ML20059J463

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Notice of Consideration of Issuance of Amends to Licenses NPF-11 & NPF-18 & Proposed NSHC Determination & Opportunity for Hearing.Amend Relates to Hardware Implementation Per NRC Bulletin 93-003, Resolution of Issues Re Rwl...In Bwrs
ML20059J463
Person / Time
Site: LaSalle  
Issue date: 11/03/1993
From: Lynch M
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20059J467 List:
References
IEB-93-003, IEB-93-3, NUDOCS 9311120215
Download: ML20059J463 (10)


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UNITED STATES NUCLEAR REGULATORY COMMISSION COMMONWEALTH EDISON COMPlgil DOCKET NOS. 50-373 AND 50-374 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENTS Tjl FACILITY OPERATING LICENSES. PROPOSED NO SIGNIFICANT HAZARDS

@ NSIDERATION DETERMIFATION. AND OPPORTUNITY FOR A HEARING The U.S. Nuclear Regulatory Comission (the Chrnission) is considering issuance of amendments to Facility Operating License Nos. NPF-11 and NPF-18, issued to the Comonwealth Edison Company (the licensee), for operation of the l

LaSalle County Station, Units I and 2, located in LaSalle County, Illinois.

The proposed amendments would add a total of eight valves in a new category to Table 3.6.3-1, " Primary Containment Isolation Valves," of the LaSalle Technical Specifications (TS). The new category will be " Reference Leg Backfill" and will consist of two containment isolation devices which are 4

i simple check valves, in each of four backfill lines added to the reference legs of the Reactor Vessel level Instrumentation System (RVLIS). The subject reference legs are those which provide an input to the instruments which, in turn, provide actuation signals to various engineered safety features (ESF)

I including signals which would open the safety relief valves (SRV) on the main steamlines and signals which would initiate operation of various emergency core cooling systems (ECCS).

I There are two other reference legs in the LaSalle RVLIS which provide indication only of the reactor vessel water level and do not provide actuation signals to the station's ESFs. These latter reference legs also will have l

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backfill lines but do not, by design, require any additional containment isolation devices.

The addition of six backfill lines to each of the two units of LaSalle is in respcnse to the NRC's request in NRC Bulletin 93-03, " Resolution of Issues Related to Reactor Water Level Instrumentation in BWRs," dated May 28, 1993 (Bulletin). The Bulletin requested each affected licensee to implement hardware modifications necessary to ensure that the RVLIS design is of high functional reliability for long-term reliability. The purpose of these proposed hardware modifications is to provide a continuous supply of degessified water from the Control Rod Drive (CRD) system which will be injected into the six RVLIS reference lines, thereby eliminating a potential source of error in the indications of the reactor vessel water level. This indication error could occur either during a rapid depressurization event or during depressurization while undergoing a normal reactor cocidown as discussed in the Bulletin.

Before issuance of the proposed license amendments, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations.

Pursuant to 10 CFR 50.91(a)(6), for amendments to be granted under exigent circumstances, the NRC staff must determine that the amendments requested involve no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendments would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different i

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.. i kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:

Commonwealth Edison has evaluated the proposed Technical Specification Amendment and determined that it does r.ot 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 I and 2 in accordance with the proposed amendment will not:

Involve a significant increase in the probability or consequences of an i

accident previously evaluated because:

The proposed change to Technical Specification Table 3.6.3-1 is administrative in nature. Adding components to Table 3.6.3-1 does not change the probability nor does it change the consequences of any previously evaluated accident for LaSalle County Station.

i The proposed modifications for the reference leg backfill instrument lines do not increase the probability of any previously evaluated accidents for LaSalle County Station. For the indication only reference legs, the inadvertent closure of a root valve does not significantly increase the consequence of any previously evaluated accident as a result of the proposed plant modifications.

The proposed plant modifications for the reference leg backfill check valves will not increase the radiological consequences of any previously evaluated accident. The radiological impact from a reference leg backfill instrument line break is bounded by LaSa11e's Instrument Line Break analysis (UFSAR Section 15.6.2). Thercfore, the proposed plant changes will not increase the consequences of any previously evaluated accident.

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

The proposed modification connects the non-safety-related CRD system to each safety-related division of RPV instrumentation. The failure of the CRD piping may result in instrument line leakage. However, this event is mitigated by the isolatica action of the reference leg backfill check valves. These check valves are classified as safety-related and will be maintained and controlled such that overall plant safety is maintained. The addition of the reference leg backfill valves to the Technical Specifications is administrative in

n-nature and does not create the possibility of a new or different kind of accident for LaSalle Station.

Involve a significant reduction in the margin of safety because:

The proposed change to Technical Specification Table 3.6.3-1 to include the reference leg backfill valves is administrative in nature.

Primary containment integrity is not compromised by the addition of a pair of check valves that provide isolation for the reference leg backfill lines. These valves have been demonstrated to meet the criteria specified in General Design Criteria (GDC) 55.

The maintenance and control applied toward all the reference' leg backfill check valves ensures that overall plant safety is maintained.

It can therefore be concluded that the addition of the reference leg backfill valves to Technical Specification Table 3.6.3-1 does not reduce the margin of safety for LaSalle County Station.

The NRC staff has reviewed the licensee *s analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendments requested involve no significant hazards consideration.

The Comission is seeking public coments on this proposed determination. Any coments received within 15 days after the date of publication of this notice will be considered in making any final determination.

Normally, the Comission will not issue the amendments until the expiration of the 15-day notice period. However, should circumstances change during the notice period, such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the j

i Comission may issue the license amendments before' the expiration of the i

15-day notice period, provided that its final determination is that the amendments involve no significant hazards consideration. The final 3

determination will consider all public and State coments received. Should i

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1 the Commission take this action, it will publish in the FEDERAL REGISTER a notice of issuance. The Commission expects that the need to take this action will occur very infrequently, i

Written comments may be submitted by mail to the Rules Review and Directives Branch, Division of Freedom of Information and Publications Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555, and should cite the publication date and page number of this FEDERAL REGISTER notice. Written comments may also be delivered to Room P-223, Phillips Building, 7920 Norfolk Avenue, Bethesda, Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays. Copies of written comments received may be examined at the NRC Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555.

The filing of req tests for hearing and petitions for leave to intervene is discussed below.

By December 9,1993

, the licensee may file a request for a hearing with respect to issuance of the amendments to the subject facility operating licenses and any person whose interest may be affected by this proceeding and wha vishes to participate as a party in the proceeding must file a written request for a hearing and a petition for leave to intervene.

Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.

Interested persons should consult a current copy of 10 CFR 2.714 which is available at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555 and'at the local public document room located at the Public Library I

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l of Illinois Valley Comunity College, Rural Route No.1, Oglesby, Illinois 61348.

If a request for a hearing or petition for leave to intervene is filed by the above date, the Comission or an Atomic Safety and Licensing Board, designated by the Comission or by the Chairman of the Atomic Safety and t

Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.

As required by 10 CFR 2.714, a petition for leave to intervene shall set forth with particular'ity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following

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t factors:

(1) the nature of the petitioner's right under the Act to be made a party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (3) the possible effect of any order which may be entered in the proceeding on the petitioner's interest. The petition should also identify the specific aspect (s) of the subject matter of the proceeding as to which petitit,ner l

wishes to intervene. Any person who has filed a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the Board up to 15 days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.

Not later than-15 days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the i

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i petition to intervene which must include a list of the contentions which are sought to be litigated in the matter. Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted.

In addition, the petitioner shall provide a brief explanation of the bases of the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to rely in proving the contention at the hearing.

The petitioner must also provide references to those specific sources and i

i documents of which the petitioner is aware and on which the petitioner intends to rely to establish those facts or expert opinion.

Petitioner must provide sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact. Contentions shall I

be limited to matters within the scope of the amendments under j

consideration. The contention must be one which, if proven, would entitle i

the petitioner to relief. A petitioner who fails to file such a supplement which satisfies these requirements with respect to at least one contention r

will not be permitted to participate as a party.

Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to particip-i fully in the conduct of the hearing, including the opportunity to present 'vidence and cross-examine witnesses.

If the amendments are issued before the expiration of the 30-day hearing period, the Commission will make a final determination on the issue of no significant hazards consideration.

If a hearing is requested, the final determination will serve to decide when the hearing is held.

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If the final determination is that the amendments requested involve no significant hazards consideration, the Commission may issue the amendments and make them immediately effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendments.

If the final determination is that the amendments requested involve a significant hazards consideration, any hearing held would take place before the issuance of any amendments.

A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Docketing ec, Services Branch, or may be delivered to the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555, by the above date. Where petitions are filed during the last 10 days of the notice period, it is requested that the petitioner promptly so inform the Commission by a toll-free telephon, call to Western Union at 3 '*^0) 248-5100 (in Missouri 1-(800) 342-6700). The Western Union operato should be given Datagram Identification Number N1023 and the following message addressed to J. Dyer: petitioner's name and telephone number, i

date petition was mailed, plant name, and publication date and page number of this FEDERAL REGISTER notice. A copy of the petition should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555, and to Michael I. Miller, Esquire; Sidley and Austin, One First National Plaza, Chicago, Illinois 60693, attorney for the licensee.

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Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a determination by the Commission, the presiding officer or the presiding Atomic Safety and Licensing Board that the petition and/or request should be granted based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).

For further details with respect to this action, see the application for amendments dated October 29, 1993, which is available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washir.gton, DC 20555, and at the local public document room, located at the Public Library of Illinois Valley Community College, Rural Route No. 1, Oglesby, Illinois 61348.

Dated at Rockville, Maryland, this 3rd day of November 1993.

FOR THE NUCLEAR REGULATORY COMMISSION MD v

M. David Lynch, Acting Project Manager Project Directorate III-2 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

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C0lltiONHEALTH EDISON COMPANY,_ LASALLE COUNTY STATION One signed original of the Federaf Register Notice identified below is enclosed for your transmittal to the Office of the Federal

'f Register for publication. Additional conformed cooles (

S ) of the Notice are enclosed for your use.

Notice of Receipt of Application for Construction Permit (s) and Operating License (s).

Notice of Receipt of Partial Application for Construction Permit (s) and Facility License (s): Time for Submission of Views on Antitrust Matters.

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' Notice of Consideration of issuance of Amendment to Facility Operating Licenas.(Call with_-day insert date).

Notice of Receipt of Application for Facility Licensets); Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License (s) and Notice of Opportunity for Hearing-

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-i Notice of Availability of NRC Draf t/ Final Environmental Statement.

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. Notice of Limited Work Authorization.

2 Notica of Availability of Safety Evaluation Report.

Notice of ICsuance of Construction Permit (s).

Notice of issuance of Facility Operating License (s) or Amendment (s).

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.t Exemption.

k Notice of Granting Exemption.

Environmental Assessment.

Notice of Preparation of Environmental Assessment.

Receipt of Petition for Director's Decision Under 10 CFR 2.206.

Issuance of Final Director's Decidon Under 10 CFR 2.206.

f Q otsw NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING

'I LICENSES, PROPOSED NO SIGNIFICANT liAZARDS CONSIDERATION DETERMINATI0R,'AND' OPPORTUNITY FOR A HEARING (Call with 30-day insert date) 1 l~

3ames E. Dyer, Direct $r, PDIII-2 1;i-

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00m0iNEALTH EDISON C0iiPANY _ LASALLE COUNTY STATION' One signed original of the fec'eral Register Notice identified below is enclosed for your transmittal to the' Office of the Federal Register for publication. Additional conformed copies (

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) of the Notice are enc'osed for your use.

Notice of Receipt of Application for Construction Permit (s) and Operating License (s).'

Notice of Receipt of Partial Appiication for Construction Permit (s)and Facility License (s): Time for Submisshn of Views on Antitrust Matters.

Notice of Consideration of Issuance of Amendment to Facility Operating License. (Call with.._. day insert date).

Notice of Receipt of Application for Facility License (s); Notlee of Availability of Applicant's Environmental Report; and Notice of Consideration of issuance of Facliity License (s) and Notice of Opportunity for Hearing.

Notice of Availability of NRC Draft / Final Environmental Statement.

Notice of Limited Work Authorization.

Notice of Availability of Safety Evaluation Report.

Notice of issuance of Construction Permit (s).

Notice of issuance of Facllity Operating License (s) or Amendment (s).

Order.

Exemption.

Notice of Granting Exemption.

Environmental Assessment.

Notice of Preparation of Environmental Assessment.

Receipt of Petition for Director's Decision Under 10 CFR 2.206.

Issuance of Final Director's Decision Under 10 CFR 2.206.

- @ other: NOTICE OF CONSIDERATION OF ISSUMsCE OF AMENOMENTS TO FACILITY OPERATING-LICENSES, PROPOSED NO SIGNIFICANT liAZARDS CONSIDERATION DETERNIHATION, AND OPPORTUNITY FOR A tiEARING (Call with 30-day insert date)

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