ML20056G948
| ML20056G948 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/26/1993 |
| From: | Stone J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056G949 | List: |
| References | |
| NUDOCS 9309070359 | |
| Download: ML20056G948 (9) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION SALEM NUCLEAR GENERATING STATION. UNIT 2 DOCKET NO. 50-311 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE. PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION. AND OPPORTUNITY FOR A HEARING The U.S. Nuclear Regulatory Comission (the Comission) is considering l
issuance of an amendment to Facility Operating License No. DPR-75 issued to Public Service Electric and Gas Company (the licensee) for operation of the Salem Nuclear Generating Station, Unit 2, located in Salem County, New Jersey.
The proposed amendment would modify the Technical Specifications for the A.C. power sources, on a one time basis, to allow connection of two new 500/13.8 kv transformer bus sections as part of the Salem switchyard project during the Unit I lith refueling outage.
The change would extend the allowed outage time for one inoperable offsite power circuit from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> for two separate action statement entries to allow switchyard modifications.
It would also modify the emergency diesel generator testing requirements during the action statement entries.
Before issuance of the proposed license amendment, the Comission will i
have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations.
The Comission has made a proposed determination that the amendment request involves no significant hazards consideration.
Under the Comission'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 9309070359 930826 PDR ADOCK 05000311 P
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, 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 i
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 i
consideration, which is presented below:
The proposed changes to Technical Specification 3.8.1.1 for Salem Unit No. 2:
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do not involve a significant increase in the probability or
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consequences of an accident previously evaluated.
The proposed change to the Salem Generating Station (SGS) Unit 2 Technical Specifications would allow extension of the action statements 3.8.1.1.a and 3.8.1.1.b, for one inoperable offsite power circuit, from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />.
This extension would apply to two separate action statement entries to enable bus connections for new 500/13.8 kv transformers as part of the Salem Switchyard Project.
The proposed change would also reduce the number of Emergency Diesel Generator tests associated with the action statement entries.
l The Salem Probabilistic Risk Assessment was used to compare the impact of extending the action time vs. the impact of manual reactor shutdown on core damage probability. The PRA results support two l
conclusions:
- 1) the risk of operating SGS Unit 2 for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> beyond the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action time is less than the risk of shutting down the unit upon expiration of the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock; and 2) increase in core damage probability associated with the increased action time is insignificant.
With one 500/13.8 kv transformer deenergized, and Unit 1 in a refueling outage, Unit 1 plant loads will be supplied by the one j
energized transformer. With Unit 2 operating, its plant electrical loads will be powered from the Unit 2 main generator via the i
Auxiliary Power Transformer (APT).
In the event of a Unit 2 trip, j
the group bus (nonvital) loads would be transferred to the one 500/13.8 kv transformer.
In order to minimize the effects of the potential load transfer, a 500/13.8 kv transformer will not be deenergized until the large Unit 1 balance of plant loads (i.e.,
condensate pumps, circulating water pumps, heater drain pumps and turbine auxiliaries cooling pumps), and reactor coolant pumps are secured.
This will reduce the base load on the 500/13.8 kv transformer to accommodate the potential Unit 2 load transfer. The l
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. 500/13.8 kv transformers will not be removed from service unless the three Unit 2 EDG's are operable.
These EDG's will be available to provide vital power in the event of a loss of offsite power.
The switchyard activities performed during the Unit I refueling outage are scheduled such that redundant decay heat removal and A.C.
power capability will be maintained. The modifications will be performed in accordance with OSHA requirements relative to minimum clearance distances for energized equipment, and will be subject to the operations department administrative controls for switchyard equipment.
The proposed change would also exempt the Unit 2 EDG's from repetitive testing during the action statement entries. The Unit 2 EDG's will have been successfully tested to demonstrate operability r
prior to deenergizing a 500/13.8 kv transformer.
Implementation of the switchyard modifications would not challenge EDG operability.
The Improved Standard Technical Specifications as approved by NRC in NUREG 1431 do not require EDG testing with an inoperable offsite circuit.
Based on the above, the proposed changes do not involve a significant increase in probability or consequences of an accident.
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do not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed change would extend the allowable time that SGS Unit 2 may operate with one inoperable offsite power circuit.
It would not allow the plant to operate in any new configuration that is l
prohibited by the present plant Technical Specifications. The proposed change includes an exception to repetitive diesel testing while in an action statement for inoperable offsite power circuit.
Deenergizing a 500/13.8 kv transformer will not affect EDG operability, and would not involve any changes to EDG operation.
Therefore, the proposed changes do not involve any new or different kind of accident from any previously evaluated.
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do not involve a significant reduction in a margin of safety.
The Technical Specification requirements for A.C. power sources ensure that redundant electrical power is available to mitigate the consequences of any design basis accident and bring the plant to a safe shutdown condition. The proposed change would not affect the ability of SGS Unit 2 to recover from any design basis transient involving loss of offsite power plus a single failure of one EDG.
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, l Unit I will be shutcown with redundant decay heat removal capability during implementation of the proposed change. Therefore, the proposed changes do not involve a 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.
l 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.
l Any comments received within 30 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 30-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 j
may issue the license amendment before the expiration of the 30-day notice period, provided that its final determination is that the amendment involves l
no significant hazards consideration. The final determination will 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 hearing after issuance. The Commission expects that the need to take this action will occur very infrequently.
Written comments may be submitted by mail to the Rules Review and Directives Branch, Division of Freedom of Information and Publications Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555, and should cite the publication date and page number of
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I i this FEDERAL REGISTER notice. Written coments 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 coments 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 October 1,1993
, 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 i
who wishes to participate 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 Comission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.
Interested persons should consult a current copy of 10 CFR 2.714 which is available at the Comission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555 and at the local public document room located at the Salem Free Public Library,112 West Broadway, Salem, New Jersey 08079.
If a request for a hearing or petition 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; i
and the Secretary or the designated Atomic Safety and Licensing Board will 1ssue a notice of hearing or an appropriate order.
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! i 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 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 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 i
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 j
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 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 i
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.f l aware and on which the petitioner intends to rely to establish 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 i
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.
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l 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 Comission 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 Comission may issue the amendment and make it imediately 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 j
filed with the Secretary of the Comission, U.S. Nuclear Regulatory Comission, Washington, DC 20555, Attention: Docketing and Services Branch,
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Building, 2120 L Street, NW., Washington, DC 20555, 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 Comission by a toll-free I
telephone call to Western Union at 1-(800) 248-5100 (in Missouri 1-(800) 342-6700).
The Western Union operator should be given Datagram Identification Number N1023 and the following message addressed to Michael L. Boyle, Acting Director, Prcject Directorate I-2:
petitie.er'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 Comission, Washington, DC 20555, and to Mark J. Wetterhahn, Esquire, Winston and Strawn, 1400 L Street, NW., Washington, DC 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 entertained j
absent a determination by the Comission, 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 the factors specified in 10 CFR 2.714(a)(1)(1)-(v) and 2.714(d).
For further details with respect to this action, see the application for amendment dated August 4, 1993, and supplemented by letter dated August 24, 1993, which are available for public inspection at the Comission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555
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i I and at the local public document room located at the Salem Free Public Library, 112 West Broadway, Salem, New Jersey 08079.
Dated at Rockville, Maryland, this 26th day of August 1993.
FOR THE NUCLEAR REGULATORY COMMISSION l
l James C. Stone, Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation n