface, NRC Docket Nos. 50-373 and 50-374", dated March 1,1984, transmitted Commonwealth Edison Company's reviewlanalysis of a fire in a single fire zone causing the inadvertent opening of hightlow pressure interface valves. Supplement 8 of the SER, Section 9.5.6.7, page 9-6, provides the NRC staff's review and approval of this response. Accordingly, this License Condition is satisfied. This Open item was closed by inspection Report 50-374/84-05(DPRP), dated 4/18184.

l

UNIT 2 LICENSE CONDITIONS - 2.C.(15)(continued)

(j) Prior to startup after the first refueling outage, the licensee shall provide the suppreselon poollevel and temperature monitoring instrumentation at the remote shutdown panel which are electrically isolated from the control room, and assure the instrumentation are operable with the necessary surveillance procedures in place.

This License Condition was tracked by Open item (374/81-00-49(DPRP)). This Open item l was closed by inspection Report 50 374/89021, dated 11/13/89. 1 (k) Prior to startup after the first refueling outage, the licensee shall assure, in a manner acceptable to the NRC staff, that a fire in any single zone will not affect the control of the fuel oil transfer pumps for diesel generators "0" and "2A".

This License Condition was tracked as Unresolved item (374/81-00-50). A modification re-routed the "0" DG fuel oil transfer pump control cables to a different fire zone. Therefore, a fire in any single zone will not affect the control of the fuel oil transfer pumps for diesel generators "0" and "2A".

This Unresolved item was closed by inspection Report 50-374/86044(DRP), dated 1/28/87.

I I

f I

l l

l l

1 J

UNIT 2 LICENSE CONDITIONS FROM ATTACHMENT 1 TO THE UNIT 2 LICENSE E. The following items must be completed for the Fire Protection Program prior to exceeding 5% of rated full power operation:

1. The licensee shall conduct a review of the adequacy of its fire detector system installation. This evaluation shall specifically address the number and location of fire detectors, and ventilation effects on the ability of the d. actors to sense a fire. The licensee shall initiate compensatory measures to areas found deficient to assure adequate fire detection capability. These compensatory measures will remain in place until permanent modificationa to correct any deficiencies are made to the fire detection system.

2. The licensee shall demonstrate that Emergency Lighting Units with at least an 8-hour battery power supply have been installed and are functionally operable in the Control ,

Room,in the Auxiliary Electric Equipment Room at the Remote Shutdown Panel, and on a dedicated access route from the Control Roem to the Auxiliary Electric Equipment room which will include two egress doors from the Control Room.

3. The licensee shall have in place approved procedures defining egress routes for Control Room evacuation to the Remote Shutdown Panel.

4. The licensen shall install the rollup door in the Unit 2 Auxiliary Electric Equipment l Room. l l

5. The licensee shall have in place approved procedures for manual override of those ventilation dampers identified in LaSalle Unit 2 ECN-M-763-LA and LaSalle Unit 1 Modification M-1-1-82-311 as requiring such operation during certain fires.

6. The licensee shall meet the breathing air supply requirements specified in 10 CFR 50, Appendix R, Section lil.H.

7. The licensee shall provide a redundant fire stop for the penetrations identified as exceeding established and tested cable density criteria.

8. The licensee shall have in place approved surveillance procedures for fire barrier penetration seals, including detailed acceptance criteria. .

l

9. The hose nozzles on the refueling floor will be replaced with nozzles appropriately rated.

10. The licensee shall be in conformance to the fire watch qualification requirements of NFPA 518.

11. The licensee shall provide procedures for maintaining the "0" and "2A" diesel generator day tanks at the nominal full position.

This License Condition was tracked as Open item (374/81-00-56(DPRP)). The NRC inspector verified that all eleven items were completed prior to Unit 2 reaching 5% of rated power.

This Open item was closed by inspection Report 50-374/84-05(DPRP), dated 4/18/84.

I 1 UNIT 2 LICENSE CONDITIONS FROM ATTACHMENT 1 TO THE UNIT 2 LICENSE (continued)

F. The following items must be completed prior to startup following the first refueling outage:

1. The licensee shall complete all modifications to the fire detection system identified as  :

being required.

This License Condition was tracked as Open item (374/81-00-28DPRP)). Per Safety Evaluation Report (NUREG-0519), Supplement 8, page 1-2, Condition F of Attachment 1 to License NPF-18 is completed.  ;

2. The licensee shall review the performance of the fire protection system jockey booster pumps and irnplement any changes required by this review.

This License Condition was tracked as Open item (374/81-00-57). This License Condition was closed by inspection Report 50-374/89021, dated 11/13/89.

1 3

5 This proposed amendment does not involve a significant relaxation of the criteria used to establish safety limits, a significant relaxation of the bases for the limiting safety system settings or a significant relaxation of the bases for the limiting conditions for operations.

Therefore, based on the guidance provided in the Federal Register and the criteria established in 10 CFR 50.92(c), the proposed change does not constitute a significant hazards consideration.

l i

I 2

i 4

4 i

i i

i i

i I

i 4

i

1 I

i ATTACHMENT C ENVIRONMENTAL ASSESSMENT Commonwealth Edison has evaluated the proposed amendment against the criteria for identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR Part 51.21. It has been determined that the proposed changes meet the criteria for categorical exclusion as provided for under 10 CFR Part 51.22(c)(9). This conclusion has been determined because the changes requested do not pose significant hazards considerations or do not involve a significant increase in the amounts, and no significant i changes in the types of any effluents that may be released off-site. Additionally, this request i does ne' involve a significant increase in individual or cumulative occupational radiation I exposure.

l l

I t l l

I 4

6 l

1

-. -. -- .- - . . ~ . _ .. _ . . - -

1 ATTACHMENT D l l PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS, FACILITY OPERATING LICENSES NPF-11 AND NPF-18 l LASALLE COUNTY STA110N UNITS 1 & 2 l NPF-11 NPF-18 I

LICENSE PAGES: LICENSE PAGES:

8 6 9 7 Attachment 1 page 2 Attachment 1 page 3 TECHNICAL SPECIFICATION PAGES

TECHNICAL SPECIFICATION PAGES:

V V .

Vill Vill Xill Xill XV XV XXil XXil XXill XXill 3/4 3-74 3/4 3-74 3/4 3-75 3/4375 3/4 3-76 3/4 3-76

'3/4 3-77 3/4 3-77 3/4 3-78 f 3/4 3-78 )

3/4 3-79 3/4 3-79 3/4 3-80 3/4 3-80 I 3/4 7-11 3/4 7-11 3/4 7-12 3/4 7-12 3/4 7-13 3/4 7-13

)

3/4 7-14 3/4 7-14 3/4 7-15 3/4 7-15 3/4 7-16 3/4 7-16 3/4 7-17 3/4 7-17 3/4 7-18 3/4 7-18 3/4 7-19 3/4 7-19 3/4 7-20 3/4 7-20 3/4 7-21 3/4 7-21 3/4 7-22 3/4 7-22 3/4 7-23 3/4 7-23 3/4 7-24 B 3/4 3-5 B 3/4 3-5

B 3/4 7-2 B 3/4 7-2 B 3/4 7-3 B 3/4 7-3 l

6-2 62 l

I

- .. . . _ . _ . - . . . - = -- . . . - _ . - - - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -_

i l

! UNIT 1 LICENSE CONDITIONS - 2.C.(25)

Fire Protection Proaram (Section 9.5. SER. SSER #2. SSER #3 (NUREG-051911.

(a) The licensee shall maintain in effect and fully implement all provisions of the approved '

! fire protection plan. In addition, the licensee shall maintain the fire protection program set forth in Appendix R to 10 CFR Part 50, except for the following deviations:

(i) Hydrostatic hose tests in accordance with NEPA 1962-1979, and (ii) No automatic fire detection systems in areas 2K/3K and 5B4.

l This License Condition is presently in effect, and will be superseded upon issuance of the standard license condition in accordance with the guidance of GLs 86-10 and 88-12.

(b) Prior to initial criticality, the licensee shall install a 1-hour rated barrier on all four sides of a i partially protected power cable pan and a general sprinkler system, both located in the {

diesel-generator ccrridor.

i A general fire sprinkler system and a designed and installed fire protection system were done under Modifications 1-1-82-035, and 1-1-82-055 for the Unit 1 and Unit 2 diesel generator corridors. The NRC staff confirmed, per Section 1.1 of the LaSalle Safety Evaluation Report (NUREG-0519), Supplement 4, that the additional fire protection in the diesel generator corridor had been added prior to exceeding 5 percent power as required by l this License Condition.

This License Condition was closed by inspection Report 50-373/88018(DRP) dated 8/16/88.

t (c) Prior to startup after the first refueling outage, the licensee shall provide fire protection ,

systems in fire areas 2Cl3C,4C3 and 6E. '

This License Condition was tracked by Open item (373/81-00-120(DRP)). The additional fire detection zones were installed under Modification 1-1-82-289. Amendment 44 to License NPF-11 wac approved June 20,1986. The NRC inspector verified that fire protection requirements of this License Condition were met. This Open item was closed by inspection I Report 50-373/86035(DRP), dated 10/29/86.

(d) Prior to startup after the first refueling outage, the licensee with respect to fire doors, shall implement one of the following:

(i) Perform an engineering review of the manufacturer's certified doors and door frames by a nationally recognized laboratory to certify that the door and frames provide the required fire resistance rating, or (ii) Test a replicate "as installed" door assembly by a nationally recognized laboratory to determine the door rating, or l

L i

f UNIT 1 LICENSE CONDITIONS - 2.C.(25)(continued)

(iii) Replace manufacturer's labeled doors and door frames with UL rated items.

4 This Lirense Condition was tracked by Open item (373/8100-130). This Open item was

closed by inspection Report 50-373/86046(DRP), dated 211 818 7.

i

(e) Prior to startup after the first refueling outage, the licensee shall demonstrate the adequacy of its fire protection for record storage.

The Non-Compliance item was closed by inspection Report 50-373/83-12(DPRP), dated 6/13183. The License Condition was closed by inspection Report 373/83-25(DPRP), dated 8/3/83.

9

04/17/82-Lic:2so No. NPF-11 (b) A prelube pump, powered from a reliable direct current power supply, be installed in the system to operate in parallel with the engine-driven lube oil pump, or an alternative acceptable to the NRC shall be installed to preclude dry-starting of the diesel-engine.

(c) Controls and monitoring instrumentation be removed from the engine and engine skid, except instruments qualified for this location. The non-qualified control and monitoring instruments shall be installed on a free standing floor mounted panel and located on a vibration free floor area. If the floor is not vibration free, the panel shall be equipped with vibration mounts.

(22) Direct current Power Syst--- (Emetion 8.1.1.2, tre)

Prior to startup after the first refueling outage for the 125 and 250-volt direct current systems for Divisions 1 and 2 and the 125-volt Division 3 direct current system, the following additional instrumentation shall be provided in the control rooms (1) Battery current (amuneter-charge / discharge), (2)

Battery charger output voltage (voltmeter), (3) Battery charger output current (muneter), (4) Battery high discharge rate alarm, and (5) Battery charger trouble alarm. In the interim, the licensee shall implement approved procedures to monitor battery current, battery charger output voltage, and batter charger output current at the local panels at least once per eight hour shift..

(23) Remeter can*=1--=nt Electrieml:Panatratlana (Eaction 8,4.1. Ere)

Prior to startup after the first refueling outage, a redundant fault current device (circuit breakers or fuses) shall be provided on each penetrating circuit that would limit a fault current surge to be less than the surge for which the penetration is qualified except for low energy (allliumps) instrument systems.

(24) Renarmelen of Elama 1E and Mon clama 1E rahle Trays (Eaction a.4.s.1, tre, mere si, care a2) i Prior to startup after the first refueling outage, the licensee

. shall provide adequate separation or barriers between Class 1E and adjacent non-Class 1E cable trays.  ;

D (25) Fire Proteetlen Proaram (Rection 9.5, tre, mere a2, tems a3)

~ -

(a) The licensee shall maintain in effect and fully implement all provisions of the approved fire protection plan. In addition, the licensee shall maintain the fire protection program set forth in Appendia R to 10 CFR Part 50, except ))

for the following deviations:

~- -

f 0011k

~

SY _

f  !

INSERT A The licensee shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Updated Fint.1 Safety Analysis Report for LaSalle County Nuclear Station, and as described in the SERs for NUREG-0519, NUREG-0519 Supplement 2, ,

NUREG-0519 Supplement 3, NUREG-0519 Supplement 5, NUREG-0519 Supplement 7, and  !

NUREG-0519 Supplement 8, subject to the following provision:  ;

The licensee may make changes to the approved Fire Protection Program without prior  !

Commission approval only if those changes would not adversely affect the ability to achieve and i maintain safe shutdown in the event of a fire.

4 i

e i

t l

1 I

i i

f i

l 1

04/10/89 License 5:o. NPT-11

~

(i) Hydrostatic hose tests in accordance with NEPA 1962-1979, and (11) No automatic fire detection systems in areas i 2K/3K and 554.

{

i f) (b) Prior to initial criticality, the licensee shall install a i I

1-tour rated barrier on all four sides of a partially ' .

protected power cable pan and a general sprinkler system, r

! both located in the diesel- generator corridor.

t

)

(c) Prior to startup after the first refueling outage, the j

licensee shall provide fire protection systems in fire j i areas 2C/3C, 4C3 and 6E. l

}

f (d) Prior to startup after the first refueling outage, the j

licensee with respect to fire doors shall implement one of 1 the following i

(i) Perform an engineering review of the manufac-turer's certified doors and door frames by a I nationally recognised laboratory to certify that the door and door frames provide the required .

fire resistance rating, or l 1 (ii) Test a replicate "as installed" door hssembly by l a nationally recognised laboratory to determine j l .

the door rating, or .

l (iii) Replace manufacturer's labeled doors and door '

frames with UL rated items.

k 4

(e) Prior to startup af ter the first refueling outage, t.no i

licensee shall demonstrate the adequacy of its fire j

protection for record storage.

Am. 14 (26) DELETED  !

i 5/05/83 i

i (27) InAnatrial Security (Rection 13.6, RFR, EEER. GM i

I j Am. 65 CECO shall fully implement and maintain in effect all l

j 4/10/89 provisions of the Commission approved physical security, guard j training and qualification, and safeguards contingency plans 3

including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 l CFR 50.90 and 10 CFR 50.54(p). The plans, which contain 2

0011k i

i

l INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION i 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRLMENTATION. . . . . . . . . . . . .3/4 . . . 3-1

.... l 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 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION l l ATWS Recirculation Pump Trip System Instrumentation.......... 3/4 3-35 End-of-Cycle Recirculation Pump Trip System i Instrumentation.....................................,....... 3/4 3-39 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION t

INSTRUMENTATION........ ................................... 3/4 3-45

! 3/4.3.6 CONTROL R0D WITNDRAWAL BLOCK INSTRUMENTATION. . . . . . . . . .3/4 . . . 3-50 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitori ng Instrumentation. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-56 Sei smic Monitoring Instrumentation. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-60 Meteorological Monitoring Instr a entation.................... 3/4 3-63 Remote Shutdown Monitoring Instrumentation................... 3/4 3-66 Accident Monitoring Instrumentation.......................... 3/4 3-69 Source Range Monitors........................................ 3/4 3-72 Tra versing In-core Probe System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-73 l

' Deleted...................................................... 3/4 3-74 '

(Fi re Detection Instrumentation. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-75 0eleted...................................................... 3/4 3-81 Explosive Gas Monitoring Instrumentation.................... 3/4 3-82 Loose-Part Detection System.................................. 3/4 3-85 3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION i i

1 I NST RUMENTATI ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4

. . . .3-86 i

4 l

LA SALLE - UNIT 1 V Amendment No. 85

. .