ML20205T718

Proposed Changes to Tech Spec Table 3.3.6-2,decreasing Rod Block Monitor Trip Setpoints & Allowable Values by 2% for Control Rod Withdrawal Block Instrumentation Setpoints

ML20205T718
Person / Time
Site:	LaSalle
Issue date:	06/10/1986
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20205T715	List: ML20205T711 ML20205T718
References
NUDOCS 8606160177
Download: ML20205T718 (5)

Text

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Attachment A Proposed changes l

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i 8606160177 860610 PDR ADOCK 05000373 P PDR l

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INDEX LIMITING CONDITI0t4S FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops.......................................... 3/4 4-1 Jet Pumps.................................................... 3/4 4-2 Recirculation Loop Flow...................................... 3/4 4-3 Idle Recirculation Loop Startup.............................. 3/4 4-4 m.___, ,, , , -

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avuv....vj.................................. s,, , ,. , . , . u i -6 3/4.4.2 SAFETY / RELIEF VALVES......................................... 3/4 4-5 3/4 4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.......... ......................... 3/4 4-6 Operational Leakage.........................'................. 3/4 4-7 3/4.4.4 CHEMISTRY.................................................... 3/4 4-10 3/4.4.5 SPECIFIC ACTIVITY............................................ 3/4 4-13 3/4.4.6 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System....................................... 3/4 4-16 Reactor Steam Dome........................................... 3/4 4-20 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES............................. 3/4 4-21 ,

3/4.4.8 STRUCTURAL INTEGRITY......................................... 3/4 422 3/4.4.9 RESIDUAL HEAT REMOVAL Hot Shutdown................................................. 3/4 4-23 Cold Shutdown................................................ 3/4/4-24 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ECCS-0PERATING..........,..................................... 3/4 5-1 3/4.5.2 ECCS-SHUTD0WN................................................ 3/4 5-6 3/4.5.3 SUPPRESSION CHAMBER......................................... 3/4 5-8 LA SALLE - UNIT 1 VI Amendment No. 40

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' TABLE 3.3.6-2 E

y CONTROL R00 WITilDRAWAL BLOCK INSTRUMENTATION SETPOINTS l- TRIP SETPOINT ALLOWABLE VALUE ni TRIP FUNCTION

$ R00 BLOCK HONITOR ,

1.

E a. Upscale ++

1) Two Recirculation 327o 919.

[ Loop Operation -< 0.66 W t* R -< 0.66 W +.4 W '

18

2) Single Recirculation 32.'I 'lo 35.97. -

,p Loop Operation 1 0.66W +.34d %~ $ 0.66W + Urff Inoperative N.A. N.A.

b.

c. Downscale 1 5% of RATED THERMAL POWER 1 3% of RATED THERMAL POWER

2. APRH .

a. Flow Blased Simulated R Thermal Power-Upscale

! +- 1) Two Recirculation (p Loop Operation 1 0.66 W t 42%* 1 0.66 W + 45%*

g 2) Single Recirculation 16 Loop Operation < 0.66W t 36.7% < 0.66W + 39.7%*

Inoperative N.A. N.A.

b. > 3% of RATED TilERMAL POWER

c. Downscale > 5% of RATED TilERHAL POWER

d. Neutron Flux-High 312%ofRATEDTilERHALPOWER 314% of RATED TilERMAL POWER

3. SOURCE RANGE MONITORS ,

N.A. N.A. l36 a.. Detector not full in 5

b. Upscale < 2 x 105 cps < 5 x 10 cps H.A. 'H.A. lse

c. Inoperative

- d. Downscale 1 0.7 cps 1 0.5 cps .

g 4. INTERHEDIATE RANGE MONITORS N.A. N.A. I'8 I a. Detector not full in < 110/125 of full scale m b. Upscale < 108/125 of full scale H.A. H.A. l,g -

$ c. Inoperative P d. Downscale 1 5/1250f full scale 1 3/125 of full scale

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ATTACISBNT B SIGNIFICANT HAZARDS CONSIDERATION comunonwealth Edison has evaluated the proposed Technical Specification Amendment and determined that it does not represent a significant hazards consideration. Based on the criteria for defining a significant hazards consideration established in 10 CPR 90, operation of LaSalle County Station Units 1 and 2 in accordance with the proposed amendment will not:

1) Involve a significant increase in the probability or consequences of an accident previouly evaluated because it decreases the RBM setpoint for Unit I to be consistent with the Rod Withdrawal Errors analysis already performed and accepted for Unit 1 Cycle 2 reload.

2) Create the possibility of a new or different kind of accident from any accident previously evaluated because the Rod Withdrawal Error has already been analyzed for Unit 1 Cycle 2 reload in the determination of the MCPR operating limit.

3) Involve a significant reduction in the margin of safety because the Rod Withdrawal Error is already analyzed for Unit 1 Cycle 2 reload in the determination of the MCPR operating limit.

Based on the preceding discussion, it is concluded that the proposed l system change clearly falls within all acceptable criteria with respect to the system or component, the consequences of previously evaluated accidents will not be increased and the margin of safety will not be decreased. Therefore, based on the guidance provided in the Federal Register and the criteria established in 10 CFR 50.92(e), the proposed change does not constitute a j significant hazards consideration.

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