ML20154R844

Application for Amends to Licenses NPF-11 & NPF-18,changing Tech Specs to Reflect Addition of Backup Overload Protection Devices.Fee Paid

ML20154R844
Person / Time
Site:	LaSalle
Issue date:	03/21/1986
From:	Allen C COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20154R848	List: ML20154R844 ML20154R851
References
1447K, NUDOCS 8603310214
Download: ML20154R844 (4)

Text

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C:mm:nvicstth Edison Y2 One First National Plaza. Chicago. Illinois -

C/" Address Reply to: Post Othce Box 767 Chicago, llhnois 60690 March 21, 1986 Mr. Harold R. Denton, L3 rector Office of Nuclear Reactorc Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

LaSalle County Station Units 1 and 2 Proposed Amendment to Technical Specification for Facility Operating License NPF-11 and NPF-18 Primary Containment Penetration Conductors Overcurrent Protective Devices NRC Docket Nos. 50-373 and 50-374

Dear Mr. Denton:

i Pursuant to 10 CFR 50.90, Commonwealth Edi on proposes to amend i Appendix A, Technical Specification, to Facility Operating License NPF-11 and NPF-18. This amendment change is being submitted for your staff's review and approval.

The proposed amendment reflects the addition of backup overload protection devices required to satisfy License Condition NPF-11 2.C.23. This change incorporates both the primary and backup breakers into the Unit 1 i Technical Specification for NPF-11. In addition the backup breakers (which had previously been installed on Unit 2) are added to the Unit 2 Technical Specifications NPF-18.

Attachment A provides background and discussion. The proposed change is enclosed in Attachment B. The attached change has received both On-Site and off-Site review and approval. We have reviewed this amendment request and find that no significant hazards consideration exists. Our review is documented in Attachment C.

Commonwealth Edison is notifying the State of Illinois of our request for this amendment by transmitting a copy of this letter and its attachments to the designated State Official.

i In accordance with the requirements of 10 CFR 50.170, a fee j remittance in the amount of $150.00 is enclosed.

80 pl W#

9603310214 860321 yp PDR ADOCK 05000373 p PM 3

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H. R. Denton March 21, 1986 Please direct any questions you may have concerning this matter to this office.

Three (3) signed originals and thirty-seven (37) copies of this transmittal and its attachments are provided for your use.

Very truly yours,

()/y OfL '

y a C. M. Allen Nuclear Licensing Administrator bs Attachments A: Background and Discussion B: Technical Specification Changes to NPF-11 and NPF-18 C: Evaluation of Significant Hazards Consideration cc: Region III Inspector - LSCS A. Bournia - NdR M. Parker - State of Ill.

SUBSCRIBED AND SWORN to before me this .0/ M day of Y//b/ , 1986 1k 1 (lLV

~ Notary Public j 4

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Attachment A LaSalle County Station Unit 1 and 2 Technical Specification Change Request

Subject:

Primary Containment Penetration Conductor '

Overcurrent Protection Devices

References:

(a) Technical Specification 3.8.3.2 (pages 3/4 8-22 thru 3/4 8-25)

(b) NUREG-0123, GE-STS (BWR/5) Standardized Technical Specifications (c) FSAR Question 40.106 (d) SSER Supplement 5 Item 1.10(7)(1)

(e) Byron Technical Specification 3/4 8.4.1 (f) License condition NPF-11 2.C.23 (g) Regulatory Guide 1.63 (h) SER 8.4.1

Background:

The license condition (Reference (f)) identified in Reference (h) which required reactor containment electrical penetrations' redundant fault current devices was not issued om LSCS Unit 2 (Reference (d)) due to installation of the subje:t devices on that unit. Installation of these devices will be completed in Unit 1 during the first refueling outage.

Backup overload protection is required for energized circuits which pass through the containment electrical penetrations (Reference (g)). Both the primary and the backup breakers should be included in Table 3.8.3.2-1. The backup breakers while actually installed in Unit 2 were not reflected in the Unit 2 specification, as issued.

Discussion: The revisions included in the proposed amendment (Attachment B) specifically indicate the primary and backup breakers. Table 3.8.3.2-1 indicates the newly installed breakers in Unit 1 and clarifies the existing installation for Unit 2. Actions a and b have been revised to clarify the actions required to deenergize a circuit. The same actions apply to 6.9 kV, 4.16 kV or 480 volt breakers. There is no nerj to provide different actions for different breaker voltages. appropriate actions for other systems which may be affected by this action (i.e.,

deenergizing the circuit) will be taken, however there is no need to explicity state it in the specification action statement.

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l The " TRIP SETPOINT" and " RESPONSE TIME" information has been '

deleted from Table 3.8.3.2-1. This information is no longer required in the GE STS (Reference (b)). The information provided in those columns represented nominal trip setpoints which are well below the design current of the penetrations

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(Reference (c)). Changes to these setpoints are periodically j required due to motor changes or other reasons. These changes are reviewed to ensure that they remain within the penetration design limits, so the requirement to include these setpoints in the specification is unnecessary. The procedures to check these values reference the proper vendor manuals / graphs to

ensure proper breaker operation within design limits.

6 The surveillance requirements have been revised, as appropriate, to reflect the revised Table 3.8.3.2-1. Surveillance 4.8.3.2.a.2 has also been revised to specify a maximum response time limit. There is no need to specify a minimum time limit since the safety concern is related to a combination of excessive time and current that a fault is allowed to exist.

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