ML20137C316

Proposed Tech Spec Changing Instrument Response Time for Main Steam Line Low Pressure Trip Function in Table 3.3.2-3 from 1 to 2

ML20137C316
Person / Time
Site:	LaSalle
Issue date:	01/09/1986
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20137C303	List: ML20137C299 ML20137C316
References
0892K, 892K, NUDOCS 8601160276
Download: ML20137C316 (3)

Text

,_

s ATTACHMENT B PROPOSED CHANGE TO APPENDIX A TECHNICAL SPECIFICATION TO OPERATING LICENSE NPF-11 REVISED PAGE: 3/4 3-18 0892K 8601160276 860109 PDR ADOCK 05000373 PDR p

d

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

TABLE 3.3.2-3

(' ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION , RESPONSE TIME (Seconds)#

A. AUTOMATIC INITIATION

1. PRIMARY CONTAINMENT ISOLATION d 2. O

a. Reactor Vessel Water Level

1) Low, Level 3 NA -

b.

2) Low Low, Level 2 Drywell Pressure - High i 11.g113(,),, -

1 13

c. Main Steam Line

1) Radiation - High(b) < 1.0*/< 13(*)**

2) Pressure - Low 7 1.0*R 13(*a),,.

3) Flow - High 7 0.5*R 13C )**

~

d. Main Steam Line Tunnel Temperature - High NA re. Condenser Vacuum - Low NA

f. Main Steam Line Tunnel A Temperature - High NA 2

2. SECONDARY CONTAINMENT ISOLATION

a. ReactorBCdingIgntExhaustPlenum Radiation - High < 13(a)

b. Drywell Pressure - High

c. Reactor Vessel Water Level - Low, Level (g) 7 i 1313(C*)

a) ,

d. Fuel Pool Vent Exhaust Radiation - High 513(a) ,

3. REACTOR WATER CLEANUP SYSTEM ISOLATION

a. A Flow - High < 13(*)"

b. Heat Exchanger Area Temperature - High NA

c. Heat Exchanger Area Ventilation AT-High NA

d. 'SLCS Initiation NA

e. Reactor Vessel Water Level - Low Low, Level 2 1 13(a) l

i. 4. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION

~

a. RCIC Steam Line Flow - High- < 13C *) "

b. RCIC Steam Supply Pressure - Low 513(a),

c. RCIC Turbine Exhaust Diaphragm Pressure - High NA

d. RCIC Equipment Room Temperature - High NA

e. RCIC Steam Line Tunnel Temperature - High NA

f. RCIC Steam Line Tunnel A Temperature - High NA

g. Drywell Pressure High NA

h. RCIC Equipment Room A Temperature - High NA g

5. RHR SYSTEM STEAM CONDENSING MODE ISOLATION i

a. RHR Equipment Area A Temperature - High NA

b. RHR Area Cooler Temperature - High NA

c. RHR Heat Exchanger Steam Supply Flow High NA LASALLE UNIT-1 3/4 3-18 Amendment No. 26

- . ,,,,v. - - - , - - ,

,+

ATTACMMENT C SIGNIFICANT HAZARDS CONSIDERATION Commonwealth 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 CFR 50.92, operation of LaSalle County Station Unit 1 in accordance with the proposed amendment will not:

1) Involve a significant hazards increase in the probability or consequences

, of an accident previously evaluated because the revised response time for the main steam line low pressure switches is bounded by the original analysis performed by General Electric for pressure regulatory failure-high.

2) Create the possibility of a new or different kind of accident from any accident previously evaluated because no new accident is possible by the required response time. No plant equipment is removed.

3) Involve a significant reduction in the margin of safety because the original design function is not affected and the increased response time is bounded by the original analysis.

Based on the preceding discussion, it is concluded that the proposed system change clearly falls within all acceptable criteria with respect to the system of 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(c), the proposed change does not constitute a significant hazards consideration.

0892K

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