ML042990506
| ML042990506 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/21/2004 |
| From: | Morgan M NRC/NRR/DRIP/RLEP |
| To: | |
| Morgan M, NRR/DRIP/RLEP, 415-2232 | |
| References | |
| TAC MC2099, TAC MC2100 | |
| Download: ML042990506 (10) | |
Text
October 21, 2004 LICENSEE: Nuclear Management Company, LLC FACILITY: Point Beach Nuclear Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE HELD ON AUGUST 19, 2004, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND NUCLEAR MANAGEMENT COMPANY, LLC, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATIONS (TAC NOS. MC2099 AND MC2100)
The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of Nuclear Management Company, LLC (NMC) held a telephone conference (telecon) on August 19, 2004, to discuss and clarify the staffs draft requests for additional information (D-RAIs) concerning the Point Beach Nuclear Plant License Renewal Applications. The telecon was useful in clarifying the intent of the staffs D-RAIs. provides a list of the meeting participants. Enclosure 2 contains a listing of the D-RAIs discussed with the applicant, including a brief description on the status of these items.
The applicant has had an opportunity to review and comment on this summary.
/RA/
Michael J. Morgan, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos.: 50-266 and 50-301
Enclosures:
As stated cc w/encls: See next page
ML042990506 E:\Filenet\ML042990506.wpd OFFICE PM:RLEP GI:RLEP LA:RLEP SC:RLEP NAME MMorgan MHeath MJenkins SLee DATE 10/20/04 10/21/04 10/20/04 10/21/04 DISTRIBUTION: Summary of Telecon with NMC Dated: October 21, 2004 ADAMS Accession No: ML042990506 HARD COPY RLEP RF M. Morgan (PM)
E-MAIL:
RidsNrrDrip RidsNrrDe G. Bagchi K. Manoly W. Bateman J. Calvo R. Jenkins P. Shemanski J. Fair S. Black B. Boger D. Thatcher R. Pettis G. Galletti C. Li M. Itzkowitz (RidsOgcMailCenter)
R. Weisman M. Mayfield A. Murphy S. Smith (srs3)
S. Duraiswamy Y. L. (Renee) Li RLEP Staff W. Ruland D. Spaulding L. Raghavan A. Vegel, RIII T. Mensah OPA
LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE TO DISCUSS THE POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION August 19, 2004 Participants Affiliation Rajender Auluck U.S. Nuclear Regulatory Commission (NRC)
Naeem Iqbal NRC Maurice Heath NRC Jim E. Knorr Nuclear Management Company (NMC)
Todd Mielke NMC Enclosure 1
POINT BEACH NUCLEAR POWER PLANT, UNITS 1 AND 2 REVIEW OF LICENSE RENEWAL APPLICATION FOR DRAFT REQUESTS FOR ADDITIONAL INFORMATION (D-RAIs)
August 19, 2004 Section 2.3.3 Auxiliary Systems Section 2.3.3.6 Fire Protection System RAI 2.3.3.6-1 The NRCs Fire Protection Safety Evaluation Report dated August 2, 1979, Section 4.3.1, addresses 13 hose stations in various areas of the plant, which do not appear in the license renewal application (LRA) or fire protection boundary drawings. Verify whether these hose stations are in scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an aging management review (AMR) in accordance with 10 CFR 54.21(a)(1). If they are, they should be included in Tables 2.3.3-6 and 3.3.2-6. If they are excluded from the scope of license renewal and not subject to an AMR, provide justification for the exclusion.
Discussion: The applicant indicated that the question was clear. The D-RAIs will be sent as a formal RAI.
RAI 2.3.3.6-2 The NRCs Fire Protection Safety Evaluation Report dated August 2, 1979, Sections 4.3.1, and 4.5 addresses floor drains. In LRA fire protection boundary drawings LR-M-208 SH 1, floor drains at location D3 and LR-M-208 SH 15, floor drains at locations C6, C7, E6, E7, E8, F6, F8, and F9 are not highlighted as portions of the flow diagram within the scope of license renewal and subject to an AMR. Verify whether these floor drains are in scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a)(1).
If they are, they should be included in Tables 2.3.3-6 and 3.3.2-6. If they are excluded from the scope of license renewal and not subject to an AMR, provide justification for the exclusion.
Discussion: The applicant indicated that the question was clear. The D-RAIs will be sent as a formal RAI.
RAI 2.3.3.6-3 The NRCs Fire Protection Safety Evaluation Report dated August 2, 1979, Section 4.3.1, addresses the dry pipe automatic sprinkler systems for Warehouse and Compressor Building and deluge automatic sprinkler with fusible like actuation in Control Room Emergency Ventilation System Charcoal Filters, which do not appear in the LRA or fire protection boundary drawings. Verify whether these fire suppression systems and components are in scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a)(1). If they are, they should be included in Tables 2.3.3-6 and 3.3.2-6. If they are excluded from the scope of license renewal and not subject to an AMR, provide justification for the exclusion.
Enclosure 2
Discussion: The applicant indicated that the question was clear. The D-RAIs will be sent as a formal RAI.
RAI 2.3.3.6-4 The NRCs Fire Protection Safety Evaluation Report dated August 2, 1979, Section 4.3.1, addresses the foam extinguishing system for two above ground fuel oil storage tanks, which does not appear in the LRA or fire protection boundary drawings. Verify whether these this foam suppression system and components are in scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a)(1). If they are, they should be included in Tables 2.3.3-6 and 3.3.2-6. If they are excluded from the scope of license renewal and not subject to an AMR, provide justification for the exclusion.
Discussion: The applicant indicated that the question was clear. The D-RAIs will be sent as a formal RAI.
RAI 2.3.3.6-5 The NRCs Fire Protection Safety Evaluation Report dated August 2, 1979, Section 4.3.2, addresses the carbon dioxide (CO2) suppression system in the remote gas turbine building and the Halon 1301 suppression system in the record storage vault, which do not appear in the LRA or fire protection boundary drawings. Verify whether these gaseous fire suppression systems and components are in scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a)(1). If they are, they should be included in Tables 2.3.3-6 and 3.3.2-6. If they are excluded from the scope of license renewal and not subject to an AMR, provide justification for the exclusion.
Discussion: The applicant indicated that the question was clear. The D-RAIs will be sent as a formal RAI.
RAI 2.3.3.6-6 Point Beach Nuclear Power Plant (PBNP) Fire Protection Evaluation Report Revision 3, April 2004, Section 5.1.4, states that protection of exposed structural steel in other plant areas is provided by sprayed on fire proofing material. No reference is made to it in the LRA Section 2.3.3.6, Fire Protection Systems or Section 2.4.11, Fire Barrier Commodity Group.
This appears to be a PBNP license condition. Identify where this fire proofing material is addressed in the LRA scoping, screening and AMR sections.
Discussion: The applicant indicated that the question was clear. The D-RAIs will be sent as a formal RAI.
RAI 2.3.3.6-7 PBNP Fire Protection Evaluation Report Revision 3, April 2004, Section 5.1.9, addresses Units 1 and 2 fire suppression system for outdoor transformers. However, LRA drawing LR-M- 208 SH-9 depicts the fire suppression system for 1, 2-X04 Transformers. Clarify the above drawing includes fire suppression system for Units 1 and 2 outdoor transformers.
protected by this portion of the fire protection system shown on this drawing, due to their close proximity to each other.
Discussion: The applicant indicated that the question was clear. The D-RAIs will be sent as a formal RAI.
RAI 2.3.3.6-8 PBNP Fire Protection Evaluation Report Revision 3, April 2004, Section 5.5.1, addresses a fixed smoke and heat removal system for computer and instrument rack room, control room, and cable spreading, which does not appear in the LRA or fire protection boundary drawings.
Verify whether this smoke and heat removal system and its components are in scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a)(1). If they are, they should be included in Tables 2.3.3-6 and 3.3.2-6. If they are excluded from the scope of license renewal and not subject to an AMR, provide justification for the exclusion.
Discussion: The applicant indicated that the question was clear. The D-RAIs will be sent as a formal RAI.
RAI 2.3.3.6-9 PBNP Fire Protection Evaluation Report Revision 3, April 2004, Section 6.4.1, addresses the Halon 1301 suppression system for the plant batter rooms, which does not appear in the LRA or fire protection boundary drawings. Verify whether the Halon 1301 suppression system and its components are in scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a)(1). If they are, they should be included in Tables 2.3.3-6 and 3.3.2-6. If they are excluded from the scope of license renewal and not subject to an AMR, provide justification for the exclusion.
Discussion: The applicant indicated that the question was clear. The D-RAIs will be sent as a formal RAI.
RAI 2.3.3.6-10 PBNP Fire Protection Evaluation Report Revision 3, April 2004, Section 6.5.1, addresses the dry chemical suppression system for the plant turbine-generator bearings and the gas turbine- generator exhaust, which does not appear in the LRA or fire protection boundary drawings. Verify whether the dry chemical suppression system and its components are in scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a)(1). If they are, they should be included in Tables 2.3.3-6 and 3.3.2-6. If they are excluded from the scope of license renewal and not subject to an AMR, provide justification for the exclusion.
Discussion: The applicant indicated that the question was clear. The D-RAIs will be sent as a formal RAI.
RAI 2.3.3.6-11 PBNP Fire Protection Evaluation Report Revision 3, April 2004, Section 6.5.2, addresses fixed carbon dioxide hose reel station in the control room, which does not appear in the LRA or fire protection boundary drawings. Verify whether the carbon dioxide hose reel station and its components are in scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a)(1). If they are, they should be included in Tables 2.3.3-6 and 3.3.2-6. If they are excluded from the scope of license renewal and not subject to an AMR, provide justification for the exclusion.
Discussion: The applicant indicated that the question was clear. The D-RAIs will be sent as a formal RAI.
RAI 2.3.3.6-12 Electric, diesel, and jockey fire pumps are highlighted on LRA drawings LR-M-208 SH-1 within the scope of license renewal. However, the highlighting does not trace the outline of the fire pumps and associated strainers. Verify whether fire pump strainers are in scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a)(1). If they are, they should be included in Tables 2.3.3-6 and 3.3.2-6. If they are excluded from the scope of license renewal and not subject to an AMR, provide justification for the exclusion.
Discussion: The applicant indicated that the question was clear. The D-RAIs will be sent as a formal RAI.
RAI 2.3.3.6-13 LRA drawings LR-M-208 SH-10 through SH-14 shows fire protection system and does not indicate any reference to areas of protection provided and type of fire protection system (i.e., sprinkler system or other as applicable). Identify the areas served by the fire protection system(s).
Discussion: The applicant indicated that the question was clear. The D-RAIs will be sent as a formal RAI.
Section 2.4.11 Fire Barrier Commodity Group RAI 2.4.11-1 The NRCs Fire Protection Safety Evaluation Report dated August 2, 1979, Section 4.9.1, states that Cable tray penetration in existing walls, floors, and ceilings are sealed with various configurations utilizing Flamemastic 71A coating, Kaowool ceramic fiber blanket, and Marinite insulation board. No reference is made to Flamemastic 71A and Marinite insulation board in the LRA Section 2.4.11 Fire Barrier Commodity Group or in PBNP Fire Protection Evaluation Report Revision 3, April 2004, Section 5.1.2. This appears to be a PBNP license condition.
Identify where these coatings are addressed in the LRA scoping, screening and AMR sections.
Discussion: The applicant indicated that the question was clear. The D-RAIs will be sent as a formal RAI.
Section 3.3 Aging Management of Auxiliary Systems Section 3.3.2.1.6 Fire Protection System (Table 3.3.2-6)
RAI 3.3.2.1.6-1 LRA Table 3.3.2-6 refers to Notes J and 5 which describe the aging management program(s)
AMPs for certain fire protection component types as listed in the table. Provide justification for the conclusion specified in Note 5 that the AMPs referenced are appropriate for the aging effects identified and provides assurance that the aging effects are effectively managed through the period of extended operation.
Discussion: The applicant indicated that the question was clear. The D-RAIs will be sent as a formal RAI.
Point Beach Nuclear Plant, Units 1 and 2 cc:
Jonathan Rogoff, Esq. Mr. Jeffrey Kitsembel Vice President, Counsel & Secretary Electric Division Nuclear Management Company, LLC Public Service Commission of Wisconsin 700 First Street P.O. Box 7854 Hudson, WI 54016 Madison, WI 53707-7854 Mr. Frederick D. Kuester David Weaver President and Chief Executive Officer Nuclear Asset Manager We Generation Wisconsin Electric Power Company 231 West Michigan Street 231 West Michigan Street Milwaukee, WI 53201 Milwaukee, WI 53201 James Connolly John Paul Cowan Manager, Regulatory Affairs Executive Vice President & Chief Nuclear Point Beach Nuclear Plant Officer Nuclear Management Company, LLC Nuclear Management Company, LLC 6610 Nuclear Road 700 First Street Two Rivers, WI 54241 Hudson, WI 54016 Mr. Ken Duveneck Douglas E. Cooper Town Chairman Senior Vice President - Group Operations Town of Two Creeks Palisades Nuclear Plant 13017 State Highway 42 Nuclear Management Company, LLC Mishicot, WI 54228 27780 Blue Star Memorial Highway Covert, MI 49043 Chairman Public Service Commission Fred Emerson of Wisconsin Nuclear Energy Institute P.O. Box 7854 1776 I Street, NW., Suite 400 Madison, WI 53707-7854 Washington, DC 20006-3708 Regional Administrator, Region III Dennis L. Koehl U.S. Nuclear Regulatory Commission Site Vice President 801 Warrenville Road Point Beach Nuclear Plant Lisle, IL 60532-4351 Nuclear Management Company, LLC 6610 Nuclear Road Resident Inspector's Office Two Rivers, WI 54241 U.S. Nuclear Regulatory Commission 6612 Nuclear Road James E. Knorr Two Rivers, WI 54241 License Renewal Project Nuclear Management Company, LLC Roger A. Newton 6610 Nuclear Road 3623 Nagawicka Shores Drive Point Beach Nuclear Plant Hartland, WI 53029 Two Rivers, WI 54241