ML042150431

Request for Additional Information for the Review of the Point Beach Nuclear Plant, Units 1 and 2, License Renewal Application

ML042150431
Person / Time
Site:	Point Beach
Issue date:	07/30/2004
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: ML042150431 (7)

Text

July 30, 2004 Mr. D. 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 3.2 Engineered Safety Features and Section 3.4 Steam and Power Conversion System.

These RAIs, in a draft format, have been provided to Mr. Jim Knorr of your staff on June 28, 2004. The NRC staff has discussed draft versions of these RAIs, via a telephone conference call, to provide clarifications to the NMC staff on July 13, 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/enclosure: See next page

ML042150431 Document Name: C:\\ORPCheckout\\FileNET\\ML042150431.wpd OFFICE PM:RLEP SE:RLEP LA:RLEP SC:RLEP NAME MMorgan (SSLee for)

OYee MJenkins SLee DATE 7/13/04 7/30/04 7/28/04 7/30/04

DISTRIBUTION: Dated: July 30, 2004 Accession No.: ML042150431 HARD COPY RLEP RF M. Morgan (PM)

O. Yee 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 Section 3.2 Engineered Safety Features RAI 3.2-1 In LRA Tables 3.2.2-1, 3.2.2-2, and 3.2.2-3, stainless steel heat exchangers, with heat transfer as the intended function, are identified with only internal environments and associated aging effects. The external environment is listed as not applicable. The applicant is requested to explain why for these components the external environment and associated aging effects need not be identified. The applicant is also requested to address the similar question for the stainless steel heat exchangers in Tables 3.2.2-1 and 3.2.2-2, which have pressure boundary as their intended function.

RAI 3.2-2 In LRA Tables 3.2.2-1 and 3.2.2-2, carbon/low alloy steel tank components are identified with only external environments and the associated aging effects. The internal environment is listed as N/A. On the other hand, stainless steel tank components are identified with internal environments with the associated aging effects. The applicant is requested to explain the material construction of the tank, and the environments to which it is exposed, to support the information provided in the tables.

Section 3.4 Steam and Power Conversion System RAI 3.4-1 In LRA Table 3.4.2-3, stainless steel heat exchangers, with either heat transfer or pressure boundary as the intended function, are identified with only internal environments and associated aging effects. The external environment is listed as not applicable. The applicant is requested to explain why for these components the external environment and associated aging effects need not be identified.

RAI 3.4-2 In the first quarter of 2003, Point Beach Nuclear Plant entered the Multiple/Repetitive Degraded Cornerstone Column (Column IV) of the Action Matrix of NRC Inspection Manual Chapter 0305, Operating Reactor Assessment Program, as a result of a high significance (Red) inspection finding involving the potential for a common mode failure of the auxiliary feedwater system (AFW) following a loss of the instrument air system. A second Red inspection finding (Yellow for Unit 1 and Red for Unit 2) was subsequently identified which involved the potential common mode failure of the AFW pumps due to plugging of the recirculation line pressure reduction orifices. In view of the aforementioned inspection findings and the subsequent corrective actions for the two AFW issues, the applicant is requested to address the following questions in the context of the license renewal application:

(a)

Clarify whether the instrument air system and the recirculation line pressure reduction orifices are in scope for the LRA evaluation, and that appropriate AMPs have been identified to manage the components.

(b)

For aging management evaluation as summarized in LRA Table 3.4.2-3 for the auxiliary feedwater system, discuss any impact on the scoping of mechanical components in the auxiliary feedwater system, and the AMR performed for the affected components, as a result of the recent physical modifications made to resolve the auxiliary feedwater pump room Appendix R issues.

Point Beach Nuclear Plant, Units 1 and 2 cc:

Jonathan Rogoff, Esquire 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 James E. Knorr License Renewal Project Nuclear Management Company, LLC 6610 Nuclear Road Point Beach Nuclear Plant Two Rivers, WI 54241