ML17146A978
| ML17146A978 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/25/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17146A979 | List: |
| References | |
| NUDOCS 8710010280 | |
| Download: ML17146A978 (9) | |
Text
7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION PENNSYLVANIA POh'ER A LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NOS.
50-387 AND 50-388 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS 4
CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING The U.S. Nuclear Regulatory Comission (the Commission) is considering issuance of amendments to Facility Operating License Nos.
NPF-14 and NPF-22 issued to Pennsylvania Power and Light Company, and Allegheny Electric Cooperative Inc., for operation of Susquehanna Steam Electric Station (SSES),
Units 1 and 2, located in Luzerne County, Pennsylvania.
The proposed amendments would revise the SSES Technical Specifications to permit changes to 125 volt dc battery profile contained in the Technical Specifications.
The proposed changes were previously published in bi-weekly FEDERAL REGISTER NOTICES dated July 15, 1987 (52 FR 26595),
and September 23, 1987 (52 FR 35802) in accordance with the licensee's application for amendment dated June 10, 1987, and as revised by a letter dated September 1, 1987.
By a letter dated September 23, 1987, the licensee has again revised its request for an amendment and has confirmed that the required battery load profiles can be met with the existing 125 volt dc batteries.
The licensee has had difficulty in obtaining qualified new batteries of a larger capacity and has therefore withdrawn its proposal to install two new batteries.
Before issuance of the proposed license amendments, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations.
8V>aoi02aO,87OSaS PDR ADOCK'05000387, PDR
~
~ 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 accordance with the proposed amendments 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.
The staff has reviewed the licensee's revised request and concurs with the following basis and conclusion provided by the licensee in its September 23, 1987 submittal.
The proposed change does not:
(1) involve an increase in the probability or consequences of an accident previously evaluated.
Final Safety Analysis Report (FSAR) Subsection 8.3.2. 1. 1.4 states that the station batteries have sufficient capacity without the charger to independently supply the required loads for four hours.
The Technical Specifications require that the batteries be surveilled to dummy loads which are greater than the design loads.
An assessment has been performed by our engineering department which verifies, that the batteries have adequate capacity to power the actual loads on the 125 V
DC system.
The new load Specifications envelop the actual loads(;)
(2) create the possibility of a new or different kind of accident from any previously evaluated.
As stated in Part (1), the batteries have sufficient capacity to power the actual battery loads thus enabling them to perform thei~ intended function.
Any postulated accident resulting from this change is bounded by previous analysis(;
and)
(3) involve a reduction in the margin of safety.
IEEE 485 requires that the related battery capacity include a
margin for aging of the battery and the temperature of the batteries'nvironment at the beginning of battery
f
life.
This margin allows replacement of the battery when its capacity is decreased to 80% of its rated capacity (100% design load).
As...if the battery capacity is corrected for a temperature of 65'F (the lowest observed electrolyte temperatures),
the batteries currently have at least a
25K margin in accordance with IEEE 485.
AIso, based upon the vendor's aging curves it is not expected that the batteries will significantly deteriorate during the next 3 - 4 years.
With the increased battery loads and the installation of the AVOWS ARI System it can be concluded that the overall margin of safety of the plant is improved.
The Comnission is seeking public comments on this proposed determination.
Any comnents received within 30 days after the date of publication of this notice will be considered in making any final determination.
The Comnission will not normally make a final determination unless it receives a request for a hearing.
Written coneents may be submitted by mail to the Rules and Procedures Branch, Division of Rules and Records, Office of Administration, U.S. Nuclear Regulator5r Comnission, Washington, D. C.
- 20555, and should cite the publication date and page number of this FEDERAL REGISTER notice.
Written contents may also be delivered to Room 4000, Maryland National Bank Building, 7735 Old Geortetown
- Road, Bethesda, Maryland from 8:15 a.m. to 5:00 p.m.
Copies of written comments received may be examined at the NRC Public. Document
- Room, 1717 H Street, N.W.,
Washington, D.C.
The filing of requests for hea~ing and petitions for leave to intervene is discussed below.
By November 2, 1987, 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 nroceeding 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 Commission's "Rules o~ Practice for Domestic Licensing Proceedings" in 10 CFR Part
- 2. 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 Licensino 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 52.714, 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 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 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, and the bases fnr each contention set forth with reasonable specificity.
Contentions shall be limited to matters within the scope of the amendment under consideration.
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 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 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 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 involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment.
Normally, the Commission will not issue the amendment until the expiration of the 30-day notice period.
However, should circ'umstances change during the notice period such that 'failure to act in a timely way would result 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 amendment involves no significant hazards consideration.
The final determination will consider all public and State comments received.
Should the Comnission take this action, it will publish 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.
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, D.C.
20555, Att:
Docketing and Service Branch, or may be delivered to the Commission's Public Document
- Room, 1717 H Street, NW Washington, D.C., by the above date.
Where petitions are filed during the last ten (10) days nf the notice period, it is requested that the petitioner promptly so inform the Commission by a toll-free telephone call to Western Union at (800) 325-6000 (in Missouri (800) 342-6700).
The Western Union operator should be given Datagram Identification Number 3737 and the following message addressed to Walter R. Butler, Director, Project Directorate I-2, Division of Reactor Projects I/II: 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 General
- Counsel, U. S. Nuclear Regulatory Commission, Washington, D.C.
- 20555, and to Jay Silberg, Esquire, Shaw, Pittman, Potts and Trowbridge, 2300 N Street N.W., Washington, D.C.
20037.
Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions 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 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 10,
- 1987, as amended and supplemented September 1 and 23, 1987, which are available for public inspection at the Commission's Public Document
- Room, 1717 M Street, NW, Washington, D.C.
- 20555, and at the Osterhout Free Library, Reference Department, 71 South Franklin Street, Wilkes-Barre, Pennsylvania 18701.
Dated at Bethesda, Maryland, this 25th day of september.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
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