ML20099C975

Suppls 911011 Application for Amends to Licenses NPF-11 & NPF-18,changing TS Surveillance Requirement 4.6.1.2 Re Primary Containment Leakage Rates,Per Discussions W/Nrc. Introductory Clause for SR Placed in Body of Clause

ML20099C975
Person / Time
Site:	LaSalle
Issue date:	07/31/1992
From:	Shields J COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20099C977	List: ML20099C975 ML20099C979
References
NUDOCS 9208050013
Download: ML20099C975 (2)

Text

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1400 opus Place Edison 2c

. Downers Grove, Illinois 60515 July 31,1992 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20S55 Attn: Document Control Desk

Subject:

LaSalle County Station Units 1 and 2 Pending Request for Amendment to Facility Operating Licenses NPF 11 and NPF-18, App (ndix A, Technical Specifications

. Surveillance Requirement 4.6.1.2 NRC_DocketNos 50-373 and.50 37A

Reference:

(a) P.L. Piet letter to USNRC, dated October 11,1991, LaSalle County Station Unit 2 Request for One-time Exemption from Appendix J, to 10 CFR Part 50 Accelerated Type A Testing Requirements and Request for Amendment to Facility Operating Licenses NPF-11 and NPF-18, Appendix A, Technical Specification Surveillance Requirement 4.6.1.2

Dear Dr. Murley:

In the referenced letter, Commonwealth Edison (CECO) aroposed to amend Apaendix

_ A, Technical Specification 4.6.1.2 of Facility Operating L cens 43 NPF-11 and N 'F-18 to state that the surveillance requirement would be performed in accordance with 10 CFR-50 Appendix J, subject to any exemptions granted by the Commission.

In our submittal, CECO inserted text at the end of the introductory clause for Surveillanca Rnauirement 4.6.1.2. In subsequent discussions with your staff,it was

noted thrt the proposed clause would be better placed in the body of the introductory clause, LaCaile has determined that it is aweptable to relocate the inserted text to the body or tha introductory clause. This change is consistent with the intent of the original submittal, and the co ,musions reached in the Significant Hazards Consideration Evaluation provided with the original submittal remain valid.

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- Dr. Thomas E. Murley -

2- July 31,1992 l 1

Attached are marked up pages for both the Unit 1 and Unit 2 licenses reflecting the relocation of this insert.

If there are any questions, please direct them to this office.

Sincerely,-

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JoAnn Shields Nuclear Licensing Administrator cc: A.B. Davis, Regional Administrator - Rlli B.L. Siegel, Project Manager - NRR D.L. Hills, Senior Resident inspector - LaSalle Office of Nuclear Facility Sately -IDNS 4

- ZNLD/1930/6

., CONTAINMENT SYSTEMS

' LIMITING COND1rION FOR OPERATION (Continued)

. ACTION: (Continued) restore:

a. - The overall integrated leakage rate (s) to less than or equal to 0.75 L,, and

b. The combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main. steam isolation valves and valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type 8 and C tests to less than or equal to 0.60-L,, and

c. The leakage rate to less than or equal to 100 scf per hour for all four main steam lines through the isolation valves, and

d. The combined leakage rate for all ECCS and RCIC containment isolation valves in hydrostatically tested lines which penetrate the primary containment to less than or equal to 1 gpm times the total number of such valves, prior to incressing reactor cool, ant.- systerg . temperature above 240- Fr '-n u x

{-b' t -:.e ., , I o u q ta,a "a rs., t d by h %wew> enij SURVEILLANCE REQUIREMENTS 4_ . 4 . - .

4.6.1.2 The primary containment leakage rates shall be demonstrated at the following test schedule and shall be deter ined in conformance with the criteria specifiedinAppendixJof.10CFRPart50s/singthemethodsandprovisionsofANSI u

N45,4-1972:

a. Three- Type A Overall Integ ated Containment Leakage Rate tests shall be c.onducted at 40 t 10 month intervals during shutdown ai. Pa ' '

39.6 psig, during each 10 year service period. The third test-of each set shall be conducted during the shutdown for the 10 year

-plant inservice inspection.

_g ocy c b. If any periodic Type A test fails to meet 0.75 L,, the test schedule f k g. c.q for subsequent Type A tests shall be reviewed and approved by the Commission. If two t.onsecutive Type A tests fail to meet 0.75 LB , a

~ gy;,u f m , s %-Type .r ~ A- test

~p&shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 L,, at which time the above test

[ 3 rah d b] ,

schedule may be resumed.

l { $(bwsuoy Q A L- T. The accuracy of each Type A test shall be verified by a supplemental l

l test which:

h 1. -Confirms tha accuracy of the test by verifying that the j- difference between the supplemental data and the Type A test data is within 0.25 L,.

2. Hr.s duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.

3. Requires the quantity of gas injected into the ccntainment or bled from the containment during the supplemental test to be equivalent to at least 25% of.the total measured leakage at P,, 39.6 psig.

l LA SALLE - UNIT 2 3/4 6-3 i

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