ML20209G460
| ML20209G460 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/08/1999 |
| From: | Donohew J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20209G465 | List: |
| References | |
| NUDOCS 9907190168 | |
| Download: ML20209G460 (7) | |
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7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION WOLF CREEK NUCLEAR OPERATING CORPORATION DOCKET NO. 50-482 NOTICE OF CONSIDERATION OF ISSM6MGE.OEAMEN(2MQU_I_Q FACILITY OPERATING LICENSE. PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION. AND OPPORTUNITY FOR A HEARING c
The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. NPF-42 issued to Wolf Creek Nuclear l
Operating Corporation (the licensee) for operation of the Wolf Creek Generating Station i
(WCGS) located in Coffey County, Kansas.
The proposed amendment request dated June 30,1999, would revise Technical Specs 6cahon (TS) 3/4.7.5 of the current TSs by adding a temporary action statement that would allow the piant to operate for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with an inlet temperature up to but less than 95 degrees F. The current TS limit is 90 degrees F. This new action statement would be temporary in that it would be effective until September 30,1999, after the summer. This action statement was added to the current TSs in Amendment 118 dated July 18,1998, tst it was only eNedive until September 30,1998. Amendment 118 was issued becsuae in 1998 the WCGS
, cooling imho that provides inlet water to the plant M 89 degrees F and,Jduo' ton -
i predstions for continuing harsh it::::+:4-$=! conditions throughout the summer of 1998, the concem easted that the plant inlet temperature would exceed 90 degree: F ano the plant would be forced to have an unnecessary shutdown. lhe 16consee submitted a permanent change to TS 3/4.7.5 on January 12,1999; however, the Commission considers th'a proposed change to be generic in nature and should be revwwod as a change to NUREG-1431, Standard 9907190168 990708 P DP.
ADOCK 05000482 P
Is 2-Technical Specifications, Westinghouse Plants." NUREG-1431 is the standard for the improved Technical Specifications that were issued for WCGS in Amendment 123 dated March 31,1999. To allow the Commission sufficient time to review the generic change to NUREG-1431, the licensee was requested to resubmit the temporary change approved in Amendment 118 with the temporary change being effective until September 30,1999, for the warm weather of this summer. This is the change submitted by the licensee on June 30,1999.
The proposed change is only to the current TSs because the improved TSs issued in Amendment 123 will become effective after September 30,1999, when this temporary change is no longer valid.
Before issuance of the proposed license amendment, the Commission will have made findogs required by the Atomic Energy Act of 1954, as amended (the Act) and the i
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 accorda' ice 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 any accident previously evaluated; or (3) involve a significent reduction in a margin of safety. As requesd by 10 CPR 50.91(a), the liconose has provided its analysis of the leeue of no >
eignlRcont hazards consideration, which is presented below:
1.
The pmpoemd change does not involve a signiRoont incrosse in the probability or consequences of an accident previously evaluated.
The proposed change does not involve any physical alteration of plant systems, j
structures or components. The proposed change provides an allowed time j
[12 hours] for the plant to continus operation with plant inlet water temperature in esceos of the cunent technical spoolRostion limit of 907, but less then the design limit of 95*F for plant components. The plant inlet water temperature is not assumed to be an initiating condthon of any accedent analysis evaluated in the i
.. updated safety analysis report (USAR). Therefore, the allowance of a limited time l
for the water temperature to be in excess of the current limit does not invo!ve an increase in the probability of an accident previously evaluated in the USAR. The UHS [ ultimate heat sink] supports operability of safety related systems used to
. mitigate the consequences of an accident. Plant operation for brief periods with plant inlet water temperature greater than 90*F but less than 95*F will not adversely affect the operability of these safety-related systems and will not adversely impact the ability of these systems to perform their safety-related functions. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated in the USAR.
2.
The proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
The proposed change does not involve any physical alteration of plant systems, structures or components. The temperature of the plant inlet water being greater than 90*F but less than 95'F for a short period [12 hours] does not introduce new i
failure mechanisms for systems, structures or components not already considered 1
in the USAR. Therefore, the possibility of a new or different kind of accident from any accident previously evaluated is not created.
1 3.
The proposed change does not involve a significant reduction in the margin of safety.
The proposed change will allow an increase in plant inlet water temperature above the current technical specdication limit of 90*F for the Ultimate Heat Sink, and delay the requirement to shutdown the plant when the plant inlet water system temperature limit is exceeded for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The proposed change does not alter any safety limits, limiting safety system settings, or limiting conditions for operation
[except for TS 3/4.7.5], and the proposed temperature increase will remain below the design limit cooling water input value for safety-related equipment. Thus, the proposed change does not involve a significant reduction in any margin of safety.
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 amendment request involves no significant hazards consideration.
The Commission is seeldng public comments on this proposed determination Any comments roosived within 30 days after the date of publication of this notice will be considered in making any final determination h
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. Normally, the Commission will not issue the amendment until the expiration of the 30-j day notice periM 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 Commission may issue the license amendment before the expiration of the 30-day notice period, provided that its final determination is that the amenoment involves no significant hazards consideration. The final determination wi!! 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 hear.ng after issuance. The Commission expects that the need to tcke this action will occur very infrequently.
Written comments may be submitted by mail to the Chief, Rules and Directives Branch, Division of Administrative Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20255-0001, and should cite the publication date and page number of this FEDERAL REGISTER notice. Written comments may also bs Jelivered to Room 6D59. Two White Flint North,11545 Rockville Pike, Rockviile, 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.
The filing of requests for hearing and petitions for leave to intervene is discussed below.
By August 16,1999, 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 pr icipate 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 CFP. 2.714 which is available at the Commission's Public Document Room, the Gelmcn Buildag,2120 L Street, NW., Washington, DC, and at the local
v public document room located at the Emporia State University, William Allen White Library, i
1200 Commercial Street, Emporia, Kansas 66801 and Washbum University School of Law Library, Topeka, Kansas 66621. 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 Safety and Licensing Board Panel, will R
rule on the request and/or petition; and the Secretary or the designated Atomic Safety and i
1 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 J
particularity the interest of the petitioner in the proceeding, and how that interest may be i
- 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 j
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 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 prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements doncribed above.
Not later than 15 days prior to the first prehearing conference scheduled in the proceeding, a petihonor shall file a supplement to the petition to intervene which must include a list of the contentions whit 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 addihon, 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
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6-i 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 estab!ish 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 be limited to 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 a'1y limitations in the order granting leave to intervene, and have the opportunity to participate fuliy 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 detemiination will serve to decide when the hearing is held?
If the final determination is that the amendment request involves no signifcant hazards consideration, the Commission may issue the amendment and make it immediately effective, id:N--dr,v the request for a heanng. Any hearing held would take place after issuance of the amendment.
If the final determination is that the amendment equest involves a significant hazards considerabon, any hearing 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
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7 Commission's Public Document Room, the Gelman Building,2120 L Street, NW., Washington, DC, by the above date. A copy of the petition should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and to Jay Silberg, Esq., Shaw, Pittman, Potts and Trowbridge, 2300 N Street, N.W., Washington, D.C.
20037, attomey for the licensee.
Nontimely filings of petitions for leave to intervene, amended petitions, supplemental i
petitions and/or requests for hearing will not be entertained absent a determination by the Commission, the presiding officer er 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 30,1999, 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 j
document room located at the Emporia State University, William Allen White Library, 1200 Commercial Street, Emporia, Kansas 66801 and Washbum Univemity School of Law s
Library, Topeka, Kansas 66621.
1 Dated at Rockville, Maryland, this 8th day of July 1999.
FOR THE NUCLEAR REGULATORY COMMISSION 3
DD-Jack N. Donohew, Project Manager, Section 2 Project Diredorate IV & Decomtrdesioning Dwision of Licensing Proket Management Office of Nuclear Reactor Regulation I
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