ML073110364
| ML073110364 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 11/21/2007 |
| From: | Kimberly Green NRC/NRR/ADRO/DLR/RLRB |
| To: | Entergy Nuclear Operations |
| Green, Kimberly NRR/DLR/RLRB 415-1627 | |
| References | |
| Download: ML073110364 (9) | |
Text
November 21, 2007 LICENSEE: Entergy Nuclear Operations, Inc.
FACILITY: Indian Point Nuclear Generating Unit Nos. 2 and 3
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON NOVEMBER 1, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc., held a telephone conference call on November 1, 2007, to discuss and clarify the staffs draft requests for additional information (D-RAIs) concerning the Indian Point Nuclear Generating Unit Nos. 2 and 3, license renewal application. The telephone conference call was useful in clarifying the intent of the staffs D-RAIs.
provides a listing of the participants and Enclosure 2 contains a listing of the D-RAIs discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
/RA/
Kimberly Green, Safety Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
Enclosures:
- 1. List of Participants
- 2. List of Draft Requests for Additional Information cc w/encls: See next page
ML073110364 OFFICE LA:DLR PM:RPB2:DLR OCG BC:RER2:DLR BC:RPB2:DLR NAME IKing KGreen STurk RAuluck RFranovich DATE 11/13/07 11/19/07 11/19/07 11/21/07 11/21/07
ENCLOSURE 1 TELEPHONE CONFERENCE CALL INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS NOVEMBER 1, 2007 PARTICIPANTS AFFILIATIONS Kim Green U.S. Nuclear Regulatory Commission (NRC)
Rao Karipineni NRC Bruce Heida NRC Mike Stroud Entergy Nuclear Operations, Inc. (Entergy)
Ted Ivy Entergy Leland Loyd Entergy Reza Ahrabli Entergy Charlie Caputo Entergy
ENCLOSURE 2 DRAFT REQUESTS FOR ADDITIONAL INFORMATION (D-RAIs)
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION NOVEMBER 1, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc., held a telephone conference call on November 1, 2007, to discuss and clarify the following draft requests for additional information (D-RAIs) concerning the Indian Point Nuclear Generating Unit Nos. 2 and 3, license renewal application (LRA).
D-RAI 2.3.1.3-1 The Reactor Coolant Pressure Boundary for Unit 2 is depicted on LRA Drawing LRA-9321-2738, under systems Pressurizer and Reactor Coolant, Sheet 1 as denoted in page 2.3-20. Please clarify if there are any additional sheets depicting the Reactor Coolant Pressure Boundary, and if so, where they can be found in the LRA submittal. If they are not already in the submittal, please provide the drawing(s) to the NRC staff.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI (renumbered as RAI 2.3A.1.3-1).
D-RAI 2.3.2.3-1 (A) The Containment Isolation Support Systems (CISS) are described in LRA Section 2.3.2.3 and depicted on several license renewal drawings listed in LRA Section 2.3.2.3. License renewal drawing LRA-9321-F-27463 displays Isolation Valve Seal Water System. The drawing contains two components, PCV 1076 and PCV 1090, which are in the pressure boundary. The components are highlighted indicating that the components are subject to an aging management review (AMR); however, the sensing lines connecting these components to the main line are not highlighted. Please provide additional information to describe what these components are, their intended function, and why the sensing lines are not subject to an AMR.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI (renumbered as RAI 2.3B.2.3-1).
(B) License renewal drawing LRA-9321-2726 (page 2.3-63) depicts the Penetration and Liner Weld Joint Channel Pressurization System. The drawing contains several line mounted components denoted by component numbers PRV PCV 1193 through PRV PCV 1200. Though the subject components are located in lines with a pressure boundary function, the components themselves are not highlighted. Clarify whether these components are within the scope of license renewal in accordance with 10 CFR 54.4(a), and subject to AMR in accordance with 10 CFR 54.21(a)(1). If they are excluded from the scope of license renewal and not subject to AMR, provide justification for the exclusion.
Discussion: The applicant indicated that the question is clear. The staff will modify this question to also include a reference to LRA drawing LRA-9321-27263 (Unit 3). This D-RAI will be sent as formal RAIs (renumbered as RAI 2.3A.2.3-1 and RAI 2.3B.2.3-2).
D-RAI 2.3.2.5-1 The containment penetrations covered in this section are a grouping of containment penetration components not evaluated with other systems. The scope of the evaluation in this section is passive mechanical components not evaluated in other system evaluations. The evaluation in this section includes only the containment penetration portion of these systems. The applicable systems were described in this section because their only intended function is performed by a containment penetration.
(A) License renewal drawing LRA-9321-2027 referenced for Unit 2 depicts the containment penetration portion of steam supply and condensate return from various nuclear services and unit heaters. This system is not described in LRA section 2.3.2.5 or elsewhere in the LRA.
Please provide a brief description of this system, including the license renewal intended functions.
Discussion: The applicant stated that portion of the drawing being referenced is the auxiliary steam system which is described in LRA Section 2.3.4.5. This system has intended functions other than containment isolation. LRA Section 2.3.4.5 provides a UFSAR reference and indicates that the containment isolation function of the auxiliary steam system is evaluated in LRA Section 2.3.2.5. Therefore, this question is withdrawn and will not be sent as a formal RAI.
(B) License renewal drawing LRA-9321-72043 depicts the Reactor Vessel Instrumentation System. This drawing was referenced for Unit 2. No similar system drawing was referenced for Unit 3. It appears that the referenced drawing under Unit 2 is actually applicable to Unit 3, and the correct drawing for Unit 2 should be LRA-208798. Please confirm the correctness of the referenced drawings, and if required, revise this section accordingly.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI (renumbered as RAI 2.3A.2.5-1).
Memo to Entergy Nuclear Operations, Inc. from K. Green dated November 21, 2007 DISTRIBUTION:
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON NOVEMBER 1, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION HARD COPY:
DLR RF E-MAIL:
PUBLIC SSmith (srs3)
SDuraiswamy RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDciCvib RidsNrrDciCpnb RidsNrrDraAfpb RidsNrrDeEmcb RidsNrrDeEeeb RidsNrrDssSrxb RidsNrrDssSbpb RidsNrrDssScvb RidsOgcMailCenter BPham KGreen JCaverly RFranovich MKowal JBoska ECobey, RI RConte, RI MCox, RI DJackson, RI BWittick, RI NSheehan, RI OPA DScrenci, RI OPA SBurnell, OPA DMcIntyre, OPA RShane, OCA TMensah, OEDO
Indian Point Nuclear Generating Units 2 and 3 cc:
Mr. Michael R. Kansler President & CEO / CNO Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. John T. Herron Senior Vice President Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Sr. Vice President Engineering & Technical Services Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. Fred R. Dacimo Site Vice President Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Mr. Anthony Vitale - Acting General Manager, Plant Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway P.O. Box 249 Buchanan, NY 10511-0249 Mr. Oscar Limpias Vice President Engineering Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. Joseph P. DeRoy Vice President, Operations Support Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. John A. Ventosa GM, Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. John F. McCann Director, Nuclear Safety & Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Ms. Charlene D. Faison Manager, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Ernest J. Harkness Director, Oversight Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. Patric W. Conroy Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Mr. T.R. Jones - Acting Manager, Licensing Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanana, NY 10511-0249 Mr. William C. Dennis Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
Indian Point Nuclear Generating Units 2 and 3 cc:
Mr. Paul D. Tonko President and CEO New York State Energy Research and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. John P. Spath New York State Energy, Research and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza Albany, NY 12223-1350 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspectors Office Indian Point 2 U.S. Nuclear Regulatory Commission P.O. Box 59 Buchanan, NY 10511 Senior Resident Inspectors Office Indian Point 3 U.S. Nuclear Regulatory Commission P.O. Box 59 Buchanan, NY 10511 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511 Mr. Raymond L. Albanese Four County Coordinator 200 Bradhurst Avenue Unit 4 Westchester County Hawthorne, NY 10532 Mr. William DiProfio PWR SRC Consultant 48 Bear Hill Road Newton, NH 03858 Mr. Garry Randolph PWR SRC Consultant 1750 Ben Franklin Drive, 7E Sarasota, FL 34236 Mr. William T. Russell PWR SRC Consultant 400 Plantation Lane Stevensville, MD 21666-3232 Mr. Jim Riccio Greenpeace 702 H Street, NW Suite 300 Washington, DC 20001 Mr. Phillip Musegaas Riverkeeper, Inc.
828 South Broadway Tarrytown, NY 10591 Mr. Mark Jacobs IPSEC 46 Highland Drive Garrison, NY 10524
Indian Point Nuclear Generating Units 2 and 3 cc:
Mr. R. M. Waters Technical Specialist Licensing 450 Broadway P.O. Box 0249 Buchanan, NY 10511-0249 Mr. Sherwood Martinelli Vice President FUSE USA 351 Dyckman Peekskill, NY 10566 Ms. Susan Shapiro, Esq.
President FUSE USA 21 Perlman Drive Spring Valley, NY 10977 John Sipos Assistant Attorney General New York State Department of Law Environmental Protection Bureau The Capitol Albany, NY 12224