ML042570040
| ML042570040 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/10/2004 |
| From: | Morgan M NRC/NRR/DRIP/RLEP |
| To: | Koehl D Nuclear Management Co |
| Morgan M, NRR/NRC/DRIP/RLEP, 415-2232 | |
| References | |
| TAC MC2099, TAC MC2100 | |
| Download: ML042570040 (8) | |
Text
September 10, 2004 Mr. Dennis L. Koehl Site Vice President Nuclear Management Company, LLC 6610 Nuclear Road Point Beach Nuclear Plant Two Rivers, WI 54241
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. MC2099 AND MC2100)
Dear Mr. Koehl:
By letter dated February 25, 2004, Nuclear Management Company, LLC (NMC or the applicant) submitted an application pursuant to 10 CFR Part 54, to renew the operating licenses for Point Beach Nuclear Plant, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC). The NRC staff is reviewing the information contained in the license renewal application (LRA) and has identified, in the enclosure, areas where additional information is needed to complete the review. Specifically, the enclosed requests for additional information (RAIs) are from Section 2.3 Auxiliary Systems, 2.4.11 Fire Barrier Commodity Group and 3.3.2.1 Fire Protection.
These RAIs, in a draft format, have been provided to Mr. Jim Knorr of your staff on August 10, 2004. The NRC staff has discussed draft versions of these RAIs, via a telephone conference call, to provide clarifications to the NMC staff on August 19, 2004. Your responses to these RAIs are requested within 30 days from the date of this letter. Mr. Knorr has agreed to this request. If needed, the NRC staff is willing to meet or discuss with NMC again prior to the submittal of the applicants responses to provide clarifications to the staffs RAIs.
If you have any questions, please contact me at 301-415-2232 or e-mail mjm2@nrc.gov.
Sincerely,
/RA/ Samson Lee for 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
Enclosure:
As stated cc w/encl: See next page
September 10, 2004 Mr. Dennis L. Koehl Site Vice President Nuclear Management Company, LLC 6610 Nuclear Road Point Beach Nuclear Plant Two Rivers, WI 54241
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. MC2099 AND MC2100)
Dear Mr. Koehl:
By letter dated February 25, 2004, Nuclear Management Company, LLC (NMC or the applicant) submitted an application pursuant to 10 CFR Part 54, to renew the operating licenses for Point Beach Nuclear Plant, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC). The NRC staff is reviewing the information contained in the license renewal application (LRA) and has identified, in the enclosure, areas where additional information is needed to complete the review. Specifically, the enclosed requests for additional information (RAIs) are from Section 2.3 Auxiliary Systems, 2.4.11 Fire Barrier Commodity Group and 3.3.2.1 Fire Protection.
These RAIs, in a draft format, have been provided to Mr. Jim Knorr of your staff on August 10, 2004. The NRC staff has discussed draft versions of these RAIs, via a telephone conference call, to provide clarifications to the NMC staff on August 19, 2004. Your responses to these RAIs are requested within 30 days from the date of this letter. Mr. Knorr has agreed to this request. If needed, the NRC staff is willing to meet or discuss with NMC again prior to the submittal of the applicants responses to provide clarifications to the staffs RAIs.
If you have any questions, please contact me at 301-415-2232 or e-mail mjm2@nrc.gov.
Sincerely,
/RA/ Samson Lee for 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
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION: See next page ADAMS Accession no.: ML042570040 Document Name: C:\\ORPCheckout\\FileNET\\ML042570040.wpd OFFICE PM:RLEP SE:RLEP LA:RLEP SC:RLEP NAME MMorgan (SLee for)
MHeath MJenkins SLee DATE 9/10/04 9/10/04 9/10/04 9/10/04 OFFICIAL RECORD COPY
DISTRIBUTION: Dated: September 10, 2004 Accession No.: ML042570040 HARD COPY RLEP RF M. Morgan (PM)
M. Heath E-MAIL:
RidsNrrDrip RidsNrrDe G. Bagchi K. Manoly W. Bateman J. Calvo R. Jenkins P. Shemanski J. Fair RidsNrrDssa RidsNrrDipm 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 L. Kozak, RIII J. Strasma, RIII A. Vegel, RIII H. Chernoff W. Ruland C. Marco L. Raghavan T. Mensah OPA
Enclosure REQUEST FOR ADDITIONAL INFORMATION POINT BEACH NUCLEAR PLANT, UNITS 1 & 2 LICENSE RENEWAL APPLICATION 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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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).
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.
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.
Point Beach Nuclear Plant, Units 1 and 2 cc:
Jonathan Rogoff, Esq.
Vice President, Counsel & Secretary Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Mr. Frederick D. Kuester President and Chief Executive Officer We Generation 231 West Michigan Street Milwaukee, WI 53201 James Connolly Manager, Regulatory Affairs Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241 Mr. Ken Duveneck Town Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, WI 54228 Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Resident Inspectors Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, WI 54241 Roger A. Newton 3623 Nagawicka Shores Drive Hartland, WI 53029 Mr. Jeffrey Kitsembel Electric Division Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854 David Weaver Nuclear Asset Manager Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, WI 53201 John Paul Cowan Executive Vice President & Chief Nuclear Officer Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Douglas E. Cooper Senior Vice President - Group Operations Palisades Nuclear Plant Nuclear Management Company, LLC 27780 Blue Star Memorial Highway Covert, MI 49043 Fred Emerson Nuclear Energy Institute 1776 I Street, NW., Suite 400 Washington, DC 20006-3708 Dennis L. Koehl Site Vice President Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241 James E. Knorr License Renewal Project Nuclear Management Company, LLC 6610 Nuclear Road Point Beach Nuclear Plant Two Rivers, WI 54241