ML20096D780
| ML20096D780 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/11/1996 |
| From: | Polich T NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20096D782 | List: |
| References | |
| NUDOCS 9601190268 | |
| Download: ML20096D780 (8) | |
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7590-01 UNITED STATES NUCLEAR REGULATORY COMISSION C0MANCHE PEAK STEAM ELECTRIC STATION. UNITS I AND 2 DOCKET N05. 50-445 AND 50-446 NOTICE OF CONSIDERATION 0F ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE. PROPOSED N0 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 Nos. NPF-87 and NPF-89,- issued to Texas Utilities Electric Company (TU Electric, the licens'ee), for operation of the Comanche Peak Steam Electric Station, Units 1 and 2 located in Somervell County, Texas.
The proposed exigent amendment Technical Specification (TS) would temporarily change the TS to revise the requirements for Minimum Channels OPERABLE for Wide Range RCS (Reactor Coolant System) Temp. (Temperature)-Tn remote shutdown indication for CPSES Unit 2.
The minimum number of channels required is being revised from 1 per RCS Loop for each RCS Loop to I per RCS Loop for 3 of the 4 RCS Loops. This temporary change is requested as a result of the failure of one of the T, channels in a manner which cannot be repaired without a unit shutdown and a possible cooldown. NRC granted enforcement discretion on January 5,1996, to allow the facility to c'ontinue operation while this exigent TS is processed.
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.
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) Pursuant to 10 CFR 50.91(a)(6) for amendments to be granted under l
exigent circumstances, the NRC staff must determine that the amendment request involves no significant hazards consideration. Under the
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l Commission's regulations in 10 CFR 50.92, this means that operation of the f
facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident t
i previously evaluated; or (2) create the possibility of a new or different l
kind of accident from any accident previously evaluated; or (3) involve a i'
significant reduction in a margin.of safety. As required by 10 CFR 50.gl(a), the licensee has provided its analysis of the issue'of no signifitant hazards consideration, which is presented below:
1.
Do the proposed changes involve a significant increase in the probability or consequences of an accident previously evaluated?
The unavailability of one RCS Loop T indication at the HSP cannot be an 3
initiating event for nor affect the progression or mitigation of any licensing basis accident; therefore the probability of occurrence of any.
licensing accident cannot be affected.
The request proposes to change the minimum channels operable for Wide Range Hot Leg RCS Temperature T indication at the HSP. Sufficient 3
alternate instrumentation is available on the HSP to provide the Specifications acknowledge the need to and a1I. The current Technicalow fo information normally directly obtained from T T inoperable for the Allowed Outage Time ~(A0T) in the action statement.
The current Technical Specifications have an A0T of seven days.
Further, the improved Standard Technical Specifications allows an A0T of 30 days. The duration of this request is not significantly different than these time periods. Thus the consequences of a remote shutdown with the affected instrument inoperable have already been considered and this change will not increase the consequences of an accident previously evaluated.
2.
Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated?
Operation for a period of time with the one RCS Loop T unavailable will 3
not create the possibility of a new or'different kind of accident from any accident previously evaluated. No hardware modifications are being 4
,' made and no plant procedures are being revised that would alter normal plant operations.
3.
Do the proposed changes involve a significant reduction in a margin of j
safety?
The Wide Range Hot Leg RCS Temperature indication at the HSP is only required in the event that a remote shutdown from outside the control room is needed. The availability of other remote shutdown indications (including T Tn in other RCS Loops, and Steam Generator pressure) in combination w,,ith licensed operators who have been briefed on how to compensate for an inoperable T for one RCS Loop using these other indications, assures that the Increased unavailability of the instrument will not have a significant effect in the margin of safety.
The Reactor Building Emergency Cooling system is not an initiator of any-accident described in the ANO-1. Safety Analysis Report. The engineering evaluation discussed above verifies that the green train of the Reactor Building Emergency Cooling system remains operable and capable of performing its design function under all postulated accident conditions.
,Therefore, the probability or consequences of any previously evaluated
' accident is not increased.
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 seeking public comments on this proposed determination. Any comments received within 15 days after the date of publication of this notice will be considered in making any final determination.
Normally, the Commission will not issue the amendment 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 Commission may issue the license amendment before the expiration of the 15 day notice period, provided that its final determination is that the amendment involves no significant hazards consideration. The final
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1 i determination will consider all public and State comments received. Should the comeission take this action, it will publish in the FEDERAL REGISTER a motice of issuance. The Commission expects that the need to take this t
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action will occur very infrequently.
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Written comments may be submitted by mail to the Rules Review and Directives Branch, Division of Freedom of Information and Publications Services, Dffice of, Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555, and should cite the publication date and page r; umber of this FEDERAL REGISTER notice. Written comments may also be delivered to Room 6022. Two White Flint North,11545 Rockville Pike, Rockville, Naryland, 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, l
2120 L Street, NW., Washington, DC.
The filing of requests for hearing and petitions for leave to intervene is discussed below.
By February 20,1996
, 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 proceeding must flie 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.
Inteinted 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 O
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e University of Texas at Arlington Library, Government publications / Maps, 702 College, P.O. Box 19497, Arlington, Texas 76019.
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 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 j
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 i
. 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 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 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 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
l petition to intervene which must include a list of the contentions which arv sought to be litigated in the matter. Each contention must consist of a specific statement of the issue kf law or fact to be raised or i
l controverted. In addition, the ' petitioner shall provide a brief explanation of the bases of the coritention and a concise statement of the l
alleged facts or expert opinion'which support the contention and on which f
thepetitionerintendstorelyinprovingthecontentionatthehearing.
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The petitioner must also provide references to those specific sources and i
documents of which the petitioner is aware and on which the petitioner 1
l intends to rely to establish those facts or expert opinion.
Petitioner i
must proylde sufficient information to show that a genuine dispute exists i
with the applicant on a material issue of law or fact. Contentions shall i
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 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 the amendment is 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.
If the final determination is that the amendment request involves no
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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 after issuance of the amendment.
If the final determination is that the amendment request involves a significant hazards consideration, 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, Attention: Docketing and Services Branch,,or may be delivered to the Commission'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 Commission by a toll-free telephone call to Western Union at 1-(800) 248-5100 (in Nissouri 1-(800) 342-6700). The Western Union operator should be given Datagram Identification Number N1023 and the following message addressed to [ APPROPRIATE PD): 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 Commission, Washington, DC 20555, and to Nicholas S. Reynolds, Esquire, Winston and Strawn, 1400 L. Street, N.W., Washington, D.C. 20005-3502, attorney for the licensee.
Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be L
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f entertained absent a determination by the Commission, the presiding officer 4
l 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 j
in 10 CFR 2.714(a)(1)(1)-(v) and 2.714(d).
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For further details with respect' to this action, see the application for t
amendment dated January 5,1996, which is a'vailable for public inspection at i
j the Commission's Public Document Room, the Gelman Building, 2120 L Street, l
W., Washington, DC, and at the local public document room, located at the j
i University of Texas at Arlington Library, Government Publications / Maps, i
j 702 College, P.O. Box 19497, Arlington, Texas 76019.
Dated at Rockville, Maryland, this lith day of January 1996.
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FOR THE NUCLEAR REGULATORY COPfilSSION l
Timothy J. P lich, Project Manager
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Project Directorate IV-1 l
Division of Reactor Projects III/IV
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Office of Nuclear Reactor Regulation I
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