ML19354D956
| ML19354D956 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 10/19/1989 |
| From: | Nerses V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19354D747 | List: |
| References | |
| FOIA-89-525 NUDOCS 9001250070 | |
| Download: ML19354D956 (8) | |
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7590 01 UNITED STATES NUCLEAR REGULATORY C0>t41SS10N PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE SEAB900K STATION DOCKET NO. 50 443 NOTICE OF CONSIDERATION OF ISSUANCE OF AMEN 0 MENT TO FACILITY OPERATING LICENSE AND PROPOSED NO $1GNIFICANT WA7ARDS CONSIDERATION DETERMINATION AND OPPORTUNITY TOR HEARING The U.S. Nuclear Regulatory Commission (the Comission) is considering issuance of an amendment to Facility Operating License No. NPF 67 issued to New Hampshire Yankee (the licensee) for operation of Seabrook Station located in Seabrook, Rockingham County, New Hampshire The proposed amendment would preclude the potential of a forced plant shutdown as a result of loss of the Containment Building Compressed Air System. New Hampshire Yankee (NHY) proposes that a back-up air supply be connected to the Containment Building Compressed Air Systte. The back-up air supply would be a cross-connection between the Plant Instrument Air System and the Containment Air System. The cross-connect would enter the containment
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building thru an existing containment penetration, X-68.
The penetration E
will be added to Technical Specification Table 3.6 1 " Secondary Containment
, Bypass Leakage Paths'.
The proposed change would be implemented in two phases. The first phase is scheduled for completion prior to commercial operation and would include the installation of the cross-connect piping from the Plant Instrument Air System to the Containment Compressed Air System. The piping isolation design will meet 10 CFR 50, Appendix A. General Design Criteria 56, " Primary Containment Isolation" by utilizing a fail-closed air operated valve outside Containment and a check valve inside Containment.
The air operated valve's 9001250070,900117 Ni!n b 525 PDR
automatic open/close function will be disarmed and the valve will be administrative 1y controlled in the locked closed position for Modes 1-4.
The second phase of this change will provide the instrumentation and electrical changes required to make the cross connect operate automatically with Containment Air System low pressure and assure post-accident isolation. This phase is scheduled to be implemented prior to completNn of the first refueling outape.
Before issuance of the proposed license amendment, the Comission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations.
The Comission has made a proposed detennination that the request for amendment involves no significant hazards consideration.
Under the Commission'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 l
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.
"New Hampshire Yankee has reviewed the proposed change utilizing the criteria specified in 10 CFR $0.92 and has determined that the proposed change would not 1.
Involve a significant increase in the probability of consequences of any accident previously evaluated.
The activation of a previously spare piping penetration to the Containment will allow utilization of the Plant Instrument Air System to backup the Containment Building Compressed Air System during Modes 5 and 6.
The Containment Building Compressed Air System is non-safety related and is not relied upon for safe shutdown.
The new penetration piping is designed to Quali+y Group
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8 standards and is subject to testing per 10 CFR 50, Appendix J.
The activation of this penetration will not effect the existing offsite dosage analysis since the analysis already assumes the maximum possible bypass leakage.
The total containment integrated leakage, as well as loc 41 leakage rates, will remain within 10 CFR 50 Appendix J, limits.
This cross-connect will not be used during Modes 1-4, therefore, incoming instrument air will not affect containment peak pressure.
2.
Create the possibility of a new or different kind of accident from any previously evaluated.
The additional. Type C" penetrations maximum leakage in conjunction with the combined leakage of the existing Type "B" and "C" penetrations will not exceed the total leakage allowed by 20 CFR 50 Appendix 0 for bounding radiation doses j
to within the dose guidelines o' 10 CFR part 100 during accident 4
conditions, j
3.
Involve a significant reduction in a margin of safety. The bases for the Technical Specifications indicate that allowable leakages will be consistent with assumptions made in the offsite dose analyses."
i Therefore, based on the above facts, the Commission has made a proposed determination that the Amendmen' request involves no significant hazards consideration.
The Consnission is seeking public consnents on this proposed determination.
l Any cocrnents received within 30 days after the date of publication of this notice will be considered in making any final determination. The Comission l
will not nonna11y make a final detennination unless it receives a request for a hearing.
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Written coments may be submitted by mail to the Regulatory Publications Branch, Division of Freedom of Information and Publications Services. Office of Administration, U.S. Nuclear Regulatory Comission Washington, D.C.
- 20555, and should cite the publication date and page number of this FEDERAL REGISTER notice. Written coments may also be delivered to Room P-223, Phillips Building, l
7920 Norfolk Avenue, B:!thesda, Maryland, from 7:30 a.m. to 4:15 p.m.
Copies of written comments received may be examined at the NRC Public Document Room, the L
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4-Gelman Building, 2120 L Street, N.W., Washington, D.C.
The filing of requests for hearing and petitions for leave to intervene is discussed below.
By November 27, 1989
. the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating ifcense 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 petition for leave to intervene.
Request for a hearing and petitions for leave to intervene shall be filed in accordance with the Comission's " Pules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.
Interested persons should corsult a current copy of 10 CFR 2.714 which is available at the Comission's Public Document Room, the Gelman Building, 2120 L Street, N.W., Washington, D.C. 20555 and at the Local Public Document Room located at the Exeter Public Library, Founders Park Exeter, New Hampshire 03833.
If a reovest for a hearing or petiffon for leave to intervene is filed by the above date, the Comission or an Atomic Safety and Licensing Board, designated by the Comission 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 appropriate order.
As-required by 10 CFR 12.714, 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) 'he 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 adnitted 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 speciffe 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 este.b11sh 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 amen &nents under consideration.
The contention must be one which, if proven, would m
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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 pemitted to participate as a party.
Those pemitted to intervene become parties to the proceeding, subject to any liettations 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 Comission will make a final determination on the issue of no significant hazards considerations.
The final detemination will serve to decide when the hearing is held.
If the final detemination is that the request for amendment involves no significe,s hazards consideration, the Commission may issue the amendment and make it effective, notwithstanding the reouest for a hearing. Any hearing held j
would take place after issuance of the amendment.
If a final determination is that the amendment involves a significant l
hazards consideration, any hearing held would take place before the issuance I
g of any amendment.
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Normally, the Comission will not issue the amendment until the expiration of the 30-day notice period. However, should circumstances chan0e during the notice period such that failure to act in a timely way would result, for example, 1
in derating or i;hutdown of the facility, the Comission may issue the Ifeense amendment before the expiration of the 30-day notice period, provided that its final determination is that the amendment involves no significant hazards considerations.
The final determination will consider all public and State l
l comments received. Should the Commission take this action, it will publish a l
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7 notice of issuance and provide for opportunity for a hearing after issuance.
1 The Comission expects that the need to take this action will occur very j
infrequently.
A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Comission, U.S. Nuclear. Regulatory Comission.
Washington, D.C. 20555, Attention: Docketing and Service Branch, or may be delivered to the Comission's Public Document Room, the Gelman Building, 2120 L
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Street, N.W., Washington, D.C., by the above date. Where petitions are 'iled l
during the last ten (10) days of the notice period, it is requested that the
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petitioner promptly so inform the Comission by a toll-free telephone call to i
Western Unice at 1-(800)325-6000(inMissouri 1-(800)342-6700).
The Western Union operator should be given Datagram Identification Number 3737 and the l
following message addressed to Richard H. Wessman, Project Director:
(petitioner'snameandtelephonenumber),(datepetitionwasmailed),
(plant name), and (publication date and page number of this FEDERAL REGISTER i
netice). A copy of the petition should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Comission. Washington, D.C. 20555, k
and to Thomas Dignan, Esq., Ropes 8 Gray, 225 Franklin Street, Boston, 1
Massachusetts 02110, attorney for the Ifcensee.
Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a detemination by the Comission, the presiding officer or the Atomic
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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)(1)-(v) and2.714(d).
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4 For further details with respect to this action, see the application for atendment dated September 21, 1988, which is available for public
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inspection at the Comission's Public Document Room, the Gelman Building, 2120 L Street, N.W., Washington, D.C. 20555 and at the Local Public Document Room located at the Exeter Public Library, Founders Park, Exeter, New Hampshire 03833.
l Dated at Rockville, Maryland, this f 9 #ay of' Ii
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FOR THE NUCLEAR REGULATORY COWISSION Victor Nerses, Project Manager Project Directorate I-3 Division of Reactor Projects I/II Office of Nuclear Peactor Regulation 4
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