ML20236K378

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Notice of Consideration of Issuance of Amend to License DPR-20 Proposed NSHC Determination & Opportunity for Hearing.Proposed Amend Would Revise Section 3.1.1c of TSs to Change Min Required Primary Coolant Sys Flow
ML20236K378
Person / Time
Site: Palisades 
Issue date: 06/26/1998
From: Robert Schaaf
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20236K382 List:
References
NUDOCS 9807090292
Download: ML20236K378 (7)


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7590-01-P UNITED STATE.?j_NVCl FAR REGULATORY COMMISSION CONSUMERS ENERGY COMPANY DOCKET NO. 50-255 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE NO. DPR-20 PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION. AND OPPORTUNITY FOR A HEARING The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. DPR-20 issued to Consumers Energy Company (the licensee) for operation of the Palisades Nuclear Plant, located in Van Buren County, Michigan.

The proposed amendment would revise Section 3.1.1c of the Technical Specifications (TS), Appendix A of the Operating License for the Palisades Nuclear Plant, to change the minimum required primary coolant system flow. The currently specified value is 140.7x10* lb/hr

[ pounds per hour] or greater, when corrected to 532 'F. The licensee proposed to revise the TS to specify a value of greater than or equal to 352,000 gpm [ gallons per minute), which is equivalent to approximately 135x10' lb/hr, when corrected to 532 'F.

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

The Commission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordarice with the proposed amendment 9807090292 980626 PDR ADOCK 05000255 P

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  • 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 uf accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.g1(a), the licensee has provided its analysis of the issue of no 1

- significant hazards conslosration, which is presented below-l

a. Involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed change to the minimur. reactor vessel flow does not alter the assumed i

in41stors to any analyzed event. Rather, specification of a minimum reactor vessel flow j

prov! des assurance that sufficient cooling will take place 6. fring normal and accident i

operating conditions of the reactor. Therefore the probabbity of an accident previously l

l evaluated has not been increased by this proposed change.

Each of the applicable Palisades FSAR [ Final Safety Analysis Report] Chapter 14 accident analyses have been evaluated with respect to the proposed reduction in l

minimum reactor vessel flow rate. The results of these analyses, which have twmn incorporated h'.to the Palisades Cycle 14 Disposition and Analysis of Standard Review Plan (SRP) Events, demonstrate that the acceptance criteria for each of the evt.s

' continues to be met.

Therefore, operation of the facil4y in accordance with the proposed change to TS section 3.1.1c would not involve a significant !ncrease in the probability or consequences of an accident previously evaluated.

b. Create the possibility of a new or different kind of accident from any previously evaluated.

The proposed changes provide a reduced requirement for PCS [ primary coolant systern) flow through the reactor vessel than cunantly exists in the TS. The enange doas not, however, involve any alteration in the plant configuration (no new or different type of equipment will be installed) or make changes in the methods Goveming normal plant operation However, these changes are consistent with the assumptions in the safety analyses and licensing basis. Therefore, the changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

4 Therefore, operation of the facility in accordance with the proposed change to TS section 3.1.1c would not create the possibility of a new or different kind of accident from any previously evaluated.

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6 c. Involve a significant reduction in a margin of safety.

l The proposed change to the minimum reactor vessel flow has besn evaluated against each of the applicable Palisades FSAR Chapter 14 accident analyses. Reducing the assumed minimum reactor vessel flow did not result in a significant change (per 10 CFR 50.46)in the results of the Loss Of Coolant Accident (LOCA) Emergency Core Cooling l

System (ECCS) analyses. Reducing the assumed minimum rasetor vessel flow did not l

result in penetration of TS DNB [ departure from nucleate boiling] limits or additional fuel

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l failures for non-LOCA events. Reducing the assumed minimum reactor vessel flow did I

not result in a change in the results of the LOCA or Main Steam Line Break containment l

response analyses, Reducing the assumed minimum reactor vessel flow did not result I

in a change to the radiological consequences of the SRP events with respect to 10 CFR 100 offsite doso or SRP 6.4 control room habi,tability requirements. Therefore, operation of the facility in accordance with the proposed change to TS 3.1.1c does not involve a significant reduction in the margin of safety.

The NRC staff has reviewed the licensee's analysis and, based on this rev'ew, it 1

appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff I

propocas to determine that the amendment request involves no significant hazards i

i consideration.

l The Commission is seeking public comments on this proposed determination. Any,

comments received by close of business within 30 days, after the date of publication of this notice will be considered in making any final determination.

Normally, the Commission wi!! not issue the amendment until the expiration of the 30-day notice period. However, should circumstances change during the notice period such that failure to act in a timely way would result, for exan' ple, in derating or shutdown of the facility, 1

the Commission may issue the license amendment before the expiration of the 30-day notice period, provided that its final determination is that the amendment involves 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.

1 Written comments may be submitted by mail to the Chief, Rules and Directives Branch, Division of Administrative Services, Dffice of Administration, U.S. Nuclear Regulatory l

Commission, Washington, DC 20555-0001, and should cite the publication date and page i

number of this FEDERAL REGISTER notice. Written comments may a!co be delivered to Room 6D59, Two White Flint North,11545 Rockville Pike, Rockville, Maryland, from 7:30 i

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.

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

By August 3, 1998, the licensee may file a request for a hearing with respect to issuance of the amendment 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 proceedir,g 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 oe 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 i

Commission's Public Document Room, the Gelman Building,2120 L Street, NW.,

Washington, DC, and at the local public document room located at the Van Wylen L.orary, Hope College, Holland, Michigan 49423-3698. If a request for a hearing or petition for leave to i

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 Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the designated Atomic 1

Safety and Licensing Board willissue 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

5-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 l

nature of the petitioners 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 I

possible effect of any order which may be entered in the proceeding on the petitioners 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 l

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 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 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 mat: rial issue of law or fact. Contentions shall be limited to matters within the j

scope of the amendment undu consideration. The contention must be one which, if proven, j

would entitle the petitioner to relief. A petitioner who fails to file such a supplement which 1

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sat!sfies these requirements with respect to at leest one contention will not be parmitted 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.

If a hearing is requested, the Commission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to dacide when the hearing is held.

If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing held would take place afterissuance of the amendment.

If the final determination is that the amendment request involves a significant hazards considerat%n, any hearir,J held would take place before the issuance of any amendment.

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 20555-0001, Attention: Rulemakings and Adjudications Staff, or may be delivered to the Commission's Public Document Room, the Gelman Building,2120 L Street, NW., Washington, DC, by close of business on the above date. A copy of the petition should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Commir.bn, Washington, DC 20555-0001, and to Judd L. Bacon, Esquire, Consumers Energy Company,212 West Michigan Avenue, Jackson, Michigan 49201, attomey for the licensee.

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7 Nontimely filings of petitions for leave to intervene, amended petitions, supplemental Atitions 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 amendment dated June 17,1998, and supplement dated June 23,1998, which are 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 Van Wylen Library, Hope College, Holland, Michigan 49423-3698.

Dated at Rockville. Maryland, this 26th day of June 1998.

FOR THE NUCLEAR REGULATORY COMMISSION 7'

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Robert G. Schaaf, Project Manager Project Directorate lil-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation 1

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