ML051260041

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FRN: General Notice. Susquehanna Steam Electric Station, Units 1 and 2 - Notice of Consideration of Issuance of Amend. to Facility Operating License, Prop. No Significant Hazards Consid. Determin., and Oppor. for a Hearing
ML051260041
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 05/05/2005
From: Richard Guzman
NRC/NRR/DLPM/LPD1
To: Shriver B
Susquehanna
Guzman R
References
Federal Register Citation, TAC MC6825, TAC MC6826
Download: ML051260041 (12)


Text

May 5, 2005 Mr. Bryce L. Shriver President-PPL Generation and Chief Nuclear Officer PPL Susquehanna, LLC Two North Ninth Street, GENTW15 Allentown, PA 18101-1179

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING (TAC NOS. MC6825 AND MC6826)

Dear Mr. Shriver:

Enclosed is a copy of a Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity For a Hearing, related to your application for an amendment dated April 27, 2005, as supplemented by letter dated May 4, 2005, for Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2).

The proposed amendment would revise the SSES 1 and 2, Technical Specification 3.8.4, DC Sources-Operating, Condition A, to address new required actions for the condition in which a 125 volt direct current (VDC) charger is taken out of service for the purposes of a special inspection and related activities. The proposed changes would be in effect until the special inspection and related activities are completed on each of the 125 VDC Class 1E battery chargers but no later than 60 days following the issuance of the Unit 1 and 2 amendments.

Specifically, required Action A.2.1 would require that surveillance requirement 3.8.6.1 will be performed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and once-per-12 hours thereafter; and required Action A.2.2 would restrict the restoration time for the inoperable electrical power subsystem to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

This notice has been forwarded to the Office of Federal Register for publication.

Sincerely,

/RA/

Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosure:

As stated cc w/encl: See next page

May 5, 2005 Mr. Bryce L. Shriver President-PPL Generation and Chief Nuclear Officer PPL Susquehanna, LLC Two North Ninth Street, GENTW15 Allentown, PA 18101-1179

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING (TAC NOS. MC6825 AND MC6826)

Dear Mr. Shriver:

Enclosed is a copy of a Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity For a Hearing, related to your application for an amendment dated April 27, 2005, as supplemented by letter dated May 4, 2005, for Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2).

The proposed amendment would revise the SSES 1 and 2, Technical Specification 3.8.4, DC Sources-Operating, Condition A, to address new required actions for the condition in which a 125 volt direct current (VDC) charger is taken out of service for the purposes of a special inspection and related activities. The proposed changes would be in effect until the special inspection and related activities are completed on each of the 125 VDC Class 1E battery chargers but no later than 60 days following the issuance of the Unit 1 and 2 amendments.

Specifically, required Action A.2.1 would require that surveillance requirement 3.8.6.1 will be performed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and once-per-12 hours thereafter; and required Action A.2.2 would restrict the restoration time for the inoperable electrical power subsystem to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

This notice has been forwarded to the Office of Federal Register for publication.

Sincerely,

/RA/

Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosure:

As stated cc w/encl: See next page DISTRIBUTION:

PUBLIC PDI-1 R/F CHolden RLaufer RGuzman MOBrien(2)

OGC ACRS MShanbaky, RI DLPM DPR Accession No.: ML051260014 OFFICE PDI-1/PM PDI-2/LA PDI-1/SC NAME RGuzman MOBrien RLaufer DATE 5/5/05 5/5/05 5/5/05 OFFICIAL RECORD COPY

Susquehanna Steam Electric Station, Units 1 and 2 cc:

Britt T. McKinney Michael H. Crowthers Vice President - Nuclear Site Operations Supervising Engineer PPL Susquehanna, LLC Nuclear Regulatory Affairs 769 Salem Blvd., NUCSB3 PPL Susquehanna, LLC Berwick, PA 18603-0467 Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Robert A. Saccone General Manager - Nuclear Operations Dale F. Roth PPL Susquehanna, LLC Manager - Quality Assurance 769 Salem Blvd., NUCSB3 PPL Susquehanna, LLC Berwick, PA 18603-0467 769 Salem Blvd., NUCSB2 Berwick, PA 18603-0467 Aloysius J. Wrape, III General Manager - Performance Luis A. Ramos Improvement and Oversight Community Relations Manager, PPL Susquehanna, LLC Susquehanna Two North Ninth Street, GENPL4 PPL Susquehanna, LLC Allentown, PA 18101-1179 634 Salem Blvd., SSO Berwick, PA 18603-0467 Terry L. Harpster General Manager - Plant Support Bryan A. Snapp, Esq PPL Susquehanna, LLC Assoc. General Counsel 769 Salem Blvd., NUCSA4 PPL Services Corporation Berwick, PA 18603-0467 Two North Ninth Street, GENTW3 Allentown, PA 18101-1179 Gregory F. Ruppert General Manager - Nuclear Engineering Supervisor - Document Control Services PPL Susquehanna, LLC PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Two North Ninth Street, GENPL4 Berwick, PA 18603-0467 Allentown, PA 18101-1179 Rocco R. Sgarro Richard W. Osborne Manager - Nuclear Regulatory Affairs Allegheny Electric Cooperative, Inc.

PPL Susquehanna, LLC 212 Locust Street Two North Ninth Street, GENPL4 P.O. Box 1266 Allentown, PA 18101-1179 Harrisburg, PA 17108-1266 Walter E. Morrissey Director - Bureau of Radiation Protection Supervising Engineer Pennsylvania Department of Nuclear Regulatory Affairs Environmental Protection PPL Susquehanna, LLC P.O. Box 8469 769 Salem Blvd., NUCSA4 Harrisburg, PA 17105-8469 Berwick, PA 18603-0467

Susquehanna Steam Electric Station, Units 1 and 2 cc:

Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 35, NUCSA4 Berwick, PA 18603-0035 Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Board of Supervisors Salem Township P.O. Box 405 Berwick, PA 18603-0035 Dr. Judith Johnsrud National Energy Committee Sierra Club 443 Orlando Avenue State College, PA 16803

7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NO. 50-387 AND 50-388 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 Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. NPF-14 and NPF-22, issued to PPL Susquehanna, LLC (PPL, the licensee), for operation of the Susquehanna Steam Electric Station, Units 1 and 2, located in Berwick, Pennsylvania.

The proposed amendment would revise the Technical Specification (TS) 3.8.4, DC Sources-Operating, to address new required actions for the condition in which a 125 volt direct current (VDC) charger is taken out of service for the purposes of a special inspection and related activities. The proposed changes would be in effect until the special inspection and related activities are completed on each of the 125 VDC Class 1E battery chargers but no later than 60 days following the issuance of the Unit 1 and 2 amendments. Specifically, required Action A.2.1 would require that surveillance requirement 3.8.6.1 will be performed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and once-per-12 hours thereafter; required Action A.2.2 would restrict the restoration time for the inoperable electrical power subsystem to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

The exigent amendment request is being made because of the desire to verify, on an expedited basis, that the Unit 1 125 VDC battery chargers are not degraded such that a failure could occur as was experienced on Unit 2 on April 10, 2005. The current TS requirements do

not afford enough the time to maintain 100% power operation and perform the desired inspections and related activities. The Unit 2 TSs are being requested as a contingency should it be necessary to perform further work on the Unit 2 125 VDC battery chargers as a result of the ongoing Unit 2 125 VDC cause evaluation.

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.

Pursuant to 10 CFR 50.91(a)(6) for amendments to be granted under exigent circumstances, the NRC staff must determine 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 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. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

No. The proposed changes affect Technical Specification (TS) 3.8.4 for DC Sources - Operating. The proposed changes add new Required Actions for Unit 1 and Unit 2 to specifically address a Class 1E 125 VDC electrical power subsystem that has been taken out of service to perform special inspection and related activities. These changes rely upon the capability of providing the battery charger function by an alternate means (e.g., a 125 [volt direct current] VDC portable battery charger) to justify the proposed completion times. The DC electrical power systems, including associated battery chargers, are not initiators to any accident sequence analyzed in the Final Safety Analysis Report (FSAR).

Operation in accordance with the proposed TS ensures that the DC electrical power systems are capable of performing their functions as described in the FSAR. Therefore, the mitigative functions supported by the DC Power Systems will continue to provide the protection assumed by the analysis.

Based on the above, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

No. The proposed changes involve revising TS 3.8.4 DC Sources-Operating, for the DC electrical power systems. These changes rely upon the capability of providing the battery charger function by an alternate means to justify the proposed completion times when a normal battery charger is taken out of service to perform special inspections and related activities. The DC electrical power systems, which include the associated battery chargers, are not initiators to any accident sequence. Rather, the DC electrical power systems are used to supply equipment used to mitigate an accident. These mitigative functions, supported by the DC electrical power systems, provide the protection assumed by the safety analysis described in the FSAR. The portable battery charger will be connected to the Class 1E 125 VDC subsystem using a double isolation method.

Therefore, there are no new types of failures or new or different kinds of accidents or transients that could be created by these changes.

Based on the above, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

No. The margin of safety is established through equipment design, operating parameters, and the setpoints at which automatic actions are initiated. The proposed changes do not adversely affect operation of any plant equipment.

These changes do not result in a change to the setpoints at which protective actions are initiated. Sufficient DC electrical system capacity is ensured to support operation of mitigation equipment. The equipment fed by the DC electrical sources will continue to be provided adequate power to safety-related loads in accordance with the safety analysis. Therefore, the proposed changes do not involve a significant reduction in a 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. 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 14 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 14-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 14-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 Commission take 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.

Written comments may be submitted by mail to the Chief, Rules and Directives Branch, Division of Administrative Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and should cite the publication date and page number of this Federal Register notice. Written comments may also be delivered to Room 6D59, Two White Flint North, 11545 Rockville Pike, Rockville, Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays. Documents may be examined, and/or copied for a fee, at the NRCs Public Document Room, located at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland.

The filing of requests for hearing and petitions for leave to intervene is discussed below.

Within 60 days after the date of publication of this notice, 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 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 Commissions Rules of Practice for Domestic Licensing Proceedings in

10 CFR Part 2. Interested persons should consult a current copy of 10 CFR 2.309, which is available at the Commissions PDR, located at One White Flint North, Public File Area 01F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible from the Agencywide Documents Access and Management Systems (ADAMS)

Public Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or a presiding officer designated by the Commission or by the Chief Administrative Judge of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the Chief Administrative Judge of the Atomic Safety and Licensing Board will issue a notice of a hearing or an appropriate order.

As required by 10 CFR 2.309, 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 general requirements: 1) the name, address and telephone number of the requestor or petitioner; 2) the nature of the requestors/petitioners right under the Act to be made a party to the proceeding;

3) the nature and extent of the requestors/petitioners property, financial, or other interest in the proceeding; and 4) the possible effect of any decision or order which may be entered in the proceeding on the requestors/petitioners interest. The petition must also identify the specific contentions which the petitioner/requestor seeks to have litigated at the proceeding.

Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted. In addition, the petitioner/requestor shall provide a brief explanation of the bases for 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/requestor must also provide references to those specific sources and documents of which the petitioner/requestor is aware and on which the petitioner/requestor intends to rely to establish those facts or expert opinion. The petitioner/requestor 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 entitle the petitioner/requestor to relief. A petitioner/requestor who fails to satisfy 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.

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 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.

Nontimely requests and/or petitions and contentions will not be entertained absent a determination by the Commission or the presiding officer of the Atomic Safety and Licensing Board that the petition, request and/or the contentions should be granted based on a balancing

of the factors specified in 10 CFR 2.309(c)(1)(i)-(viii).

A request for a hearing or a petition for leave to intervene must be filed by: 1) first class mail addressed to the Office of the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemaking and Adjudications Staff; 2) courier, express mail, and expedited delivery services: Office of the Secretary, Sixteenth Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland, 20852, Attention: Rulemaking and Adjudications Staff; 3) E-mail addressed to the Office of the Secretary, U.S. Nuclear Regulatory Commission, HEARINGDOCKET@NRC.GOV; or 4) facsimile transmission addressed to the Office of the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC, Attention: Rulemakings and Adjudications Staff at (301) 415-1101, verification number is (301) 415-1966. A copy of the request for hearing and petition for leave to intervene should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and it is requested that copies be transmitted either by means of facsimile transmission to 301-415-3725 or by e-mail to OGCMailCenter@nrc.gov. A copy of the request for hearing and petition for leave to intervene should also be sent to Bryan A. Snapp, Esquire, Assoc. General Counsel, PPL Services Corporation, 2 North Ninth St., GENTW3, Allentown, PA 18101-1179, attorney for the licensee.

For further details with respect to this action, see the application for amendment dated April 27, 2005, as supplemented by letter dated May 4, 2005, which are available for public inspection at the Commission's Public Document Room (PDR), located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management System's (ADAMS) Public Electronic Reading Room on the Internet at the NRC web site http://www.nrc.gov/reading-rm.html. Persons who do not have access to ADAMS or

who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, 301-415-4737, or by e-mail to pdr@nrc.gov.

Dated at Rockville, Maryland, this 5th day of May 2005.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation