ML20058P210

Proposed TS Table 3.6.3-1, Pcivs, Reflecting New Pcivs, Per NRC Bulletin 93-003

ML20058P210
Person / Time
Site:	LaSalle
Issue date:	10/18/1993
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20058P208	List: ML20058P204 ML20058P210
References
IEB-93-003, IEB-93-3, NUDOCS 9310220155
Download: ML20058P210 (8)

Text

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-- ATTACHMENT B :l ,

PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS NPF-11 NPF-18 3/4 6-34 3/4 6 ~

Insed A Insed B i

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.1 9310220155 931018 PDR E 1 ADOCK 05000373 fe'l

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, TABLE 3.6.3-1 (Continued) i 2

g PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER h

Other Isolation Valves (Continued)

U 7. Post LOCA Hydrogen Control 1HG001A, B 1HG002A, B 1HG005A, B 1HG006A, B

8. Standby Liquid Control System IC41-F004A, B -

IC41-F007

9. Reactor Recirculation Seal Injection m

O 1833-F013A,B(d) =

IB33-F017A,B(d)  :

10. Drywell Pneumatic System -

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ATTACHMENT B l PROPOSED AMENDMENTS TO THE LICENSEfrECHNICAL SPECIFICATIONS  ;

i INSERT A  !

Unit 1  !

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11. Reference Leo Backfill (*' i t

1C11-F422B 1C11-F422D l 1C11-F422F j 1C11-F422G  ;

i 1C11-F423B 1C11 F423D 1C11-F423F 1C11-F423G  !

(PTwo check valves in series perform the outboard containment isolation function. ,

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TABLE 3.6.3-1 (Continued) g p PRIMARY CONTAINMENT ISOLATION VALVES

% VALVE FUNCTION AND NUMBER i

Other Isolation Valves (Continued)

E 7. Post LOCA Hydrogen Control N 2HG001A, B 2HG002A, B 2HG005A, B 2HG006A, B

8. Standby Liquid Control System 2C41-F004A, B 2C41-F007 5 9. Reactor Recirculation Seal Injection Cl de 2B33-F013A, B f3)

" 2833-F017A, B U) -

10. Drywell Pneumatic Valves 21N018 g H. IN SE RT S h J T

,4-___ m _s-w _ ---u,_ c , m-, - -.s .--r--,-d- e e -e- * * = - - -, = uw-- ,e , . . .ru- ., , , ,. , ,, m-w- .,

ATTACHMENT B PROPOSED AMENDMENTS TO THE LICENSE / TECHNICAL SPECIFICATIONS INSERT B Unit 2

11. Reference Lea Backfill" 2C11-F422B 2C11-F422D 2C11-F422F 2C11-F422G 2C11-F423B 2C11-F423D 2C11-F423F 2C11-F423G WTwo check valves in series perform the outboard containment isolation function.

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s ATTACHMENT C  :

SIGNIFICANT HAZARDS CONSIDERATION i

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. 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:

This is an administrative change to add components to the list of Primary Containment isolation Valves, Table 3.6.3-1. Adding components to this component list does not change the probability of any accident initiators or l change any other relevant initial assumptions. Also, there is no change to the consequences of an accident previously evaluated, because' adding these  !

isolation valves to Table 3.6.3-1 does not change either the on-site or off-site  ;

dose consequences resulting from the event. Therefore, there is no increase in either the probability or consequences of an accident previously evaluated.  !

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2) Create the possibility of a new or different kind of accident from any accident previously evaluated because:

i This is an administrative change to add primary containment isolation valves to the list of Primary Containment isolation Valves to Table 3.6.3-1 of LaSalle Unit 1 and Unit 2 Technical Specifications. The addition of these valves will  ;

assure the valves are maintained and controlled as primary containment isolation valves to assure the design and operation of the plant will continue to  !

be in accordance with the UFSAR, Facility License and the associated .

Technical Specifications. Therefore, the possibility of a new or different kind of accident from any previously evaluated b not created.

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

i The addition of the new primary containment isolation valves to Technical  ;

Specification Table 3.6.3-1 is an administrative change only and there is no l reduction in the margin of safety. ,

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i ATTACHMENT C ,

SIGNIFICANT HAZARDS CONSIDERATION L

Guidance has been provided in " Final Procedures and Standards on No Significant Hazards Considerations," Final Rule,51 FR 7744, for the application of standards to license change requests for determination of the existence of significant hazards  ;

considerations. This document provides examples of amendments which are and are not considered likely to involve significant hazards considerations. These proposed amendments most closely fit the example of a of an administrative change to the Technical Specificaticas. New primary containment isolation valves are being added to Table 3.6.3-1, Prsmary Containment isolation Valves, to assure proper maintenance and test of the new valves. .

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 lirniting safety system settings or a signincant relaxation of the bases for the limiting ,

conditions for operations. Therefore, based on the guidance provided in the Federal Register and the criteria established in 10 CFR 50.92(c), the proposed change does ,

not constitute a significant hazards consideration.

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ATTACHMENT D ENVIRONMENTAL ASSESSMENT STATEMENT APPLICABILITY REVIEW Commonwealth Edison has evaluated the proposed amendment against the criteria for the identification of licensing and regulatory actions requiring environmental assessment in accordance with 10CFR51.21. It has been determined that the proposed changes meet the criteria for categorical exclusion as provided for under 10CFR51.22(c)(9). This determination is based on the fact that these changes are being proposed as amendments to licenses issued pursuant to 10CFR50. These proposed changes involve no significant hazards consideration, and neither a significant change in the types nor a significant increase in the amounts of any effluents that may be released offsite. In addition, this amendment request does not invovie a significant increase in individual or cumulative occupational radiation exposure.

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