ML20112G309

Application for Amends to Licenses NPF-11 & NPF-18,extending Deadline Until 851130 for Full Compliance w/10CFR50.49 Re Environ Qualification of Electrical Equipment.Justification Encl.Fee Paid

ML20112G309
Person / Time
Site:	LaSalle
Issue date:	01/08/1985
From:	John Marshall COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
9593N, NUDOCS 8501160291
Download: ML20112G309 (6)

Text

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r N Commonwealth Edison

/ One First Nati:nal Pl*za, Chic go, Illinois

( T } Address Reply to: Post Othee Box 767 N

j Chicago, Illinois 60690 January 8, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor 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-ll and NPF-18 Concerning Extension of Deadline for Environmental Qualification of Electrical Equipment EC Docket Nos. 50-373 and 50-374 References (a): Facility Operating License NPF-11 Condition 2.C.ll.

(b): Facility Operating License NPF-18 Condition 2.C.5.

(c): January 8, 1985 letter from J. G. Marshall to H. R. Denton:

Dear Mr. Denton:

Pursuant to 10 CFR 50.59, Commonwealth Edison proposes to amend Appendix A, Technical Specification, to Facility Operating License NPF-11 and NPF-18. These amendment changes are being submitted for your staff's review and approval.

The proposed change is enclosed in Attachment 1. The attached change has received both On-Site and Off-Site review and approval. We have reviewed this amendnent request and find that no significant hazards conside-ration exists. Our review is documented in Attachment 2. 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.

This proposed change extends the deadline for full compliance with 10 CFR 50.49 (Environmental Qualification of Electrical Equipment) to November reference30,)1985.

(c . Justification for the proposed extension is provided in I

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~ * .:H. R. Denton- January 8, 1985 In accordance with 10 CFR 170, a fee remittance of $150.00 is 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, h%

.4 . J. G. Marshall Nuclear Licensing Administrator -

Attachments (1)i Technical Specification Changes to NPF-ll and NPF-18

. (2): Evaluation of Significant Hazards Consideration cc: Region.III. Inspector - LaSalle

-A. Bournia - teR G. Wright - Ill.

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COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-373 LA SALLE COUNTY STATION, UHIT 1 AMENDMENT TO FACILITY OPERATING LICENSE License No. NPF-11 Amenoment No. 4

1. The Nuclear Regulatory Comission (the Commission or the NRC) having found that:

f A. The application for license by the Commonwealth Edison Company (Itcensee),

, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act). and the Comission's regulations set forth in 10 CFR Chapter 1; B. The facility will operate in conformity with the appitcation as amended, the provisions of the Act, and the regulations of the Comission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the pubitc, and (11) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the pubitc; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2. Accordingly, paragraph 2.C.(1), 2.C.(11), 2.C.(32), 2.C(33), 2.0, 2.F and 2.H of the Facility Operating License No. NPF-11 is hereby amended to read as follows:

(1) Maximum Power Level -

The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3323 megawatts thermal).

(11) Environmental Qualifications (Section 3.11, SER, SSER #1, SSER #2)_

J.A)dolatertha rch 31, 1985 licensee shall ,

complia with the pro ons of NUREG-05 nterim Staf Posi n on Enviro al Qualifica f Safety-Re1 .

E trical Equ nt", for saf -related electr equipment xposed to arsh enviro t.

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lete udita records must be,av e and tained at

' a ce oca which describe,t ' vironme qualificatto n ds use r all safety-r d electr,i equipment in cient etail ocument the, e of compi e with NUREG- Such , /

/reco shall be u d and mai ed current a ipment is r aced, fur tested, or rwise furthe alified ocument omplete liance no I r than March 31 985.

(32) Vacuum Breaker Yalves Prior to November 1,1982, the licensee shall complete a test and shall submit its evaluation of the results which confirm the capability of the vacuum breaker valves to withstand the opening and closing forces associated with pool swell.

(33) Heating-Ventilation and Air Condition Systems (a) Prior to exceeding 5% power operation, the licensee must provide fomal documentation of information regarding HVAC design fabri-cation and installation, discussed 11 meetings with the NRC on August 2 and 4, 1982.

(b) Prior to exceeding 50% power operation, the licensee shall submit the results of an independent review acceptable to the NRC staff of the HVAC system, including design changes, fabtication, and installation. The review shall encompass all saftty-related HVAC systems and the effect of non-safety related HVAC system failures on safety systems.

D. Exemptions from certain requirements of Appendices G, H and J and 10 CFR Part 73 are described in the Safety Evaluation Report and Supplement No.1, No. 2 and No. 3 to the Safety Evaluation Report. In addition, an exemption was requested until the completion of the first refueling from the require-ments of 10 CFR 570.24 and an exemption from 10 CFR Part 50, Appendix E from perfoming a full scale exercise within one year before issuance of an operating license, both exemptions are described in Supplement No. 2 of the Safety Evaluation Report. These exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest. Therefore, these exemptions are hereby granted. The facility will operate, to the extent authorized herein, in conformity with the application, as amended, and the rules and regulations of the Commission (except as hereinafter exempted therefrom), and the provisions of the Act.

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( (4) Ir..;ervice Testing of Pumps and Valves (Section 3.9.6, SER*)

Pursuant to 10 CFR Part 50.55a, the relief ic'entified in the submittals dated February 18, 1983, August 2, 1983, and November 12,1983 that the licensee has requested from the pump and valve testing requirements of 10 CFR Part 50, Section 55.55a(g)(2) and (g)(4)(i) is granted for that portion of the initial 120-month period during which the staff completes its review.

(5) Environmental Qualifications (Section 3.11, SER, SSER #1, SSER #2) tevtebc Prior toh:artun after the first refueling outage but not S*i d later than%rt5-t9BD the licensee shall environmentally qualify all electrical equipment as required by 10 CFR 50.49.

(6) Surveillance of Control Blade (Section 4.2.3.14, SER)

IE Bulletin No. 79-26, Revision 1, " Boron Loss from BWR Control Blades," describes certain actions to be taken by licensees to determine boron loss from BWR control blades. The licensee shall comply with items 1, 2 and 3 of this bulletin and submit a written response on item 3 within 30 days after plant startup following the first refueling outage.

(7) Low Pressure in Pum) Discharge of the Control Rod Drive (Section 4.6.2, 55E l #2, and Section 7.2.3.2, 55ER #/)

Prior to completion of the startup test program, the licensee shall install instrumentation that would automatically shut down the reactor in the event of low control rod drive pump discharge pressure. This automatic scram shall be activated during startup and refueling modes only.

(8) Containment Isolation System (Section 6.2.1.1, SSER #2 and Section 3.9.3.1, 55ER #5, SSER #6)

Prior to startup af ter the first refueling outage, the licensee shall replace the eight 26-inch and two 8-inch vent and purge isolation valves with valves that can close in 10-seconds or less and that do not require AC power to close.

• The parerthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed. ,

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COMMONWEALTH EDISON COMPANY ATTAC M 2 SIGNIFICANT HAZARDS CONSIDERATION

_ Commonwealth Edison has evaluated the proposed License 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 amendment is requested for the purpose of continuing the use of presently analyzed and installed equipment.

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

This amendment does not authorize the introduction of any new equipment i

. or systems into the plant.

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

All unqualified equipment covered in this' amendment has been justified as acceptable for interim operation.

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

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