ML020090661
| ML020090661 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 01/17/2002 |
| From: | Milano P NRC/NRR/DLPM/LPD1 |
| To: | Kansler M Entergy Nuclear Operations |
| Milano, P , NRR/DLPM, 415-1457 | |
| References | |
| TAC MB3356 | |
| Download: ML020090661 (11) | |
Text
January 17, 2002 Mr. Michael Kansler Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 - ISSUANCE OF AMENDMENT RE: TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENT REGARDING STATION BATTERY 31 TERMINAL VOLTAGE (TAC NO. MB3356)
Dear Mr. Kansler:
The Commission has issued the enclosed Amendment No. 209 to Facility Operating License No. DPR-64 for the Indian Point Nuclear Generating Unit No. 3. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated October 23, 2001, as supplemented by letter dated December 20, 2001.
The amendment revises TS Surveillance Requirement (SR) 3.8.4.1 to support replacement of the station batteries. The amendment will allow for separate required terminal voltage values for the new 31 and 32 station batteries.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely,
/RA/
Patrick D. Milano, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-286
Enclosures:
- 1. Amendment No. 209 to DPR-64
- 2. Safety Evaluation cc w/encls: See next page
January 17, 2002 Mr. Michael R. Kansler Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 - ISSUANCE OF AMENDMENT RE: TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENT REGARDING STATION BATTERY 31 TERMINAL VOLTAGE (TAC NO. MB3356)
Dear Mr. Kansler:
The Commission has issued the enclosed Amendment No. 209 to Facility Operating License No. DPR-64 for the Indian Point Nuclear Generating Unit No. 3. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated October 23, 2001, as supplemented by letter dated December 20, 2001.
The amendment revises TS Surveillance Requirement (SR) 3.8.4.1 to support replacement of the station batteries. The amendment will allow for separate required terminal voltage values for the new 31 and 32 station batteries.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely,
/RA/
Patrick D. Milano, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-286
Enclosures:
- 1. Amendment No. 209 to DPR-64
- 2. Safety Evaluation cc w/encls: See next page
- SE provided on 1/3/02; no major changes were made.
Accession Number: ML020090661 OFFICE PDI-1\PM PDI-1\LA OGC PDI-1\ASC EEIB:DE*
NAME PMilano SLittle DCummings JMunday CHolden DATE 1/15/02 1/15/02 1/15/02 1/16/02 1/3/02 Official Record Copy
DATED: January 17, 2002 AMENDMENT NO. 209 TO FACILITY OPERATING LICENSE NO. DPR-64 INDIAN POINT UNIT 3 PUBLIC PDI R/F Acting Section Chief SLittle PMilano OGC GHill (2)
WBeckner SSaba ACRS BPlatchek, RI cc: Plant Service list
Indian Point Nuclear Generating Unit No. 3 cc:
Mr. Jerry Yelverton Mr. Harry P. Salmon, Jr.
Chief Executive Officer Director of Oversight Entergy Operations Entergy Nuclear Operations, Inc.
1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Mr. Robert J. Barrett Mr. James Comiotes Vice President - Operations Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 3 Indian Point Nuclear Generating Unit 3 295 Broadway, Suite 3 295 Broadway, Suite 3 P. O. Box 308 P.O. Box 308 Buchanan, NY 10511-0308 Buchanan, NY 10511-0308 Mr. Dan Pace Mr. John Donnelly Vice President Engineering Licensing Manager Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
440 Hamilton Avenue Indian Point Nuclear Generating Unit 3 White Plains, NY 10601 295 Broadway, Suite 3 P.O. Box 308 Mr. James Knubel Buchanan, NY 10511-0308 Vice President Operations Support Entergy Nuclear Operations, Inc. Mr. John McCann 440 Hamilton Avenue Manager, Licensing and Regulatory Affairs White Plains, NY 10601 Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 2 Mr. Joseph DeRoy 295 Broadway, Suite 1 General Manager Operations P. O. Box 249 Entergy Nuclear Operations, Inc. Buchanan, NY 10511-0249 Indian Point Nuclear Generating Unit 3 295 Broadway, Suite 3 Resident Inspectors Office P. O. Box 308 U.S. Nuclear Regulatory Commission Buchanan, NY 10511-0308 295 Broadway, Suite 3 P.O. Box 337 Mr. John Kelly Buchanan, NY 10511-0337 Director - Licensing Entergy Nuclear Operations, Inc. Regional Administrator, Region I 440 Hamilton Avenue U.S. Nuclear Regulatory Commission White Plains, NY 10601 475 Allendale Road King of Prussia, PA 19406 Ms. Charlene Fiason Licensing Mr. John M. Fulton Entergy Nuclear Operations, Inc. Assistant General Counsel 440 Hamilton Avenue Entergy Nuclear Operations, Inc.
White Plains, NY 10601 440 Hamilton Avenue White Plains, NY 10601
Indian Point Nuclear Generating Unit No. 3 cc:
Ms. Stacey Lousteau Mr. Ronald Schwartz Treasury Department SRC Consultant Entergy Services, Inc. 64 Walnut Drive 639 Loyola Avenue Spring Lake Heights, NJ 07762 Mail Stop: L-ENT-15E New Orleans, LA 70113 Mr. Ronald J. Toole SRC Consultant Mr. William M. Flynn, President Toole Insight New York State Energy, Research, and 605 West Horner Street Development Authority Ebensburg, PA 15931 Corporate Plaza West 286 Washington Avenue Extension Mr. Charles W. Hehl Albany, NY 12203-6399 SRC Consultant Charles Hehl, Inc.
Mr. J. Spath, Program Director 1486 Matthew Lane New York State Energy, Research, and Pottstown, PA 19465 Development Authority Corporate Plaza West Mr. Ronald Schwartz 286 Washington Avenue Extension SRC Consultant Albany, NY 12203-6399 64 Walnut Drive Spring Lake Heights, NJ 07762 Mr. Paul Eddy Electric Division Mr. Ronald J. Toole New York State Department SRC Consultant of Public Service Toole Insight 3 Empire State Plaza, 10th Floor 605 West Horner Street Albany, NY 12223 Ebensburg, PA 15931 Mr. Charles Donaldson, Esquire Mr. Charles W. Hehl Assistant Attorney General SRC Consultant New York Department of Law Charles Hehl, Inc.
120 Broadway 1486 Matthew Lane New York, NY 10271 Pottstown, PA 19465 Mayor, Village of Buchanan Alex Matthiessen 236 Tate Avenue Executive Director Buchanan, NY 10511 Riverkeeper, Inc.
25 Wing & Wing Mr. Ray Albanese Garrison, NY 10524 Executive Chair Four County Nuclear Safety Committee Westchester County Fire Training Center 4 Dana Road Valhalla, NY 10592
ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-286 INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 209 License No. DPR-64
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Entergy Nuclear Operations, Inc. (the licensee) dated October 23, 2001, as supplemented December 20, 2001, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-64 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 209, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Joel Munday, Acting Chief,Section I Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 17, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 209 FACILITY OPERATING LICENSE NO. DPR-64 DOCKET NO. 50-286 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page Insert Page 3.8.4-2 3.8.4-2
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 209 TO FACILITY OPERATING LICENSE NO. DPR-64 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286
1.0 INTRODUCTION
By letter dated October 23, 2001, as supplemented by letter dated December 20, 2001, Entergy Nuclear Operations, Inc. (the licensee) submitted a request for changes to the Indian Point Nuclear Generating Unit No. 3 (IP3) Technical Specifications (TSs). The requested changes would revise TS Surveillance Requirement (SR) 3.8.4.1 to support replacement of the station batteries. The changes would allow for separate required terminal voltage values for the new 31 and 32 station batteries. The December 20, 2001, letter provided clarifying information that did not change the initial proposed no significant hazards consideration determination.
2.0 BACKGROUND
IP3's lead acid station batteries 31 and 32 are required to carry expected shutdown loads following a plant trip and a loss of all AC power. They are sized to carry these loads for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> without battery terminal voltage falling below its minimum required voltage. The 31 and 32 station batteries are scheduled for replacement no later than May 31, 2002. The licensee proposes changing the existing station battery 31, which has 58 cells, with a 59-cell battery, while the new 32-station battery will remain a 58-cell battery. The change from a 58-cell battery to a 59-cell battery causes the 31-station battery to have a new terminal minimum voltage on float charge, thus necessitating a change to the current SRs.
3.0 EVALUATION Currently, SR 3.8.4.1 requires verification that the battery terminal voltage is greater than 123.5 V for both batteries 31 and 32 on float charge every 31 days. However, for the replacement, the licensee proposed the following modification to SR 3.8.4.1 to reflect the new battery configurations:
Verify battery terminal voltage on float charge is within the following limits:
(1) Greater or equal to 125.7 V for battery 31; (2) Greater or equal to 123.5 V for battery 32 with a frequency of 31 days.
The minimum float voltage for battery 31 will be 59 cells x 2.13 volt per cell = 125.7 V, and the minimum float voltage for battery 32 will be 58 cells x 2.13 volt per cell = 123.5 V. Therefore,
the new battery 32 terminal voltage requirement will not change from the previous requirement (123.5 V minimum), but the new battery 31 terminal voltage requirement will increase.
The new batteries were sized per the Institute of Electrical and Electronics Engineers (IEEE) 485-1997 Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications.
A temperature correction factor based on 60 degrees F (with a 1.11 multiplier), an aging factor of 80% (with a multiplier of 1.25), and a design margin multiplier of 1.0 were used. The results of the sizing analyses yielded the required number of positive plates necessary to meet the needed capacity. This sizing criteria is acceptable, since it ensures that the required battery capacity will be available at the end of its expected life.
When this sizing approach was applied to the replacement battery 31, using only 58 cells, the ratio of positive plates selected to positive plates required resulted in a built-in design basis margin of 1.04. To improve this margin for battery 31, the licensee decided to add a 59th battery cell. Increasing the number of cells in the battery allows for a lower voltage per cell at the end of the required discharge period. This lower voltage per cell permits utilization of more amps per positive plate. As a result of the additional cell and the associated lowering of the end of discharge voltage per cell, the ratio of selected number of positive plates to the required number of positive plates increased from 1.04 to 1.20. The 1.20 value equates to a built in 20%
Direct Current design basis margin. Because of this margin, the 59-cell configuration of battery 31 will meet the design loading requirements. In comparison, the original design basis margin for the existing batteries is 1.16. The greater design basis margin indicates that the new battery 31 configuration will be capable of meeting the design loading requirements, even though the replacement cell capacities are rated at 2400 Amp-Hours, which is lower than the original 2660 Amp-Hours of the current batteries.
The licensees evaluation shows that the new station battery 31 will have an adequate design margin, and the licensee states that the new station battery 32 will also have an adequate design margin. Because of the adequate margin associated with the proposed battery 31 and 32 configurations, we find that the proposed changes (incorporating the proper minimum allowable battery terminal voltage during float charge requirements) to TS SR 3.8.4.1 are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (66 FR 59503). Accordingly, the amendment meets the
eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: S. Saba Date: January 17, 2002