ML20137V796
| ML20137V796 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/14/1997 |
| From: | Pulsifer R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20137V800 | List: |
| References | |
| NUDOCS 9704170409 | |
| Download: ML20137V796 (8) | |
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7590-01-P i
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UNITED STATES NUCLEAR REGULATORY COMMISSION COMMONWEALTH EDISON COMPANY i
DOCKET NOS. 50-237 AND 50-249 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES. PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION. AND OPPORTUNITY FOR A HEARING i
The U.S. Nuclear Regulatory Comission (the Comission) is considering i
issuance of amendments to Facility Operating License Nos. DPR-19 and DPR-25, issued to Comonwealth Edison Company (Comed, the licensee) for operation of i
t the Dresden Nuclear Power Station, Units 2 and 3, located in Grundy County,
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1 The proposed amendments would change the Technical Specifications (TS) to reflect the installation of new reactor water level instrumentation for the Emergency Core Cooling System (ECCS) actuation.
Before issuance of the proposed license amendments, the Comission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Ccmission's regulations.
j The Comission has made a proposed determination that the amendments j
requested involve no significant hazards consideration.
Under the Comission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment 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 kind of accident from ar>y accident previously evaluated; or (3) involve a signi.'icant reduction in a margin of safety. As requir.
by 10 CFR 50.91(a),
9704170409 970415 DR ADOCK 0500 7
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the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
i (1)
Involve a significant increas'e in the probability or consequences of an accident previously evaluated because of the following:
The proposed change to note (f) to Table 4.2.B-1, which modifies the
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surveillance frequency for the Reactor Vessel Water level Low Low inputs to the CS, LPCI, HPCI, and ADS systems (items 1.a. 2.a. 3.a. and 4.a) i-and the Reactor Vessel Water level High trip input to the HPCI system (item 3.c), will not increase the probability of or the consequences of 4
any accident previously evaluated in the SAR. Similarly, the proposed editorial change to achieve consistency in notation between tables 4.2.B-1 and 4.2.C-1 will not increase the probability or consequences of any accident previously evaluated in the SAR.
The surveillance requirements proposed for the Unit 3 Reactor Vessel Water level transmitters are the same 18 month channel calibration requirements required by Table 4.2.C-1 "ATWS-RPT Instrument Surveillance Requirements." The surveillance schedule proposed for the new Unit 3 Reactor Vessel Water level analog trip units has the same quarterly requirement a's the replaced Yarway level switches.
The proposed change will impose a calibration schedule on the post modification trip units only, the trip setpoints of Table 3.2.B-1 "ECCS Actuation Instrumentation" will not change.
The proposed change affects the scheduling of the surveillance only and will not have any effect on the operating trip points of the instrumentation. The proposed change cannot initiate any of the accidents previously evaluated in the SAP..
Based on this the proposed change to note (f) will not increase the probability of any accident nor the consequences of any accident previously evaluated in the SAR.
The change to the table to achieve consistency with Table 4.2.0-1 is an editorial change only. This editorial change will not increase the probability of an accident previously evaluated, nor will it increase the consequences of any accident previously evaluated.
(2)
Create the posribility of a new or different kind of accident from any accident previously evaluated because:
The proposed change to note (f) provides a schedule for performing channel calibrations on the Reactor Vessel Water Level inputs to the ECCS System. The proposed change does not introduce any new failure mechanisms or modes. The proposed change will not create the possibility of a new or different type of accident previously evaluated.
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The change to the table is an editorial change only and will not create the possibility of a new or different type of accident previously evaluated.
(3)
Involve a significant reduction in the margin of safety because:
1 The proposed amendment only specifies a schedule for performing channel calibrations for the Peactor Vessel Water level instrumentation.
The l
change will not impact the availability or trip setpoints of the ECCS system.
Further the editorial change to achieve consistency between tables will not impact the availability or operating setpoints of the instruments. Therefore, the proposed changes do not involve a l
significant reduction in the margin of safety, t
Guidance has been provided in " Final Procedures and Standards on Wo Significant Hazards Considerations," Final Rule, 51 FR 7744, for the i
application of standards to license change requests for determination of the existence of significant hazards considerations. This document l
provides examples of amendments which are and are not considered likely to involve significant hazards considerations.
This proposed amendment does not involve any irreversible changes, a significant relaxation of the criteria used to establish safety limits, a significant relaxation of the bases for the limiting safety system settings or a significant 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),
i the proposed change does not constitute a significant hazards' consideration.
l 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 Commission is seeking public comments on this proposed r
j determination. Any comments received within 30 days after the date of publication of this notice will be considered in making any final 1
determination.
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Normally, the Commission will not issue the amendments until the 1
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expiration of the 30-day notice period. However, should circumstances change e
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i during the notice period such that failure to act in a ti:aely way would i
result, for example, in derating or shutdown of the facility, the Commission may issue the license amendments before the expiration of the 30-day notice period, provided that its final determination is that the amendments involve no significant hazards consideration. The final determination will consider all public and State comments received. Should the Commission take this action, it will publish in the FEDERAL REGISTER a notice of issuance and provide for opportunity for a hearing after issuance. The Commission expects that the need to take this action will occur very infrequently.
.f Written comments may be submitted by mail to the Chief, Rules Review and Directives Branch, Division of Freedom of Information and Publications Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and should cite the publication date and page number of this FEDERAL REGISTER notice. Written comments may also be delivered to Room 6D22, Two White Flint North, 11545 Rockville Pike, Rockville, 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 Ge? man Building, 2120 L Street, NW., Washington, DC.
The filing of requests for hearing and petitions for leave to intervene is discussed below.
By May 19,1997
, the licensee may file a request for a hearing with respect to issuance of the amendments to the subject facility operating license and any person whose interest may be affected by this proceeding and who wishes 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
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- 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, and at the local public document room located at the Morris Area Public Library District, 604 Liberty Street,
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Morris, Illinois 60450.
If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or an Atomic Safety and Licensing Board, designated by the Commission or by the Chairman of the Atomic 1
Safety and 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 particularity 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 factors:
(1) the nature of the petitioner's right under the Act to be made 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
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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 petitioner 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
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. prior to the first prehearing conference scheduied in the proceeding, but such an amended petition must satisfy the specificity requirements described above.
1 Not later than 15 days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the l
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 petitioiier must also provide references to those specific sources and 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 app 1tcant on a material issue of law or fact.
Contentions shall be limited la matters within the scope of the amendment under consideration. The contention must be one which, if proven, would entitle the petitioner to relief. A petitioner who fails to file such a supplement which satisfies these requirements with respect to at least one contention 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 participate fully in the conduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.
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If a hearing is requested, the Commission will make a finsi i
determination on the issue of no significant hazards consideration. The final 1
determination will serve to decide when the hearing is held.
I If the final determination is that the amendments requested involve no I
4 significant hazards consideration, the Comission may issue the amendments and make them immediately effective, notwithstanding the request for a hearing.
i Any hearing held would take place after issuance of the amendments, l
If the final determination is that the amendments requested involve a l
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significant hazards consideration, any hearing held would take place before the issuance of any amendments.
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A request for a hearing or a petition for leave to intervene must be 1
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filed with the Secretary of the Comission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Docketing and Services Branch, or may be delivered to the Comission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC, 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 Comission by a toll-free telephone call to Western Union at 1-(800) 248-5100 (in Missouri 1-(800) 342-6700). The Western Union operator should be given Datagram Identification Number N1023 and the following message addressed to Robart A. Capra:
petitioner's name and telephone number, 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 Comission, Washington, DC 20555-0001, and to Michael I.
- Miller, Esquire; Sidley and Austin, One First National Plaza, Chicago, Illinois 60603, attorney for the licensee.
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 th'at the petition and/or request should be granted based upon a balancing of the factors specified in i
10 CFR 2.714(a)(1)(1)-(v) and 2.714(d).
i For further details with respect to this action, see the application for amendments dated January 24, 1997, which is available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC, and at the local public document room located at the Morris Area Public Library District, 604 Liberty Street, Morris, Illinois 60450.
Dated at Rockville, Maryland, this 14th day of April 1997.
FOR THE NUCLEAR REGULATORY COMMISSION Robert M. Pulsifer, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation r
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