ML042870407
| ML042870407 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/14/2004 |
| From: | Licata L NRC/NRR/DLPM/LPD1 |
| To: | Kansler M Entergy Nuclear Operations |
| References | |
| TAC MC4651 | |
| Download: ML042870407 (11) | |
Text
October 14, 2004 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
PILGRIM NUCLEAR POWER STATION - NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND OPPORTUNITY FOR A HEARING FOR JUSTIFICATION TO CONTINUE OPERATION WITH A SAFETY RELIEF VALVE DISCHARGE PIPE TEMPERATURE EXCEEDING 212 DEGREES FAHRENHEIT (TAC NO. MC4651)
Dear Mr. Kansler:
Enclosed is a copy of a Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity For a Hearing related to your application for an amendment dated October 12, 2004, for the Pilgrim Nuclear Power Station (PNPS).
The proposed amendment would approve an engineering evaluation performed in accordance with PNPS Technical Specification (TS) 3.6.D.3 to justify continued power operation with safety relief valve -3C discharge pipe temperature exceeding 212 degrees Fahrenheit (EF) for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as required by TS 3.6.D.4.
This notice has been forwarded to the Office of Federal Register for publication.
Sincerely,
/RA by George F. Wunder for/
Lee A. Licata, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosure:
As stated cc w/encl: See next page
October 14, 2004 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
PILGRIM NUCLEAR POWER STATION - NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND OPPORTUNITY FOR A HEARING FOR JUSTIFICATION TO CONTINUE OPERATION WITH A SAFETY RELIEF VALVE DISCHARGE PIPE TEMPERATURE EXCEEDING 212 DEGREES FAHRENHEIT (TAC NO. MC4651)
Dear Mr. Kansler:
Enclosed is a copy of a Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity For a Hearing related to your application for an amendment dated October 12, 2004, for the Pilgrim Nuclear Power Station (PNPS).
The proposed amendment would approve an engineering evaluation performed in accordance with PNPS Technical Specification (TS) 3.6.D.3 to justify continued power operation with safety relief valve -3C discharge pipe temperature exceeding 212 degrees Fahrenheit (EF) for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as required by TS 3.6.D.4.
This notice has been forwarded to the Office of Federal Register for publication.
Sincerely,
/RA by George F. Wunder for/
Lee A. Licata, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION PUBLIC C. Holden L. Licata G. Matakas, R-I PDI-2 Reading J. Clifford E. Cobey, R-I OGC LMarsh/JLyon DLPM DPR C. Raynor ACRS ADAMS Accession Number: ML042870407 OFFICE PDI-2/PM PDI-2/LA PDI-2/SC NAME GWunder for LLicata SLittle for CRaynor DCollins for JClifford DATE 10/14/04 10/14/04 10/14/04 OFFICIAL RECORD COPY
Pilgrim Nuclear Power Station cc:
Resident Inspector Plymouth, MA 02360-5508 U. S. Nuclear Regulatory Commission Pilgrim Nuclear Power Station Mr. Jack Alexander Post Office Box 867 Manager, Reg. Relations and Plymouth, MA 02360 Quality Assurance Pilgrim Nuclear Power Station Chairman, Board of Selectmen 600 Rocky Hill Road 11 Lincoln Street Plymouth, MA 02360-5599 Plymouth, MA 02360 Mr. David F. Tarantino Chairman, Duxbury Board of Selectmen Nuclear Information Manager Town Hall Pilgrim Nuclear Power Station 878 Tremont Street 600 Rocky Hill Road Duxbury, MA 02332 Plymouth, MA 02360-5599 Office of the Commissioner Ms. Jane Perlov Massachusetts Department of Secretary of Public Safety Environmental Protection Executive Office of Public Safety One Winter Street One Ashburton Place Boston, MA 02108 Boston, MA 02108 Office of the Attorney General Mr. Stephen J. McGrail, Director One Ashburton Place Attn: James Muckerheide 20th Floor Massachusetts Emergency Management Boston, MA 02108 Agency 400 Worcester Road Dr. Robert M. Hallisey, Director Framingham, MA 01702-5399 Radiation Control Program Commonwealth of Massachusetts Chairman Executive Offices of Health and Nuclear Matters Committee Human Services Town Hall 174 Portland Street 11 Lincoln Street Boston, MA 02114 Plymouth, MA 02360 Regional Administrator, Region I Mr. William D. Meinert U. S. Nuclear Regulatory Commission Nuclear Engineer 475 Allendale Road Massachusetts Municipal Wholesale King of Prussia, PA 19406-1415 Electric Company P.O. Box 426 Mr. John M. Fulton Ludlow, MA 01056-0426 Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Steve Brennion Supt., Regulatory & Industry Affairs Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road, M/S 1
Pilgrim Nuclear Power Station cc:
Mr. Gary J. Taylor Mr. John F. McCann Chief Executive Officer Director, Nuclear Safety Assurance Entergy Operations Entergy Nuclear Operations, Inc.
1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Mr. John T. Herron Ms. Charlene D. Faison Sr. VP and Chief Operating Officer Manager, Licensing Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
440 Hamilton Avenue 440 Hamilton Avenue White Plains, NY 10601 White Plains, NY 10601 Mr. Michael A. Balduzzi Mr. Michael J. Colomb Site Vice President Director of Oversight Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 440 Hamilton Avenue 600 Rocky Hill Road White Plains, NY 10601 Plymouth, MA 02360-5508 Ms. Stacey Lousteau Mr. Stephen J. Bethay Treasury Department Director, Nuclear Assessment Entergy Services, Inc.
Entergy Nuclear Operations, Inc. 639 Loyola Avenue Pilgrim Nuclear Power Station New Orleans, LA 70113 600 Rocky Hill Road Plymouth, MA 02360-5508 Jim Sniezek 5486 Nithsdale Drive Mr. Bryan S. Ford Salisbury, MD 21801 Manager, Licensing Entergy Nuclear Operations, Inc. Mr. Kennety L. Graesser Pilgrim Nuclear Power Station 38832 N. Ashley Drive 600 Rocky Hill Road Lake Villa, IL 60046 Plymouth, MA 02360-5508 Mr. Ronald Toole Mr. Danny L. Pace 1282 Valley of Lakes Vice President, Engineering Box R-10 Entergy Nuclear Operations, Inc. Hazelton, PA 18202 440 Hamilton Avenue White Plains, NY 10601 Ms. Deb Katz, Executive Director Nuclear Security Coalition Mr. Brian OGrady c/o Citizens Awareness Network Vice President, Operations Support Box 83 Entergy Nuclear Operations, Inc. Shelburne Falls, MA 01370 440 Hamilton Avenue White Plains, NY 10601
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION ENTERGY NUCLEAR OPERATIONS, INC.
PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 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. DPR-35 issued to Entergy Nuclear Operations, Inc. (the licensee) for operation of the Pilgrim Nuclear Power Station located in Plymouth, MA.
The proposed amendment would approve an engineering evaluation performed in accordance with Pilgrim Nuclear Power Station Technical Specification (TS) 3.6.D.3 to justify continued power operation with safety relief valve (SRV) -3C discharge pipe temperature exceeding 212 degrees Fahrenheit (EF) for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as required by TS 3.6.D.4.
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 Commissions regulations.
The Commission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commissions regulations in Title 10 of the CODE OF FEDERAL REGULATIONS (10 CFR), Section 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?
Response: No.
Indication of elevated SRV discharge pipe temperature is attributed to leakage past the SRV pilot valve. Excessive leakage, corresponding to temperatures greater than 255EF, has the potential to affect SRV operability by affecting the SRV setpoint or response time. Continued operation with the discharge pipe of the SRV indicating temperatures less than 255EF ensures that the leakage past the SRV is maintained below the threshold for a leakage rate that would potentially have an effect on SRV setpoint or response time.
Administrative controls are in place to ensure that margin to the 255EF value is maintained to assure reliable operation and to reduce the potential for damage to the SRV pilot seat and disc. The SRV continues to perform the intended design/safety function with no adverse effect because the leakage past the SRV is maintained below the threshold for a leakage rate that could potentially have an adverse impact on the ability of the SRV to perform the design function. The impact of the leakage on other systems is small and all systems continue to be able to perform their intended design functions. Current accident analyses remain bounding and there is no significant increase in the consequences of any accident previously evaluated. In addition, as a result of the leakage, normal plant operating parameters are not affected and consequently there is no increased risk in a plant transient.
Therefore, the proposed change does 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?
Response: No.
Continued plant operation with elevated SRV-3C discharge pipe temperature within the bounds of the established administrative controls ensures that the leakage past the SRV is maintained below the threshold for a leakage rate that would potentially have an effect on SRV setpoint or response time. This ensures that the SRV will perform the intended design/safety function. The leakage does not adversely impact the ability of any system to perform its design function. The methods governing plant operation and testing remain consistent with current safety analysis assumptions. Therefore, the proposed change does 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?
Response: No.
Continued operation with the of SRV-3C discharge pipe indicating temperature in excess of 212EF does not adversely affect existing plant safety margins or the reliability of the equipment assumed to operate in the safety analysis. The leakage does not result in excess SRV setpoint drift or response time changes. The imposed administrative controls on plant operation provide assurance that there will be no adverse effect on the ability of the SRV to perform the intended design/safety function.
There are no changes being made to safety analysis assumptions, safety limits or safety system settings that would adversely affect plant safety.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
The NRC staff has reviewed the licensees 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 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 60 days after the date of publication of this notice. The Commission may issue the license amendment before expiration of the 60-day period provided that its final determination is that the amendment involves no significant hazards consideration. In addition, the Commission may issue the amendment prior to the expiration of the 30-day comment period should circumstances change during the 30-day comment period such that failure to act in a timely way would result, for example in derating or shutdown of the facility. Should the Commission take action prior to the expiration of either the comment period or the notice period, it will publish in the Federal Register a notice of issuance. Should the Commission make a final No Significant
Hazards Consideration Determination, any hearing will take place 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 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, Public File Area O1 F21, 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 is aware and on which the petitioner intends to rely to establish those facts or expert opinion. The petition must include 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 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(a)(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 email to OGCMailCenter@nrc.gov. A copy of the request for hearing and petition for leave to intervene should also be sent to the J. M. Fulton, Esquire, Assistant General Counsel, Pilgrim Nuclear Power Station, 600 Rocky Hill Road, Plymouth, Massachusetts 02360-5599, attorney for the licensee.
For further details with respect to this action, see the application for amendment dated October 12, 2004, which is available for public inspection at the Commissions PDR, located at One White Flint North, File Public Area O1 F21, 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/adams.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 14th day of October, 2004.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
George F. Wunder, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation