ML20116M326
| ML20116M326 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/16/1992 |
| From: | Labarge D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20116M332 | List: |
| References | |
| NUDOCS 9211200188 | |
| Download: ML20116M326 (8) | |
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UNITED STATES NUCLEAR REGULATORY C0K? sSION SE000YAH NUCLEAR PLANT. UNITS 1 AND 2 DOCKET N05. 50-327 AND 50-328 NOTICE OF CONSIDERATION OF ISSVANCE OF AMENDMENT T0 FACILITY OPERATING LICENSE. PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION. AND OPPORTUNITY FOR HEARING The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of amendments to Facility Operating License Nos. DPR-77 and DPR-79, issued to the Tennessee Valley Authority (the licensee), for operation of the Sequoyah Nuclear Plant, Units 1 and 2 located in Soddy-Daisy, Tennessee.
The proposed amendments, submitted by the licensee's letter dated November 9,1992, would modify the technical specifications (TS) Table 3.3-5,
" Engineered Safety Feature Actuation System Instrumentation," Notation No. 2, to provide an alternative method for satisfying the response time requirement -
for the feedwater isolation (FWI) engineered safety feature.
The alternative method would consist of indicating that the response time requirement for a specific feedwater air-operated valve can also be satisfied when the air-operated valve is either closed with the supply (s) isolated, isolated by a closed manual valve, or isolated by a closed feedwater isolation valve with power removed.
When using one of these provisions for satisfying the air-operated valve response time, the closed or isolated condition would be verified at least once per 7 days. This would place the feedwater supply line into the same isolated condition addressed by the response time requirement required by the TS and serves to resolve a conflict resulting from a literal-interpretation of the TS.
9211200188 921116 POR ADOCK 05000327 P
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. The licensee has indicated that the amendment is needed on an emergency basis to prevent unnecessary challenges to plant safety systems resulting from a plant shutdown, or the need for a temocrary waiver of compliance, in the event that maintenance and/or testing of a feedwater valve is necessary.
Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as araended (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 ia 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 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:
1.
Involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed TS change fully maintains the feedwater isolation (FWI) functions assumed in the accident analysis.
In addition, no component functions will be affected by utilizing the alternate methods to ensure completion of the FWI function for accident miti-gation.
Since maintaining the conditions to provide FWI is not postulated to create an accident, there is no increase in the probability of an accident.
By maintaining isolation of the feed-water flow path when the response time for automatic actuation of the air-operated FWI valve is considered inoperable, all safety functions assumed in the accident analysis for FWI are met to mitigate accident conditions.
Therefore, there is no increase in the consequences of an accident because the safety functions for accident mitigation are maintained by the alternate isolation methods that are more conservative than the normal time delayed valve actuation.
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2.
Create the possibility of a new or different kind of accident from any previously analyzed.
The isolation of feedwater ficw is not considered the source of an accident although inadvertent isolation may initiat6 automatic unit shutdown that is an analyzed event.
This change will not alter any plant design or operating parameters su-h that conditions could be created that would create new accident potentials. The isolation methods are the same as or equivalent to the closing of the air-operated valves and will not create any additional safety concern or plant operating impact. Tnerefore, the use of these methods to maintain the FWI function will not create a new or different kind of accident.
3.
Involveasignificantthereductioninamarginofsafety$
This change provides alternate FWI methods are more conservative than the delay 9d isolation assumed in the accident analysis.
By placing the flow path in an isolation condition, the safety function is already achieved without the need for the valve actuation and the associated response time. Therefore, the use of these alternate rWI methods to satisfy TS response time requirements will actually result in an increase in the margin of safety when compared to normal plant operation.
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 fif teen (15) day, after the date of publication of this notice will be considered in making any final d(termination.
The Commission will not normally make a final determination unless it receives a request for a hearing.
Written comments may be submitted by mail to the Rules and Directives Review Branch, Divi: ion of Freedom of Information and Publications Services, Office of Administration, U.S. Nucleat Regulatory Cummission, Washington, DC 20555, and should cite the publication date and page number of this FEDERAL i
1 Rr.GISTER 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 requests for hearing and petitions for leave to intervene is discussed below.
By November 20, 1992, the licensee may file a request for a hearing with respect to issuanco of the amendment to the subjen 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 intervena. Requests for a hearing and a petition for luve to intervene shall be filed in accordance with the Commission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.
Inter 6sted 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 Chattanooga-Hamilton County Library, 1101 Broad Street, Chattanooga, Tennessee 37402.
If a re. quest for a hearing cr petition for leave to inteivene 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' Atcmic Safaty 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 1
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. 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 a party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (3) tF possible effect of any order which may be entered in the proceeding on the tioner'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 wito 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 fifteen (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 fifteen (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 pei.itioner 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 en which the petitioner intends to rely to establish those facts or expert opinion.
Petitioner must provide sufficient information to show that a
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.. - genuir.e' dispute exists.with the applicant on a material issue of law or fact._
Contentions shall be-limited to matters within the scope of-thel amendment under consideration.- The contention must be one which,.if prove'n', would entitle the petitlener 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 1%itations in the order granting leave to intervene, and have the-opportunity to participate fully in the conduct of the hearing, including the e
opportunity-to present evidence and cross-examine witnesses.
If the amendment is issued before the expiration of 30-days, 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 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.
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If the final determination is that the amendment request involves a significant hazards consideration, any hearing held would take place oefore the issuance of any amendment.
Normally, the Commission will not issue the amendment untti 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 woulti E
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 l
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period, provided that its final: determination is that the amendment involves no significant hazards consideration. The; final-- determination will consider i all..public and State coments received.
Should the Commission ;ake 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.
A request for a hearing or a petition for leave to intervene must bo 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, N.W., Washington, DC 20555, by the above date.-
Where petitions ara filed during the-last ten (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)_325-6000 (in'
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Hissouri 1-(800) 342-6700). The Western Union operator should be given Datagram Identification Number N1023 and the following message addressed to Mr. Frederick J. Hebdon: -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 General Council, Tennessee Valley Authority, ET 11H, 400 West Summit Hill' Drive, Knoxville, Tennessee 37902,-attorney for the-
- licensee. Nontimely filings:of petitions for leave to intervene, amendedL j
petitions, supplemental petitions and/or requests for hearingLwill not _be.
em rtained absent' a: determination by the Commission,- the presiding. officer or-
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the presiding Atomic Safety and Licensing Board that the petition and/ ors L
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, 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 November 9, 1992, whi:h is available for public inspection 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 C!>.ttanooga-Hamilton County Library, 1101 Broad Street, Chattanooga, nassee 3740?.
Dated at Rockville, Maryland, this -16th day of November 1992.
FOR THE NUCLEAR REGULATORY COMMISSION f
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David E. LaBarge, Senior Project Manager Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l
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