ML20235J296

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Proposed Tech Specs,Allowing Removal of Main Steam Line Isolation from Main Steam Tunnel Temp & Differential Temp Sensors
ML20235J296
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 07/10/1987
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20235J272 List:
References
3317K, NUDOCS 8707150482
Download: ML20235J296 (14)
v • d • e


Text

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ATTACHMENT B PROPOSED CHANGES TO THE TECHNICAL SPECIFICATIONS FOR OPERATING LICENSES NPF-11 AND NPF-18 l

l REVISED PAGES:

NPF-11 NPF-18 3/4 3-11 3/4 3-11 3/4 3-14(a) 3/4 3-14(a) 3/4 3-15 3/4 3-15 3/4 3-18 3/4 3-18 3/4 3-20 3/4 3-20 B7071504gg 97ay39 DR p ADOCK 05000373 PDR

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NOTES (Continued)

(g) Requires RCIC steam supply pressure-low coincident with drywell pressure-high.

(h) Manual initiation isolates 1E51-F008 only and only with a coincident _

eactor vessel water level-low, level 2, signal. )

) Bo1.n uimun is vi enun wig oy nem may oe piacea in an inoperable status for u}

to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for required reactor building ventilation filter change and damper I cycling without placing the trip system in the tripped condition provided that the ambient temperature channels in the same trip. systems are operable.

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LA SALLE UNIT-1 3/4 3-14 (a) Amendment No.26

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, TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)#

A. AUTOMATIC INITIATION

1. PRIMARY CONTAINMENT ISOLATION
a. Reactor Vessel Water Level
1) Low, Level 3 NA
2) Low Low, Level 2 < 13(a) 3)- Low Low Low, Level 1 7 1.0*/< 13(a)w*
b. Drywell Pressure - High' b13(a)-

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c. Main Steam Line
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2) Pressure - Low 7 2.0*R 13(a),*
3) Flow - High 7 0.5* R 13(") ,

Main Steam Line lunnel Temperature - High d [. p. Condenser vacuum - Low. NA neln steam Line lunnel a Temperature nign Im

{ T.

2,- SECONDARY CONTAINMENT ISOLATION

a. ReactorBuildinggntExhaustPlenum Radiation - High < 13(a,)
b. Drywell Pressure - High
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7 13

d. FuelPoolVentExhaustRadiation-High(g) 513(aj
3. REACTOR WATER CLEANUP SYSTEM ISOLATION
a. A Flow - High 5 13(a)##
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 f 1 13 ")
4. ._ REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION
a. RCIC Steam Line Flow - High < 13(a)###
b. RCIC Steam Supply Pressure - Low 513(a)
c. RCIC Turbine Exhaust. Diaphragm Pressure - High NA
d. RCIC Equipment Room Temperature - High NA
j. 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
5. RHR SYSTEM STEAM CONDENSING MODE ISOLATION l a. RHR Equipment Area a Temperature - High NA O e-c.

a"a aree ceoler Temperature - 840 "

RHR Heat Exchanger Steam Supply Flow High "a

NA LA SALLE.- UNIT 1 3/4 3-18 Amendment No.EC

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V TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME j TRIP FUNCTION RESPONSE TIME (Seconds)#

A. AUTOMATIC INITIATION

1. PRIMARY CONTAINMENT ISOLATION
a. Reactor Vessel Water Level
1) Low, level 3
2) Low Low, Level 2 N.A(a) 1 13 a)**
3) Low Low Low, Level 1
b. Drywell Pressure - High 11.g<13.0 (13
c. Main Steam Line ,,
1) Radiation - High(b) 11.0*/ 113 ,,
2) Pressure - Low <2.0*/<13
3) Flow - High 20.5*/713(a),,

(d. ___ Main steam Line tunnel Temperature - Hiah E.A. _~

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d*e Condenser Vacuum - Low N.A.

ii. A

{ nain Steam Line lunnel a t emperature - tilgn

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a. ReactorBuildinggntExhaustPlenum o Radiation - High <13(a)

Q b.

c.

Drywell Pressure - High Reactor Vessel Water Level - Low, Level 513fa

<13 a

d. FuelPoolVentExhaustRadiation-High(f) 513(")
3. REACTOR WATER CLEANUP SYSTEM ISOLATION
a. A Flow - High $ 13(a)##
b. Heat Exchanger Area Temperature - High N.A. .
c. Heat Exchanger Area Ventilation AT-High N.A. I
d. SLCS Initiation N.A
e. Reactor Vessel Water Level - Low Low, Level 2 513(")
4. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION
a. RCIC Steem Line Flow - High <13(a)##
b. RCIC Steam Supply Pressure - Low 513(a)
c. RCIC Turbine Exhaust Diaphragm Pressure - High N.A.
d. RCIC Equipment Room Temperature - High N.A.
e. RCIC Steam Line Tunnel Temperature - High N.A.
f. RCIC Steam Line Tunnel Temperature - High N. A.
g. Drywell Pressure - High N.A.
h. RCIC Equipment Room A Temperature - High N.A.
5. RH_R SYSTEM STEAM CONDENSING MODE ISOLATION

/^ a. RHR Equipment Area temperature - High N.A.

(.)g b. RHR Area Cooler Temperature - High N.A.

c. RHR Heat Exchanger Steam Supply Flow High N.A.

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o ATTACHMENT 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 10CFR50.92 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 previously evaluated because:

Section 15.2.4 of the UFSAR provides the safety analysis for inadvertent MSIV closure. MST temperature trips are a potential cause of spurious MSIV closures therefore, by removing the '

temperature trips the risk of.an inadvertent MSIV closure will be l reduced.

The safety analysis for steam system break outside of the containment (UFSAR 15.6.4) assumes that a main steamline instantaneously and circumferential1y breaks at a location downstream of the outermost l isolation valve. Therefore the analysis'does not take into account the ability to detect small steam leaks in the MST.

1- 2) Create the possibility of a new or different kind of accident from any l L

accident previously evaluated because:

1:

l The safety evaluation in section 15.6.4 of the UFSAR does not include l an analysis of small steam leaks. The only analysis is for a )

catastrophic failure of a main steamline which represents the  !

envelope evaluation of steamline failures outside of the containment.

3) Involve a significant reduction in the margin of safety because:

Analysis has shown that the decrease in the margin of safety due to removal of the MST temperature trips is insignificant. The small ,

increase in risk to plant safety due to small steam line breaks which )

4 quickly propagate to large breaks is'more than offset by the reduction in risk to plant safety posed by the challenges to plant safety systems caused by spurious MSIV cosures.

The MST high temperature alarms will be retained to provide early I warning for small steam leaks outside of the containment. l3 I

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Guidance has been provided in the Federal Register Volume 51 (reference (b)), for the application of standards to license change requests for determination of the existence of significant hazards considerations.

That document provides examples of amendments which are and are not considered likely to involve significant hazards considerations.

This proposed amendment does not involve a significant relaxation of the criteria used to establish safety limits, a significant relaxation of the bases for the limiting safety system settings or a significant relaxation of the bases for the limiting conditions for operations. Therefore, based on the guidance provided in the Federal Register and the criteria established in 10CFRSO.92(e), the proposed change does not constitute a significant hazards consideration.

This proposed amendment most closely resembles example e. (vi) on page 7751, "a change which either may result in some increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, but where the results of the change are clearly within all acceptable criteria with respect to the system or component specified in the Standard Review Plan, eg, a change resulting from the application of a small refinement of a previously used calculational model or design method."

ATTACHMENT D RISK-BASED EVALUATION OF TECHNICAL SPECIFICATION PROBLEMS AT THE LASALLE COUNTY NUCLEAR STATION EPRI Research Project 2142-2 Section 1.0 Introduction.

2.0 General Approach for Applying Probabilistic Methods In Technical Specification Improvement Activities.

4.0 Main Steam Tunnel Ambient and Delta Temperature Trip (Tech Spec 3.3.2).

6.0 Summary and conclusions.

7.0 Data Analyis.

App. B MST Temperature Trips Supplemental Analysis.

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