Text

Amends 23 & 11 to Licenses NPF-11 & NPF-18,respectively, Incorporating Administrative Changes Which Achieve Agreement Between Units 1 & 2 Tech Specs
	ML20129B615
Person / Time
Site:	LaSalle
Issue date:	05/22/1985
From:	Butler W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20129B623	List: ML20129B615; ML20129B630;
References
	NUDOCS 8506050281
	Download: ML20129B615 (68)
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l' h NUCLE AR REGULATORY COMMISSION E

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,p COM.CN'AEALTH EDISON C0:WAfd DOCKET f40. 50-373 LA SALLE COUNTY STATI0f;, UNIT 1 APEf:Cf'.EfC TO FACILIT) OPERATING LICENSE Ar'endhent No. 23 License Uc. i.PF-11 1.

The Nuclear Regulatory Cornission (the Cornission or the hRC) havirig found that:

A.' The applicaticr. for crerdment filed by the Comcr.t.ealth Ecison Ccr. par.y, dcted February 21, 1985 as sepplcr.:ented by ietter datec

l. arch 5,1985, complies with the stardards and recuirements ci the Atomic Energy Act of 1954, as amended (the Act), arc.the Connissior.'s regulations set forth in 10 CFR Chapitr !;

F.

The facility will operate in conformity with the application, the f revisions of the Act, and the regulations of the Corrission; C.

There is reascnable asst.rance:

(i) that the activities Puthcri ed by this ar:ercrent can be conducted without endangering the health

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and safet) cf thc public, and (ii) that such actitities bill be conducted in conplicnce with the Conmission's regulatics.s set f orth -

in 10 CFR Chapter I; D.

The issuar.ce of this anendnent will not lee inimical to the comon defense ano security or tc the health and safety of the public; and E.

The issuance of this amendnent is in accordance with 10 CFR Fart 51 of the Ccrmissicr's regulations and all applicable requirements have been satisfied.

E.

Accordingly, the license is anendcd by changes to the Technical Specifications as indicatec ir, the attachment to this litersc trier.cnent ar.d pregraph 2.C.(2) of Facility Operatinc License Nc. NPF-11 is hereby amended te read as fcllows:

(2) Technical Specifications and Enviror.r.cr.tal Frotection Plan The Techricc1 Specifications contained in Appencix A, as revised through Amendrent he.23, enc the Environmental Frutecticr. Plar.

cortainea in Appendix B, are hereby inccrporated in the license.

Thc licensee shall operatt the facility 1r. acccrcance with the Technical Specificaticr.S End the Environnental Prctcctior. fien.

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3. -This.anendment is effective as of date of issuance.

.F0P THE NUCLEAP REGULATORY COMMISSION k'al ter R..Butfer,' Chief Licensing. Branch No. 2 Division of Licensino

Enclosure:

- Changes to the~ Technical Specif.ications.

. Date of Issuance: taAY 21 E

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s g l ATTACHMENT TO !.ICENSE AftENDMENT NO. 23 FACILITY GPERATING LICENSE-NO..NPF-11 D_0CKET NO. 50-373 Replace. the foll_owina.Depes of the Appendix "A": Technical Specifications with the enclosed pages. The revised pages.are. identified by Amendnent -

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. number and contain-vertical -lines indicating the-area' of change'. -

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REMOVE INSERT

' I I --.

II 1 1-6 3/4 3 3/4 3-60 3/4 3-63' 3/4'3 3/4 3-75 3/4 3-75 3/4 4 3/4 4-13 3/4 7 3/4 7 3/4 7-14 3/4 7-14

-3/4 7-17 3/4 7-17 3/4 7-18 3/4 7 3/4.7-22 3/4 7-22

-3/4 7-24 3/4 7-24 t:

.3/4 8-7 3/4 8-7

.3/4 11 3/4 11-6

-3/4 11-7 3/4.11-7 3/4 11-13 3/4 11-13 3/4 11-14 3/4 11-14 3/4 11-15.

3/4 11-15' 3/4 11-16 3/4 11-16 3/4 11-20 3/4.11-20 3/4 11-2?

3/4 11 3/4 12-1 3/4 12-1.

3/4 12-9 3/4 12-9 6-9 6-9 6-18 6-18 6-19 6-19 6-24 6-24 6-25 6-25 6-?6 6-26 6-27 6-27 6-28 6-?8 J

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INDEX DEFINITIONS

- SECTION DEFINITIONS (Continued)

PAGE

1. 26 OPERATIONAL CONDITION - CONDITION.................................

1-4 1.27 PHYSICS TESTS.'....................................................

1-4 1.28 PRESSURE BOUNDARY LEAKAGE.........................................

1-5 1.29 PRIMARY CONTAINMENT INTEGRITY.....................................

1-5 1.30 PROCESS CONTROL PR0 GRAM...........................................

1-5 1.31 PURGE - PURGING...................................................

1-5 1.32 RATED THERMAL P0WER...............................................

1-5 1.33 REACTOR PROTECTION SYSTEM RESPONSE TIME...........................

1-5 1.34 REPORTABLE EVENT..................................................

1-6 l

1.35 ROD DENSITY.......................................................

1-6 1.36 SECONDARY CONTAINMENT INTEGRITY...................................

1-6 1.37-SHUTDOWN MARGIN...................................................

1-6 1.38 SOLIDIFICATION....................................................

1-6 1.39-SOURCE CHECK......................................................

1-7 1.40 STAGGERED TEST BASIS..............................................

1 1.41 THERMAL P0WER.....................................................

1-7 1.42 TURBINE BYPASS RESPONSE TIME......................................

1-7 1.43 UNIDENTIFIED LEAKAGE..............................................

1-7 1.44 VENTILATION EXHAUST TREATMENT SYSTEM..............................

1-7 1.45 VENTING...........................................................

1-7 LA SALLE UNIT 1 II Amendment No. 23

DEFINITIONS REPORTABLE EVENT 1.34. A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

R0D DENSITY 1.35 R0D DENSITY shall be the number of control rod notches inserted as a fraction of.the total number of control rod notches.

All rods fully inserted is equivalent to 100% R0D DENSITY.

SECONDARY CONTAINMENT INTEGRITY 1.36 SECONDARY CONTAINMENT INTEGRITY shall exist when:

a.

All secondary containment penetrations required to be closed during accident conditions are either:

1.

Capable of being closed by an OPERABLE secondary containment automatic isolation system, or 2.

Closed by at least one manual valve, blind flange, or deactivated automatic damper secured in its closed position, except as provided in Table 3.6.5.2-1 of Specification 3.6.5.2.

b.

All secondary containment hatches and blowout panels are closed and sealed.

c.

The standby gas treatment system is OPERABLE pursuant to Specification 3.6.5.3.

d.

At least one door in each access to the secondary containment is closed.

e.

The sealing mechanism associated with each secondary containment penetration, e.g., welds, bellows or 0-rings, is OPERABLE.

f.

The pressure within the secondary containment is less than or equal to the value required by Specification 4.6.5.1.a.

SHUTDOWN MARGIN 1.37 SHUTDOWN MARGIN shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming all control rods are fully inserted except for the single control rod of highest reactivity worth which is assumed to be fully withdrawn and the reactor is in the shutdown condition; cold, i.e. 68 F;_and xenon free.

SOLIDIFICATION 1.38 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).

LA SALLE UNIT'1 1-6 Amendment No.23

INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION

LIMITING CONDITION FOR OPERATION 3.3.7.2 The seismic monitoring instrumentation shown in Table 3.3.7.2-1 shall be OPERABLE.**

APPLICABILITY:

At all times.

ACTION:

a.

With one or more seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission l

pursuant to Specification 6.6.C within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.2.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.2-1.

4.3.7.2.2 Each of the above required seismic monitoring instruments actuated during a seismic event greater than or equal to 0.02g shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a CHANNEL CALIBRATION performed within 5 days following the seismic event.

Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion.

A Special Report shall be prepared and submitted to the Commission l

pursuant to Specification 6.6.C within 10 days describing the magnitude, frequency spectrum and resultant effect upon unit features important to safety.

The Seismic Monitoring Instrumentation System is shared between La Salle Unit 1 and La Salle Unit 2.

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

LA SALLE - UNIT 1 3/4 3-60 Amendment No.23

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. INSTRUMENTATION METEOROLOGICALMON$TORINGINSTRUMENTATION*'

LIMITIGCONDITIONFOROPERkiION 3.3.7.3 The meteorological' monitoring instrumentation channels shown in Table

- 3.3.7.3-1 shall be OPERABLE.**

APPLICABILITY:

At all times.

r ACTION:

a.

With one or more meteorological monitoring instrumentation channels inoperable for more than 7 days, prepare and submit c Special Report l

to the Commission' pursuant to Specification 6.6.C within the next 10 days outlining,the cause of the malfunction and the plans for restoring th.e instrumentation to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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SURVEILLANCE REQUIREMENTS Y

4.3.7.3 Each of th'e above required meteoroTogical monitoring instrumentation channels shall be demonstrated OPERABLE by the performance 'of the' CHANNEL

- CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.3-1.

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The Meteorological Monitoring Instrumentation System is shared between La Salle Unit 1 and La Salle Unit 2.

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- **The normal or emergency-power source may be inoperable in OPERATIONAL CONDITION 4 or 5 or when def?;eled.

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'A LA SALLE ' UNIT 1 T

3/4 3-63 Amendment No.23

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.9 As a minimum, the fire detection instrumentation for each fire 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 Minimum Instruments OPERABLE requirement of Table 3.3.7.9-1:

a.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations listed in Speci'ication 4.6.1.7.

b.

Restore the minimum numbar of instruments to OPERABLE status within 14 days or, prepare and submit a Special Report to the Commission l

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 Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS l

4.3.7.9.1 Each of the above required fire detection instruments which are i

accessible during unit operation shall be demonstrated OPERABLE at least once l

per 6 months by performance of a CHANNEL FUNCTIONAL TEST.

Fire detectors l

which are not accessible during unit operation shall be demonstrated OPERABLE i

by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN l

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

e 4.3.7.9.2 The NFPA Standard 720 supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.

Super-vised circuits with detectors which are inassessible during unit operation shall be demonstrated OPERABLE during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

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

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'LA SALLE - UNIT 1 3/4 3-75 Amendment No. 23 1

h REACTOR COOLANT SYSTEM 3/4.4.5 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.5 The specific activity of the primary coolant shall be limited to:

a.

Less than or equal to 0.2 microcurie per gram DOSE EQUIVALENT-I-131, and b.

Less than or equal to 100/E microcuries per gram.

-APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3 and 4.

ACTION:

a.

In OPERATIONAL CONDITIONS 1, 2 or 3 with the specific activity of the primary coolant; 1.

Greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131 but less than or equal to 4.0 microcuries per gram, operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months provided that the cumulative operat-ing time under these circumstances does not exceed 800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months in any consecutive 12 month period. With the total cumulative operating time at a primary coolant specific activity greater than or equal to 0.2 microcurie per gram DOSE EQUIVALENT I-131 exceeding 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months in any consecutive six month period, prepare and submit a special report to the Commission pursuant to Specification 6.6.C within 30 days indicating the number of hours of operation above this limit.

The provisions of Specification 3.0.4 are not applicable.

2.

Greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or for more than 800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months cumulative operating time in a consecutive 12-month period, or greater than or equal to 4 microcuries per gram, be in at least H0T SHUTOOWN with the main steam line isolation valves closed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3.

Greater than 100/E microcuries per gram, be in at least H0T SHUTDOWN with the main steamline isolation valves closed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

In OPERATIONAL CONDITIONS 1, 2, 3 or 4, with the specific activity of the primary coolant greater than 0.2 microcurie per gram DOSE EQUIVALENT I-131 or greater than 100 E microcuries per gram, perform the sampling and analysis requirements of Item 4a of Table 4.4.5-1 until the specific activity of the prim ry ;oolant is restored to within the limit.

A Special Report s'9' e be prepared and submitted l

to the Commission pursuant to Spec ( e ion 5.6.C.

This report shall contain the results of the spec: N.it' tity analyses and the time duration when the specific actsr!.y a

,ie coolant exceeded 0.2 microcurie per gram DOSE EQUIVAMNT I-13) together with the following additional information.

LA SALLE-UNIT 1 3/4 4-13 Ament ent No.23

PLANT SYSTEMS' 3/4.7.5 ' FIRE SUPPRESSION SYSTEMS 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 suppression header, b.

An OPERABLE flow path capable of taking suction from the CSCS water 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.

APPLICABILITY:

At all times.

ACTION:

a.

With one fire pump and/or one water supply inoperable, restore the inoperable equipment to OPERABLE status within 7 days or, prepare and l

submit a Special Report to the Commission pursuant to Specification 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 Specifications 3.0.3 and-3.0.4 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and 2.

Prepare and submit a Special Report in accordance with I

Specification 6.6.C; a)

By telephone within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 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 CONDITION 4 or 5 or when defueled.

LA SALLE - UNIT 1 3/4 7-11 Amendment No.23 1

0 PLANT SYSTEMS DELUGE AND/0R SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.5.2 The deluge and sprinkler systems of Unit 1 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 l

-Report to the Commission pursuant to Specification 6.6.C within the next.30 days outlining the action taken, the cause of the inoperabi-

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

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 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, 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:

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 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.

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

'LA SALLE - UNIT 1 3/4 7-14 Amendment No.23

PLANT SYSTEMS CO2 SYSTEMS l

LIMITING CONDITION FOR OPERATION 3.7.5.3 The following low pressure CO2 systems of Unit 1 and Unit 2 shall be OPERABLE.*

a.

Division 1 diesel generator 0 room.

b.

Division 2 diesel generator 1A room.

c.

Division 3 diesel generator 1B room.

d.

. Unit 2 Division 2 diesel generator 2A 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 C02 systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 Com-l 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 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.5.3 Each of the above required low pressure C02 systems shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying C02 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."

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

LA SALLE - UNIT 1 3/4 7-17 Amendment No. 23

o.

.o PLANT' SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.5.4 The fire hose stations of Unit 1 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 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if the inoperable fire hose is the primary means of fire suppression; otherwise, route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Restore the inoperable fire hose station (s) to OPERABLE status within 14 days or, prepare and submit a Special Report to the Commission l

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 Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.5.4 Each of 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 l

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.

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 at a pressure of 150 psig or at least 50 psig above the maximum fire main operating pressure, whichever is greater.

LA SALLE - UNIT 1 3/4 7-18 Amendment No. 23

.o 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 enclosures and other fire barriers separating safety related fire areas or 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.

APPLICABILITY:

At all times.

ACTION:

a.

With one or more of the above required fire rated assemblies and/or sealing devices inoperable, within one hour either establish a con-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 inoperable fire rated assembly (s) and/or sealing device (s) to OPERABLE status within 7' days or, prepare and submit a Special Report to the Commission l

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 device (s) to OPERABLE status.

b.

The provisions of. Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.6.1 Each of the above required fire rated assemblies and sealing devices shall be verified to be OPERABLE at least once per 18 months by performing a visual inspection of:

a.

The exposed surfaces of each fire rated assemblies.

b.

Each fire window / fire damper and associated hardware.

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 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.

LA SALLE - UNIT 1 3/4 7-22 Amendment No. 23

- PLANT SYSTEMS 3/4.7.7 AREA TEMPERATURE MONITORING LIMITING CONDITION FOR OPERATION 3.7.7 The temperature of each area of Unit 1 and Unit 2 shown in Table 3.7.7-1 shall be maintained within the limits indicated in Table 3.7.7-1.

APPLICABILITY: Whenever the equipment in an affected area is required to be

. 0PERABLE.

ACTION:

With one or more areas exceeding the temperature limit (s) shown in Table-3.7.7-1:

a.

For more than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , in lieu of any Licensee Event Report, prepare l

and submit a Special Report to the Commission pursuant to Speci-fication 6.6.C within the next 30 days providing a record of the amount by which and the cumulative time the temperature in the affected area exceeded its limit and an analysis to demonstrate the continued OPERABILITY of the affected equipment.

b.

By more than 30 F, in addition to the Special Report required above, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either restore the area to within its temperature limit or declare the equipment in the affected area inoperable.

SURVEILLANCE REQUIREMENTS 4.7.7 The temperature in each of the above required areas shown in Table 3.7.7-1 shall be determined to be within its limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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LA SALLE - UNIT 1 3/4 7-24 Amendment No. 23 L.

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ELECTRICAL' POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.

At~least once per 10 years or after any modifications which could affect diesel generator interdependence by starting diesel gener-ators 0,1A and 18 simultaneously, during shutdown, and verifying

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that all three diesel generators accelerate to 900 rpm + 5, -2% in less than or equal to 13 seconds.

f.

At least once per 10 years by:

1.

Draining each fuel oil storage tank, removing the accumulated sediment and cleaning the tank'using a sodium hypochlorite or equivalent solution, and 2.

Performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection ND, of the ASME Code in accordance with ASME Code Section 11, Article IWD-5000.

4.8.1.l.3 Reports - All diesel generator failures, valid or non-valid, shall be reported to the Commission pursuant to Specification 6.6.C within 30 days.

l Reports of' diesel' generator failures shall include the information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977.

If the number of failures in the last 100 valid tests, on a per nuclear unit basis, is greater than or equal to 7, the' report shall be supplemented to include the additional information recommended in Regulatory Position c.3.b of Regulatory Guide 1.108, Revision 1, August 1977.

TABLE 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE Number of Failures in Last 100 Valid Tests

Test Frequency

<1 At least once per 31 days 2

At least once per 14 days 3

At least once per 7 days

>4 At least once per 3 days

" Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, Revision 1, August 1977, where the last 100 tests are determined on a per nuclear unit basis.

With the exception of the semi-annual fast start, no starting time re-quirements are required to meet the valid test requirements of Regulatory Guide 1.108.

LA SALLE - UNIT 1 3/4 8-7 Amendment No. 23

. RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site (see Figure 5.1.1-1) shall be limited:

a.

During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and b.

During any calendar year to less than or equal to 3 mrem to the total body'and to less than or equal to 10 mrem to any organ.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits,.in lieu of any other report required by Specification 6.6.A, prepare and submit l.

to the Commission within 30 days, pursuant to Specification 6.6.C, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commit-ment to an individual from these releases is within 3 mrem to the total body and 10 mrem to any organ.

This Special Report shall also include the radiological impact on finished drinking water supplies

-at the nearest downstream drinking water source, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations.

Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days.

LA SALLE - UNIT 1 3/4 11-6 Amendment No. 23

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RADI0 ACTIVE EFFLUENTS LIQUID WASTE TREATMENT' SYSTEM LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE.

The

- appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from each reactor unit, from the site (see Figure 5.1.1-1), when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

APPLICABILITY:

At all times.

. ACTION:

a.

With the liquid radwaste treatment system inoperable _ for more than 31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specification 6.6.A, prepare and submit to the l

Commission within 30 days pursuant to Specification 6.6.C a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

Summary description of action (s) taken to prevent a recurrence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with the ODCM.

4.11.1.3.2 The liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at-least 30 minutes at.least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.

d LA SALLE - UNIT 1 3/4 11-7 Amendment No. 23

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TRADI0 ACTIVE' EFFLUENTS-

' DOSE!- NOBLE' GASES

-LIMITING CONDITION FOR OPERATION-3.11'.2.2 The air doseLdue to noble' gases released.in gaseous effluents, from each reactor unit,Jfrom the site (see Figure 5.1.1-1) shall be limited to the following:

-a.

During any calendar quarter:

Less than or equal to 5 mrad for gamma fradiation and.less than or equal to 10 mrad for beta radiation, and b.

.During any calendar year:

Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY:

At all times.

ACTION:

+-

a.

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any other

~

report required by Specification 16.6.A, prepare and submit to the l

Commission within'30 days, pursuant to Specification 6.6.C, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the' corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will'be in compliance with the above limits.

-b.

The provisions of Specifications 3.0.3 and 3.0.4~are not applicable.

SURVEILLANCE REQUIREMENTS

. 4.11.2.2 Dose Calculations Cumulative dose contributions for the current

. calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per_31 days.

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LA SALLE - UNIT 1 3/4 11-13 Amendment No. 23

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

E RADI0 ACTIVE EFFLUENTS DOSE - RADI0 IODINES, RADI0 ACTIVE MATERIALS IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN N0BLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an indiv'idual from radioiodines and radioactive meterials in particulate form, and radionuclides, other than noble gases, with hali-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site (see Figure 5.1.1-1) shall be limited to the following:

a.

During any calendar quarter:

Less than or equal to 7.5 mrems to any organ, and b.

During any calendar year:

Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides (other than noble gases) with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.6.A, prepare and submit to the Commission l

within 30 days, pursuant to Specification 6.6.C, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.

.~

LA SALLE - UNIT 1 3/4 11-14 Amendment No. 23 t

RADI0 ACTIVE EFFLUENTS CASE 0VS RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation.

APPLICABILITY: Whenever the main condenser air ejector system is in operation.

ACTION:

a.

With the GASE0US RADWASTE TREATMENT SYSTEM inoperable for more than 7 days, in lieu of any other report required by Specification 6.6.A, l

prepare and submit to the Commission within 30 days, pursuant to Specification 6.6.C, a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

Summary description of action (s) taken to prevent a recurrence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be verified to be in operation at least once per 7 days.

LA SALLE - UNIT 1 3/4 11-15 Amendment No.23

c RADI0 ACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.5 The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE and be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from each reactor unit, from the site (see Figure 5.1.1-1), when averaged over 31 days, would exceed 0.3 mrem to any organ.

APPLICABILITY:

At all times.

ACTION:

a.

With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than 31 days, or with gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specification 6.6.A, prepare and submit to the l

Commission within 30 days, pursuant to Specification 6.6.C, a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

Summary description of action (s) taken to prevent a recurrence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the ODCM.

4.11.2.5.2 The VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 30 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.

LA SALLE - UNIT 1 3/4 11-16 Amendment No. 23

o RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADICTCTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3 The solid radwaste system shall be OPERABLE and used, as applicable in accordance with a PROCESS CONTROL PROGRAM, for the SOLIDIFICATION and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site.

APPLICABILITY:

At all times.

ACTION:

a.

With the packaging requirements of 10 CFR Part 20 and/or 10 CFR Part 71 not satisifed, suspend shipments of defectively packaged solid radioactive wastes from the site.

b.

With the solid radwaste system inoperable for more than 31 days, in lieu of any other report required by Specification 6.6.A, prepare and l

submit to the Commission within 30 days, pursuant to Specifi-cation 6.6.C, a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE

status, 3.

A description of the alternative used for SOLIDIFICATION and packaging of radioactive wastes, and 4.

Summary description of action (s) taken to prevent a recurrence.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3.1 The solid radwaste system shall be demonstrated OPERABLE at least once per 92 days by:

a.

Operating the solid radwaste system at least once in the previous 92 days in accordance with the Process Control Program, or b.

Verification of the existence of a valid contract for SOLIDIFICATION to be performed by a contractor in accordance with a PROCESS CONTROL PROGRAM.

LA SALLE - UNIT 1 3/4 11-20 Amendment No. 23

RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

APPLICABILITY: At all times.

ACTION:

a.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica-tions 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, in lieu of any other report required by Specification 6.6.A, l

prepare and submit, pursuant to Specification 6.6.C, a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.11.4.

This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluents pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this report.

If the estimated dose (s) exceeds the limits of Specification 3.11.4, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of K 190.11.

Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this technical specification.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.4 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the ODCM.

LA SALLE - UNIT 1 3/4 11-22 Amendment No. 23

4 d

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING

.3/4.12.1 MONITORING' PROGRAM 4

LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1.

APPLICABILITY: At all times.

r ACTION:

4 a.

With the radiological environmental monitoring program not being conducted as specified in Table 3.12.1-1, in lieu'of any other report required by. Specification 6.6.A, prepare and submit to the l.

Commission, in the-Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b.

With the level of radioactivity in an environmental sampling medium exceeding the reporting levels.in Table 3.12.1-2 when averaged over any calendar quarter, in lieu of any other report required by Specifi-cation 6.6.A, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter a Special Report pursuant to Specification 6.9.1.13.

When more than one of the radionuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1), concentration (2) + ***> 1.0 limit level (1) limit level ~(2)

When radionuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report'shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

I' c.

With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12.1-1, in lieu of any other report required by Specification 6.6.A, prepare and submit to the Commission within 30 days, pursuant to Specification 6.6.C, a Special Report which identifies the cause'of the unavailability of samples and identifies locations for obtaining replacement samples.

.The locations from which samples were unavailable may then be deleted from those required by Table 3.12.1-1, provided the locations from which the replacement samples were obtained are added to the environ-mental monitoring program as replacement locations, d.

'The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

j.

I LA'SALLE - UNIT 1 3/4 12-1 Amendment No.23 i

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify the location-of the nearest milk animal and the nearest residence in each of the 16 meteor-ological sectors within a distance of five miles.

(For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals in each of the 16 meteoro-logical sectors within a distance of three miles.)

APPLICABILITY:

At all times.

ACTION:

a.

With a land use census identifying a location (s) which yieldt a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, in lieu of any other report required by Specification 6.6.A., prepare and submit to the l

Commission within 30 days, pursuant to Specification 6.6.C., a Special Report which identifies the new location (s).

b.

With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, in lieu of any other report required by Specification 6.6.A., prepare and l

submit to the Commission within 30 days, pursuant to Specifica-tion 6.6.C., a Special Report which identifies the new location.

The new location shall be added to the radiological environmental monitoring program within 30 days.

The sampling location, excluding the control station location, having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after (October 31) of the year in which this land use census was conducted.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted at least once per 12 months between the dates of (June 1 and October 1) using that information which will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

(

LA SALLE - UNIT 1 3/4 12-9 Amendment No.23

1

! ADMINISTRATIVE CONTROLS Ons'ite Review and Investigative Function (Continued)'

3)

Review of all proposed changes to the Technical Speci -

fications.

4)

' Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

5)

Investigation of all noncompliance with NRC requirements

~

and shall prepare and forward a report covering evalua-tion and recommendations:to prevent recurrence to the Division Vice President-Nuclear Stations and to the Supervisor of the Offsite Nuclear and Investigative Function.

6)

Review of facility. operations to detect potential safety hazards.

7)

Performance of special reviews and investigations and reports thereon as requested by the Supervisor of the Offsite Review and Investigative Function.

8)

Review of the Station Security Plan and shall submit recommended changes to the Division Vi = President-Nuclear

' Stations.

9)

Review of the Emergency Plan and station implementing procedures and shall submit recommended changes to the Division Vice President-Nuclear Stations.

10) Review of reportable events and actions taken to prevent l

recurrence.

11) Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations

-and disposition of the corrective action to prevent recur-rence to the Division Vice President-Nuclear Stations and to the Supervisor of the Offsite Nuclear Review and Investigative Function.

12) Review of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and'radwaste treatment systems.

b.

Authority The Technical Staff Supervisor is responsible to the Station Superintentent and shall make recommendations in a timely manner in all areas of review, investigation, and quality control phases of plant maintenance, operation, and administra-l tive procedures relating to facility operations and shall have the authority to request the action necessary to ensure compliance with rules, regulations, and procedures when in his opinion such action is necessary. The Station Superintendent shall follow such recommendations or select a course of action that is more i

conservative regarding safe operation of the facility.

All such

[

disagreements shall be reported immediately to the Division i-Vice President-Nuclear Stations and the Supervisor of the Offsite Review and Investigative Function.

LA SALLE UNIT 1 6-9 Amendment No. 23 je

1 ADMINISTRATIVE CONTROLS PLANT OPERATING PROCEDURES AND PROGRAMS (Continued)

F.

The following programs shall be established, implemented, and maintained:

1.

Primary Coolant Sources Outside Primary Containment A program to reduce leakage from those portions of systems outside primary containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

The systems include LPCS, HPCS, RHR/LPCI, RCIC, hydrogen recombiner, process sampling, containment monitoring, and standby gas treatment systems. The program shall-include the following:

a.

Preventive maintenance and periodic visual inspection require-ments, and b.

Integrated leak test requirements for each system at refueling cycle intervals or less.

2.

In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.

This program shall include the following:

a.

Training of personnel, b.

Procedures for monitoring, and c.

Provisions for maintenance of sampling and analysis equipment.

3.

Post-accident Sampling A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.

The program shall include'the following:

a.

Training of personnel, b.

Procedures for sampling and analysis, c.

Provisions for maintenance of sampling and analysis equipment.

6.3 ACTION TO BE-TAKEN IN THE EVENT OF A REPORTABLE EVENT IN PLANT

-OPERATION The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a Licensee Event Report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.

Each REPORTABLE EVENT shall be reviewed pursuant to Specifi-cation 6.1.G.2.a(5).

LA SALLE UNIT 1 6-18 Amendment No. 23

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

ADMINISTRATIVE CONTROLS 6.4 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED If a safety limit is exceeded, the reactor shall be shut down immediately pursuant to Specification 2.1.1, 2.1.2 and 2.1.3, and critical reactor operation shall not be resumed until authorized by the NRC.

The conditions of shutdown shall be promptly reported to the Division Vice President-Nuclear Stations or his designated alternate. The incident shall be reviewed pursuant to Specifi-cations 6.1.G.1.a and 6.I.G.2.a and a separate License Event Report for each occurrence shall be prepared in accordance with Section 50.73 to 10 CFR Part 50.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour.

The Division Vice President-Nuclear Stations and the Director of Nuclear Safety shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

6.5 PLANT OPERATING RECORDS A.

Records and/or logs relative to the following items shall be kept in a manner convenient for review and shall be retained for at least 5 years:

1.

Records of normal plant operation, including power levels and periods of operation at each power level; 2.

Records of principal maintenance and activities, including inspection and repair, regarding principal items of equipment pertaining to nuclear safety; 3.

Records and reports of reportable events; l

4.

Records and periodic checks, inspection and/or calibrations performed to verify that the surveillance requirements (see Section 4 of these specifications) are being met.

All equipment failing to meet surveil-lance requirements and the corrective action taken shall be recorded; 5.

Records of changes to operating procedures; 6.

Shift engineers' logs; and 7.

Byproduct material inventory records and source leak test results.

4 LA SALLE UNIT 1 6-19 Amendment No. 23

z

. ADMINISTRATIVE CONTROLS-

' Semiannual Radioactive Effluent Release Report (Continued)

The radioactive effluent release' report'shall. include the following information for each type of solid waste shipped offsite during the report period:

a.'

Container volume, b.

Total curie quantity (specify whether determined by measurement or estimate),

c.

Principal radionuclides (specify whether determined by measurement or estimate),

d.

Type of waste (e.g... spent resin, compacted dry waste, evaporator bottoms),

e.

Type of container (e.g., LSA, Type A, Type B, Large Quantity),.

and f.

Solidification agent (e.g., cement, urea formaldehyde).

The radioactive effluent release reports shall include unplanned releases-from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis.

The' radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

5.

Monthly Operating Report Routine reports of operating statistics and shutdown experience, including documentation'of all challenges to safety / relief valves, shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control, US Nuclear Regulatory l

Commission, Washington, DC 20555, with a copy of the appropriate Regional Office, to arrive no later than the 15th of each month

.following the calendar month covered by the report.

Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) l was made effective..In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by Onsite Review and Investigative Function.

B.-

Deleted LA SALLE UNIT 1 6-24 Amendment No.23 l

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This page intentionally left blank LA SALLE UNIT 1 6-25 Amendment No.23 i

p e,

i This page intentionally left blank LA SALLE UNIT 1 6-26 Amendment No.23

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This page intentionally left blank L.

LA SALLE UNIT 1 6-27 Amendment No. 23

ADMINISTRATIVE CONTROLS C.

Unique Reporting Requirements 1.

Special Reports shall be submitted to the Director of the Office of Inspection and Enforcement (Region III) within the time period specified for each report.

6.7 PROCESS CONTROL PROGRAM (PCP)*

6.7.1 The PCP shall be approved by the Commission prior to implementation.

6.7.2 Licensee initiated changes to the PCP:

a.

Shall be submitted to the Commission in the semi annual Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shall contain:

1.

Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; 2.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and 3.

Documentation of the fact that the change has been reviewed and found acceptable by the Onsite Review and Investigative Function.

b.

Shall become effective upon review and acceptance by the Onsite Review and Investigative Function.

(PCP)* Common to LaSalle Unit 1 and LaSalle Unit 2 LA SALLE' UNIT 1 6-28 Amendment No.23

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UNITED STATES 3

i NUCLEAR REGULATORY COMMISSION

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WASHING TON, D. C. 20555 -

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0 3... 4 COMMONWEALTH EDIS0N C0!:PA!;Y DOCKET NO.-50-374 r

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LA SALLE COUNTY STATION, UNIT 2 AMENDMEhT TO FACILITY GPERATING LICENSE

'O s s

w.

Amendrheni No.11 License flc. t'PF-18

1. - The Nuclear. Regulatory Comission (the Cecr.ission or the NRC) havinc 1

' ~ found that:

.A.

The application for amendment filed by the Ccmenwealth Edison

-Corrany, dated February 21, 1985 as supplerr.ented by letter dated March 5, 1985, complies with the standards and requirements cf the Atomic Energy Act of 1954, as amended (the Act), and the Ccr.Taission's regulations set forth in 10 CFR Chapter 1;.,

6.

The facility will operate in conformity with the application, the provisions cf the Act, and thc reculations of the Comission;

(-

C.

There is reasonable assurance:

(i) that the activities authori:ed by this amenorr.ent can be conducted withcut endangering the health and safety of thc public, and (ii) that such activities will be conducted in compliance with the Cocraission's regulatiens set forth ir. 10 CFR Chapter 1; C.

The issuance of this amendraent will not be inimical to the comon defense and security or tc the health and safety of the public; and' E.

The issuarce of this amendment is in accordance with 10 CFR Part'51 of the Comission's regulations and all applicable requirenents*

have been satisfied.

E.

Accordingly, the license is arer.de$ by changes to the T.echnical' I

Specifications as indicated ir. the cttachuent to this license amenocient ar.d paragraph 2.C.(2) of Facility Operatine License No. NPF-18 is hereby amended to reao as follcus-(2) Technical Specifications and Envircr.r. ental Protection _._f an v.

The Technicai Specifications contained in Appendix /, as revised through Amenc' tent No.ll. and the Environmental Protdcticr. Plan contained inMppendix B, are hereby ir.ccrpcrated in 'the license.

The licensee shall operate the f acility in accordance with the Technical Specificatier.s and the Environmental Protecticn Plan.

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3..This amendment is' effective as of date of issuance.

FOR THE NUCLEAR REGULATORY. COMMISSION i.

Walter R. Butler, Chief Licensing Branch No. 2 Division of Licensing

Enclosure:

. Changes to the' Technical

' Specifications Date of-Issuance: MAT I I E 9

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u ATTACHMENT TO LICENSE AMENDMENT NO.11 FACILITY OPERATING LICENSE NO. NPF-18 DOCKET NO. 50-374 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendnent number and contain vertical lines indicating the area of change.

REMOVE INSERT II II 1-6 1-6 3/4 3-60 3/4 3-60 3/4 3-63 3/4 3-63 3/4 3-75 3/4 3-75 3/4 4-14 3/4 4-14 3/4 7 3/4 7-11 3/4 7-14

~3/4~7-14 3/4 7-17.

3/4 7-17 3/4 7-18 3/4 7-18 3/4 7-23 3/4 7-23 3/4 7-25 3/4 7-25 3/4 8-7 3/4 8-7 3/4 11-6 3/4 11-6 3/4 11-7 3/4 11-7 3/4 11-13 3/4 11-13 3/4 11-14 3/4 11-14 3/4 11-15 3/4 11-15 3/4 11-16 3/4 11-16.

3/4 11-20 3/4 11-20 3/4 11-22 3/4 11-22 3/4 12-1 3/4 12-1 3/4 12-9 3/4 12-9 6-9 6-9 6 6-18 6-19 6-19 6-24 6-24 6-25 6-25 6-26 6-26 6-27 6-27.

6-28 6-28

F-INDEX DEFINITIONS SECTION DEFINITIONS (Continued)

PAGE

'1.25 OPERABLE

.0PERABILITY............................................

1-4 1.26 OPERATIONAL CONDITION

. CONDITION.................................

1-4 1.27 PHYSICS TESTS.....................................................

1-4 1.28 PRESSURE BOUNDARY LEAKAGE.........................................

1-5 1.29 PRIMARY CONTAINMENT INTEGRITY.....................................

1-5 1.30 PROCESS CONTROL PR0 GRAM...........................................

1-5 1.31 PURGE - PURGING...................................................

1-5 1.32 RATED THERMAL P0WER......,........................................

1-5 1.33 REACTOR PROTECTION SYSTEM RESPONSE TIME...........................

1-5 1.34 REPORTABLE EVENT..................................................

1-6 l

1.35 ROD DENSITY.......................................................

1-6 1.36 SECONDARY CONTAINMENT INTEGRITY...................................

1-6 1.37 SHUTDOWN MARGIN...................................................

1-6 1.38 SOLIDIFICATION....................................................

1-6 1,39 SOURCE CHECK......................................................

1-7 1.40 STAGGERED TEST BASIS..............................................

1-7 1.41 THERMAL P0WER.....................................................

1-7 1.42 TURBINE BYPASS RESPONSE TIME......................................

1-7 1.43 UNIDENTIFIED LEAKAGE..............................................

1-7

'~

1.44 VENTILATION EXHAUST TREATMENT SYSTEM..............................

1-7 1.45 VENTING...........................................................

1-7

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LA SALLE - UNIT 2 II Amendment No.11

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DEFINITIONS REPORTABLE EVENT 1.34 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

R0D DENSITY 1.35 R0D DENSITY shall be the number of control rod notches inserted as a fraction of the total number of control rod notches.

All rods fully inserted is equivalent to 100% R0D DENSITY.

SECONDARY CONTAINMENT INTEGRITY 1.36 SECONDARY CONTAINMENT INTEGRITY shall exist when:

a.

All secondary containment penetrations required to be closed during accident conditions are either:

1.

Capable of being closed by an OPERABLE secondary containment automatic isolation system, or 2.

Closed by at least one manual valve, blind flange, or deactivated automatic damper secured in its closed position, except as provided in Table 3.6.5.2-1 of Specification 3.6.5.2.

b.

All secondary containment hatches and blowout panels are closed and sealed.

c.

The standby gas treatment system is OPERABLE pursuant to Specification 3.6.5.3.

d.

At least one door in each access to the secondary containment is closed.

e.

The sealing mechanism associated with each secondary containment penetration, e.g., welds, bellows or 0-rings, is OPERABLE.

f.

The pressure within the secondary containinent is less than or equal to the value required by Specification 4.6.5.1.a.

SHUTDOWN MARGIN 1.37 SHUTDOWN MARGIN shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming all control rods are fully inserted except for the single control rod of highest reactivity worth which is assumed to be fully withdrawn and the reactor is in the shutdown condition; cold, i.e. 68*F; and xenon free.

SOLIDIFICATION 1.38 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized l

solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).

I LA SALLE - UNIT 2 1-6 Amendment No.ll l

INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION

LIMITING CONDITION FOR OPERATION 3.3.7.2' The seismic monitoring instrumentation shown in Table 3.3.7.2-1 shall be OPERABLE.**

APPLICABILITY:

At all times.

ACTION:

a.

With one or more seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission l

pursuant to Specification 6.6.C within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.2.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the. CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL' CALIBRATION operations at the frequencies shown in Table 4.3.7.2-1.

4.3.7.2.2 Each of the above required seismic monitoring instruments actuated during a seismic event greater than or equal to 0.02g shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a CHANNEL CALIBRATION performed within 5 days following the seismic event.

Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission l

pursuant to Specification 6.6.C within 10 days describing the magnitude, frequency spectrum, and resultant effect upon unit features important to I

safety.

The Seismic Monitoring Instrumentation System is shared between La Salle Unit 1 and La Salle Unit 2.

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

LA SALLE - UNIT 2 3/4 3-60 Amendment No.ll

INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION

LIMITING CONDITION FOR OPERATION 3.3.7.3 The meteorological monitoring instrumentation channels shown in Table 3.3.7.3-1 shall be OPERABLE.**

APPLICABILITY:

At all times.

ACTION:

a.

- With one or more meteorological monitoring instrumentation channels inoperable for more than 7 days, prepare and submit a Special Report l

to the Commission pursuant to Specification 6.6.C within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrumentation to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.3 Each of the above required meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.3-1.

l l

The Meteorological Monitoring Instrumentatica System is shared between i

La Salle Unit 1 and La Salle Unit 2.

i

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

l LA SALLE - UNIT 2 3/4 3-63 Amendment No.ll L

INSTRUMENTATION

~ FIRE DETECTION-INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.9 As a minimum,'the fire' detection instrumentation for each fire 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 Minimum Instruments OPERABLE requirement of Table 3.3.7.9-1:

Within I hour, establish a fire watch patrol to inspect the zone (s) a.

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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 0PERABLE status within 14 days or, prepare and submit a Special Report to the Commission l

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 Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.9.1-Each of the above required fire detection instruments which are i

accessible during unit operation shall 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 L

by the performance of.a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN t!

exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 instruments shall be demonstrated OPERABLE at least once per 6 months.

Super -

E

. vised circuits with detectors which are inaccessible during unit operation shall e

be demonstrated OPERABLE during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless

. performed in the previous 6 months.

j

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

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LA SALLE - UNIT 2 3/4 3-75 Amendment No.ll l

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REACTOR COOLANT SYSTEM 3/4.4.5 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.5 The specific activity of the primary coolant shall be limited to:

a.

Less than or equal to 0.2 microcurie per gram DOSE EQUIVALENT I-131, and b.

Less than or equal to 100/E microcuries per gram.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3, and 4.

ACTION:

a.

In OPERATIONAL CONDITION 1, 2, or 3 with the specific activity of the primary coolant; 1.

Greater than 0.2 microcuria per gram DOSE EQUIVALENT I-131 but less than or equal to 4 microcurie per gram, operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months provided that the cumulative operat-ing time under these circumstances does not exceed 800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months in any consecutive 12-month period. With the total cumulative operating time at a primary coolant specific activity greater than or equal to 0.2 microcurie per gram DOSE EQUIVALENT I-131 exceeding 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months in any consecutive 6-month period, prepare and submit a special report to the Commission pursuant to Specification 6.6.C within 30 days indicating the number of hours of operation above this limit.

The provisions of Specification 3.0.4 are not applicable.

2.

Greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous _ time interval or for more than 800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months cumulative operating time in a consecutive 12-month period, or greater than or equal to 4 microcuries per gram, be in at least HOT SHUTDOWN with the main steam line isolation valves closed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3.

Greater than 100/E microcuries per gram, be in at least HOT SHOTDOWN with the main steamline isolation valves c'esed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

In OPERATIONAL CONDITION 1, 2, 3, or 4, with the specific acti.fty of the primary coolant greater than 0.2 microcurie per gram DOSE EQUIVALENT I-131 or greater than 100/E microcuries per gram, perform the sampling and analysis requirements of Item 4a of Table 4.4.5-1 until the specific activity of the primary coolant is restored to within the limit.

A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.6.C.

This report shall contain the results of the specific activity analyses and the time duration when the specific activity of the coolant exceeded 0.2 microcurie per gram DOSE EQUIVALENT I-131 together with the following additional information.

LA SALLE - UNIT 2 3/4 4-14 Amendment No.11

o PLANT SYSTEMS 3/4.7.5 FIRE SUPPRESSION SYSTEMS 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 sup-pression header, b.

An OPERABLE flow path capable of taking suction from the CSCS water 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.

APPLICABILITY: At all times.

ACTION:

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 Specifications 3.0.3 and 3.0.4 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and 2.

Prepare and submit a Special Report in accordance with Specifi-l cation 6.6.C; a)

By telephone within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 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 CONDITION 4.ot 5 or when defueled.

LA SALLE - UNIT 2 3/4 7-11 Amendment No.ll

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PLANT SYSTEMS DELUGE AND/0R SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION

-3.7.5.2 The deluge and sprinkler systems of Unit 1 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months _ 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 l

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 OPERABLE status.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

e SURVEILLANCE REQUIREMENTS 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, 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:

1.

By performing a system functional test which includes simulated dUtomatiC actuation of the system, and:

a)

Verifying that the automatic valves in the flow path 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.

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.ll

PLANT SYSTEMS CO, SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.5.3 The following low pressure CO systems of Unit 1 and Unit 2 shall be 2

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 1A 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 l

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 OPERABLE status.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 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 systar. 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 CONDITION 4 or 5 or when defueled.

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

PLANT SYSTEMS FIRE HOSE STATIONS

' LIMITING CONDITION FOR OPERATION 3.7.5.4 The fire hose stations of Unit 1 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 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if the inoperable fire hose is the primary means of fire suppression; otherwise, route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Restore the inoperable fire hose station (s) to OPERABLE status within 14 days or, prepare and submit a Special Report to the Commission l

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 Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.5.4. Each of 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.

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 at a pressure of 150 psig or at least 50 psig above the maximum fire main operating pressure, whichever is greater.

LA SALLE - UNIT 2 3/4 7-18 Amendment No.Il

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 enclosures and other fire barriers separating safety-related fire areas or 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.

APPLICABILITY:

At all times.

ACTION:

a.

With one or more of the above required fire rated assemblies and/or sealing devices inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either establish a con-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 inoperable fire rated assembly (s) and/or sealing device (s) to OPERABLE status within 7 days or, prepare and submit a Special Report to the Commission l

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 device (s) to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.6.1 Each of the above required fire rated assemblies and sealing devices shall be verified to be OPERABLE at least once per 18 months by performing a visual inspection of:

a.

The exposed surfaces of each fire rated assemblies.

b.

Each fire window / fire damper and associated hardware.

c.

At least 10% of each type of sealed penetration.

If apparent changes in appearance or abnormal degradations are found, a visual inspection of an additional 10% of each type of sealed penetration shall be made.

This inspection process shall continue until a 10% sample with no apparent changes in appearance or abnormal degradation is found.

LA SALLE - UNIT 2 3/4 7-23 Amendment No.ll

PLANT SYSTEMS 3/4.7.7 AREA TEMPERATURE MONITORING LIMITING CONDITION FOR OPERATION 3.7.7 The temperature of each area of Unit 1 and' Unit 2 shown in Table 3.7.7-1 shall be maintained within the limits indicated in Table 3.7.7-1.

APPLICABILITY: Whenever the equipment in an affected area is required to be OPERABLE.

ACTION:

With one or more areas exceeding the temperature limit (s) shown in Table 3.7.7-1:

a.

For more than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , in lieu of any Licensee Event Report, prepare l

and submit a Special Report to the Commission pursuant to Specifica-tion 6.6.C within the next 30 days providing a record of the amount by which and the cumulative time the temperature in the affected area exceeded its limit and an analysis to demonstrate the continued OPERABILITY of the affected equipment.

b.

By more than 30 F, in addition to the Special Report required above, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either restore the area to within its temperature limit or declare the equipment in the affected area inoperable.

SURVEILLANCE REQUIREMENTS 4.7.7 The temperature in each of the above required areas shown in Table 3.7.7-1 shall be determined to be within its limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i LA SALLE - UNIT 2 3/4 7-25 Amendment No.11

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.

At least once per 10 years or after any modifications which could affect diesel generator interdependence by starting diesel ge'ner-ators 0, 2A, and 2B simultaneously, during shutdown, and verifying that all three diesel generators accelerate to 900 rpm + 5, -2% in less than or equal to 13 seconds.

f.

At least once per 10 years by:

1.

Draining each fuel oil storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypochlorite or equivalent solution, and 2.

Performing a. pressure test of those portions of the diesel fuel oil system designed to Section III, subsection ND, of the ASME Code in accordance with ASME Code Section 11, Article IWD-5000.

4.8.1.1.3 Reports - All diesel generator failures, valid or non-valid, shall be reported to the Commission pursuant to Specification 6.6.C within 30 days.

l Reports of diesel generator failures shall include the information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977.

If the number of failures in the last 100 valid tests, on a per nuclear unit basis, is greater.than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position c.3.b of Regulatory Guide 1.108, Revision 1,' August 1977.

TABLE 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE Number of Failures in Last 100 Valid Tests

Test Frequency

$1 At least once per 31 days 2

At least once per 14 days l

l 3

At least once per 7 days

>4 At least once per 3 days

Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of i

Regulatory Guide 1.108, Revision 1, August 1977, where the last 100 tests are determined on a per nuclear unit basis. With the exception of the semiannual fast start, no starting time require-ments are required to meet the valid test requirements of Regulatory Guide 1.108.

I i

l LA SALLE - UNIT 2 3/4 8-7 Amendment No.ll

RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site (see Figure 5.1.1-1) shall be limited:

a.

During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and b.

During any calendar year to less than or equal to 3 mrem to the total body and to.less than or equal to 10 mrem to any organ.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.6.A, prepare and submit l

to the Commission within 30 days, pursuant to Specification 6.6.C, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commit-ment to an individual from these releases is within 3 mrem to the total body and 10 mrem to any organ.

This Special Report shall also include the radiological impact on finished drinking water supplies at the nearest downstream drinking water source.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations.

Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days.

k LA SALLE - UNIT 2 3/4 11-6 Amendment No.ll

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1.

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RADIOACTIVE EFFLUENTS i

LIQUID WASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 1-3.11.1.3l The liquid radwaste treatment system shall be OPERABLE.. The appropriate portionslof the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from each reactor unit, from the site (see Figure.5.1.1-1),-when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

l APPLICABILITY:

At all times.

ACTION:

_ ith the liquid radwaste treatment system inoperable for more than W

a.

31 days or with radioactive liquid waste being discharged without treatment and.in excess of the above limits, in lieu of any other report required by Specification 6.6.A, prepare and. submit to the l

Commission within 30 days pursuant to Specification 6.6.C-a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s).taken to restore the inoperable equipment to OPERABLE status,'and 3.

Summary description of action (s) taken to prevent a recurrence.

b.

.The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

I SURVEILLANCE REQUIREMENTS t-

'4.11.1.3.1-Doses due to liquid releases-shall be projected at least once per l-31 days,.in accordance with the ODCM.

l; L

4.11.1.3.2 - The liquid radwaste treatment system shall be demonstrated CPERABLE L

.by operating the liquid radwaste treatment system equipment for at least l'

30 minutes at least once per 92 days unless the liquid radwaste system has been l

-utilized to process radioactive liquid effluents during the previous 92 days.

l LA SALLE - UNIT 2 3/4 11-7 Amendment No.ll

~

RADI0 ACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site (see Figure 5.1.1-1) shall be limited to the following:

a.

During any calendar quarter:

Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and b.

During any calendar year:

Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

a.

With_the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.6.A, prepare and submit to the l

Commission within 30 days, pursuant to Specification 6.6.C, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.

LA SALLE - UNIT 2 3/4 11-13 Amendment No.ll

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RADI0 ACTIVE EFFLUENTS DOSE - RADI0 IODINES, RADI0 ACTIVE MATERIALS IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from radioiodines and radioactive materials in particulate form, and radionuclides, other than noble gases, with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site (see Figure 5.1.1-1) shall be limited to the following:

a.

During any calendar quarter:

Less than or equal to 7.5 mrems to any organ, and b.

During any calendar year:

Less than or equal to 15 mrems to any organ.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides (other than noble gases) with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.6.A, prepare and submit to the l

Commission within 30 days, pursuant to Specification 6.6.C, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.

1 k

s LA SALLE - UNIT 2 3/4 11-14 Amendment No.11

RADI0 ACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASE0US RADWASTE TREATMENT SYSTEM shall be in operation.

APPLICABILITY: Whenever the main condenser air ejector system is in operation.

ACTION:

a.

With the GASE0US RADWASTE TREATMENT SYSTEM inoperable for more than 7 days, in lieu of any other report required by Specification 6.6.A, l

prepare and submit to the Commission within 30 days, pursuant to Specification 6.6.C, a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status,-and 3.

Summary description of action (s) taken to prevent a recurrence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4 The GASE0US RADWASTE TREATMENT SYSTEM shall be verified to be in operation at least once per 7 days.

l t

t LA SALLE - UNIT 2 3/4 11-15 Amendment No.ll

RADI0 ACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.5 The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE and be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from each reactor unit, from the site (see Figure 5.1.1-1), when averaged over 31 days, would exceed 0.3 mrem to any organ.

APPLICABILITY:

At all times.

ACTION:

a.

With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than 31 days, or with gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specification 6.6.A, prepare and submit l

to the Commission within 30 days, pursuant to Specification 6.6.C, a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

Summary description of action (s) taken to prevent a recurrence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from the site shall be projected at l

1 east once per 31 days in accordance with the ODCM.

4.11.2.5.2 The VENTILATION EXHAUST TREATMENT SfSTEM shall be demonstrated OPERABLE by operating the VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 30 minutes, at least once per 92 days unless the appropriate system has been utilized to process radicactive gaseous effluents during the previous 92 days.

LA SALLE - UNIT 2 3/4 11-16 Amendment No.11

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RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADI0 ACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3 The solid radwaste system shall be OPERABLE and used, as applicable in accordance with a PROCESS CONTROL PROGRAM, for the SOLIDIFICATION and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site.

APPLICABILITY:

At all times.

ACTION:

. a.

With the packaging requirements of 10 CFR Part 20 and/or 10 CFR Part 71 not satisifed, suspend shipments of defectively packaged solid radioactive wastes from the site.

b.

With the solid radwaste system inoperable for more than 31 days, in lieu of any other report required by Specification 6.6.A, g

prepare and submit to the Commission within 30 days, pursuant to Specification 6.6.C, a Special Report which includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE

status, 3.

A description of the alternative used for SOLIDIFICATION and packaging of radioactive wastes, and 4.

Summary description of action (s) taken to prevent a recurrence.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS i

4.11.3.1 The solid radwaste system shall be demonstrated OPERABLE at least once per 92 days by:

a.

Operating the solid radwaste system at least once in the previous 92 days in accordance with the Process Control Program, or b.

Verification of the existence of a valid contract for SOLIDIFICATION to be performed by a contractor in accordance with a PROCESS CONTROL PROGRAM.

LA SALLE - UNIT 2 3/4 11-20 Amendment No.11

RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica-tions 3.11.1.2.a 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, in lieu of any other report required by Specification 6.6. A, prepare and submit, pursuant to Specification 6.6.C, a l

Special Report to the Director, Nuclear Reactor Regulation, U.S.

Nuclear Regulatory Commission, Washington, D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.11.4.

This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluents pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this report.

If the esti-mated dose (s) exceeds the limits of Specification 3.11.4, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of S 190.11.

Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this technical specification.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.4 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the ODCM.

LA SALLE - UNIT 2 3/4 11-22 Amendment No.ll

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1.

APPLICABILITY:

At all times.

ACTION:

a.

With the radiological environmental monitoring program not being conducted as specified in Table 3.12.1-1, in lieu of any other report required by Specification 6.6.A, prepare and submit to the l

Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b.

With the level of radioactivity in an environmental sampling medium exceeding the reporting levels in Table 3.12.1-2 when averaged over any calendar quarter, in lieu of any other report required by Specifi-cation 6.6.A, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter a Special Report pursuant to Specification 6.6.C.

When more than one of the radio-nuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1), concentration (2) + ***> 1.0 limit level (1) limit level (2)

When radionuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shall be submitted i

if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

This report is not required if the measured level of l

radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c.

With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12.1-1, in lieu of any other report required by Specification 6.6.A, prepare and submit l

l to the Commission within 30 days, pursuant to Specification 6.6.C, a Special Report which identifies the cause of the unavailability of samples and_ identifies locations for obtaining replacement samples.

The locations from which samples were unavailable may then be deleted l

from those required by Table 3.12.1-1, provided the locations from which the replacement samples were obtained are added to the environ-mental monitoring program as replacement locations.

d.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

l LA SALLE - UNIT 2 3/4 12-1 Amendment No. 11

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A_ land use census shall be conducted and shall identify the location of the nearest milk animal and the nearest residence in each of the 16 meteor-ological sectors within a distance of five miles.

(For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals in each of the 16 meteoro-logical sectors within a distance of three miles.)

APPLICABILITY:

At all times.

ACTION:

a.

With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, in lieu of any other report required by Specification 6.6.A, prepare and submit to the l

Commission within 30 days, prusuant to Specification 6.6.C., a Special Report which identifies the new location (s).

b.

With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, in lieu of any other report required by Specification 6.6A, prepare and submit to l

the Commission within 30 days, pursuant to Specification 6.6.C., a Special Report which identifies the new location.

The new location shall be added to the radiological environmental monitoring program within 30 days.

The sampling location, excluding the control station location, having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after (October 31) of the year in which this land use census was conducted.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted at least once per 12 months between the dates of (June 1 and October 1) using that information which will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

LA SALLE - UNIT 2 3/4 12-9 Amendment No.11

ADMINISTRATIVE' CONTROLS

'Onsite Review and Investigative Function (Continued) 3)

Review of all proposed changes to the Technical Speci-fications.

4)~

Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

-5)

Investigation of'all noncompliance with NRC requirements and shall prepare and forward a report covering evalua-tion and recommendations to prevent recurrence to the Division Vice President-Nuclear Stations and to the Supervisor of the.0ffsite Nuclear and Investigative Function.

6)

Review of facility operations to detect potential safety hazards.

7)

Performance of special reviews and investigations and reports thereon as requested by.the Supervisor of the Offsite Review and Investigative Function.

8)

Review of the Station Security Plan and shall submit recommended changes to the Division Vice President-Nuclear Stations.

9)

Review of the Emergency Plan and station implementing procedures and shall submit recommended changes to the Division Vice President-Nuclear Stations.

10) Review of reportable events and actions taken to prevent l

recurrence.

11) Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recur-rence to the Division Vice President-Nuclear Stations and to the Supervisor of the Offsite Nuclear Review and Investigative Function.

12) Review of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL,'and radwaste treatment systems.

b.

Authority The Technical Staff Supervisor is responsible to the Station Superintentent and shall make recommendations in a timely manner in all areas of review, investigation, and quality control phases of plant maintenance, operation, and administra-tive procedures relating to facility operations and shall have the authority to request the action necessary to ensure compliance with rules, regulations, and procedures when in his opinion such action is necessary.

The Station Superintendent shall follow such recommendations or select a course of action that is more conservative regarding safe operation of the facility.

All such disagreements shall be reported immediately to the Division Vice President-Nuclear Stations and the Supervisor of the Offsite Review and Investigative Function.

LA SALLE - UNIT 2 6-9 Amendment No.ll

~ ADMINISTRATIVE CONTROLS

. PLANT OPERATING PROCEDURES AND PROGRAMS (Continued)

F.

The following programs shall be established, implemented, and maintained:

1.

Primary Coolant Sources Outside Primary Containment A program to reduce leakage from those portions of systems outside primary containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

The systems include LPCS, HPCS, RHR/LPCI, RCIC, hydrogen recombiner, process sampling, containment monitoring, and standby gas treatment systems. The program shall include the following:

a.

Preventive maintenance and periodic visual inspection require-ments, and b.

Integrated leak test requirements for each system at refueling cycle intervals or less.

2.

In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.

This program shall include the following:

a.

Training of personnel, b.

Procedures for monitoring, and c.

Provisions for maintenance of sampling and analysis equipment.

3.

Post-accident Sampling A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.

The program shall include the following:

a.

Training of personnel, b.

Procedures for sampling and analysis, c.

Provisions for maintenance of sampling and analysis equipment.

~~~

6.3 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE EVENT IN PLANT OPERATION The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified and a Licensee Event Report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.

Each REPORTABLE EVENT shall be reviewed pursuant to Specifica-tion-6.1.G.2.a(S).

L LA SALLE - UNIT 2 6-18 Amendment No. 11 i-

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's ADMINISTRATIVE CONTROLS s s s,.

6.4 ACTION TO BE TAKEN IN THE EVENT A SAFET'Y LIMIT IS EXCEEDED If_a safety limit is exceeded, the reactor shall be shut down immediately pursuant to Specification 2.1.1, 2.1.2 and 2.1.3, and critical reactor operation shall not be resumed until authorized by the NRC. The conditions of shutdown shall be promptly reported to the Division Vice President-Nuclear Stations or his designated alternate.

The ir.cident shall be reviewed pursuant to Specifica-tions 6.1.G.1.a and 6.I.G.2.a and a separate License Event Report for each occurrence shall be prepared in accordance with Section 50.73 to 10 CFR Part 50.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour.

The Division Vice President-Nuclear Stations and 'Cs the Director of Nuclear Safety shall beinotified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

s t

6.5 PLANT CPERATING RECORDS A.

RecordsandIorlogsrelativetothefollowingitemsshallbekeptina manner convenient *for review and shall be retained for at least 5 years:

1.

Records of normal plant operation, including power levels and periods of operation at each power level; 2,

Records of principal maintenance and activities, including inspection and repair, regarding principal items of equipment pertaining to nuclear safety; 3.

Records and reports of reportable events; l

4.

Records and periodic checks, inspection and/or calibrations performed to verify that the surveillance requirements (see Section 4.of these specifications) are being met.

All equipment failing to meet surveil-lance requirements and the corrective action taken shall be recorded; 5.'

Records of changes to operating procedures; 6.

Shift engineers' logs; and 7.

Byproduct material inventory records and source leak test results.

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LA SALLE - UNIT 2 6-19 Amendment No.11

+

1 ADMINISTRATIVE CONTROLS Semiannual Radioactive Effluent Release Report (Continued)

The radioactive effluent release report'shall include the following information for each type of solid waste shipped offsite during the report period:

a.

Container volume, b.

Total curie quantity (specify whether determined by

~

measurement or estimate),

c.

Principal radionuclides (specify whether determined by measurement or estimate),

d.

Type of waste (e.g.

spent resin, compacted dry waste, evaporator bottoms),

e.

Type of container (e.g., LSA, Type A, Type B, Large Quantity),

and f.

Solidification agent (e.g., cement, urea formaldehyde).

The radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a ' quarterly basis.

The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

5.

Monthly Operating Report Routine reports of operating statistics and shutdown experience, including documentation of all challenges to safety / relief valves, shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control, US Nuclear Regulatory Commission, Washington, DC 20555, with a copy of the appropriate Regional' Office, to arrive no later than the 15th of each month following the calendar month covered by the report.

Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective.

In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by Onsite Review and Investigative Function.

B.

Deleted.

LA SALLE - UNIT 2 6-24 Amendment No.ll

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-.LA SALLE UNIT 2 6-26 Amendment No.11

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.LA SALLE - UNIT 2 6-27 Amendment No.11

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a-c ADMINISTRATIVE CONTROLS

- C.

Unique Reporting Requirements 1.

Special Reports shall be_ submitted to the Director of the Office of Inspection and Enforcement (Region III) within the-time ~ period specified for each report.

6.7 PROCESS CONTROL PROGRAM (PCP)*

6.7.1 The PCP shall be approved by the Commission prior to implementation.

6.7.2~ Licensee-initiated changes to the PCP:

a.

Shall be submitted to the Commission in the semiannual Radioactive Effluent Release Report for the period in which'the change (s) was made.

This submittal shall contain:

1.

Sufficiently detailed information to totally support the rationale for_the change without benefit of additional or supplemental information; 2.

A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and 3.

Documentation of the fact that the change has been reviewed and found acceptable by the Onsite Review and Investigative Function.

b.

Shall become. effective upon review and acceptance by the Onsite Review and Investigative Function.

The Process. Control Program (PCP) is common to La Salle Unit 1 and La Salle Unit 2.

LA SALLE - UNIT 2 6-28 Amendment No.11

ML20129B615

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Enclosure:

Enclosure:

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