ML052100060
| ML052100060 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 07/28/2005 |
| From: | Daniel Merzke NRC/NRR/DRIP/RLEP |
| To: | Nuclear Management Co |
| Merzke, D., NRR/DRIP/RLEP, 415-3777 | |
| References | |
| Download: ML052100060 (9) | |
Text
July 28, 2005 LICENSEE:
Nuclear Management Company, LLC FACILITY:
Monticello Nuclear Generating Plant
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE HELD ON JULY 14, 2005 BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION (NRC)
AND NUCLEAR MANAGEMENT COMPANY, LLC, (NMC) CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE MONTICELLO NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION The NRC staff and representatives of NMC, LLC held a telephone conference on July 14, 2005 to discuss and clarify the staffs draft request for additional information (D-RAI) concerning the Monticello Nuclear Generating Plant, license renewal application. The conference call was useful in clarifying the intent of the staffs D-RAI. provides a listing of the meeting participants. Enclosure 2 contains the D-RAI discussed with the applicant, including a brief description on the status of these items.
The applicant had an opportunity to comment on this summary.
/RA/ (S. Lee for)
Daniel J. Merzke, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No.: 50-263
Enclosures:
As stated cc w/encls: See next page
DOCUMENT NAME: E:\\Filenet\\ML052100060.wpd OFFICE PM:RLEP LA:RLEP SC:RLEP NAME DMerzke (S. Lee for)
MJenkins SLee DATE 07 /28/05 07/28/05 07/28/05
cc:
Jonathan Rogoff, Esquire Vice President, Counsel & Secretary Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 U.S. Nuclear Regulatory Commission Resident Inspector's Office 2807 W. County Road 75 Monticello, MN 55362 Manager, Regulatory Affairs Monticello Nuclear Generating Plant Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637 Robert Nelson, President Minnesota Environmental Control Citizens Association (MECCA) 1051 South McKnight Road St. Paul, MN 55119 Commissioner Minnesota Pollution Control Agency 520 Lafayette Road St. Paul, MN 55155-4194 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Commissioner Minnesota Department of Health 717 Delaware Street, S. E.
Minneapolis, MN 55440 Douglas M. Gruber, Auditor/Treasurer Wright County Government Center 10 NW Second Street Buffalo, MN 55313 Commissioner Minnesota Department of Commerce 85 7th Place East, Suite 500 St. Paul, MN 55101-2198 Manager - Environmental Protection Division Minnesota Attorney Generals Office 445 Minnesota St., Suite 900 St. Paul, MN 55101-2127 John Paul Cowan Executive Vice President & Chief Nuclear Officer Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Nuclear Asset Manager Xcel Energy, Inc.
414 Nicollet Mall, R.S. 8 Minneapolis, MN 55401 Mr. James Ross Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Patrick Burke License Renewal Project Manager Monticello Nuclear Generating Plant Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637 Mr. Douglas F. Johnson Director, Plant Life Cycle Issues Nuclear Management Company, LLC 700 First Street Hudson, WI 54016
DISTRIBUTION: Summary of Telecon Held on July 14, 2005 Concerning RAI for Monticello Nuclear Generating Plant License Renewal Applicatioin Dated on July 28, 2005 ADAMS Accession No.:
HARD COPY RLEP RF E-MAIL:
RidsNrrDrip RidsNrrDe G. Bagchi K. Manoly W. Bateman J. Calvo R. Jenkins J. Fair RidsNrrDssa RidsNrrDipm D. Thatcher R. Pettis G. Galletti C. Li K. Winsberg (RidsOgcMailCenter)
R. Weisman M. Mayfield A. Murphy S. Smith (srs3)
S. Duraiswamy Y. L. (Renee) Li RLEP Staff L. Raghavan M. Padovan A. Stone, RIII B. Burgess, RIII P. Lougheed, RIII R. Orlikowski, RIII T. Mensah OPA LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE TO DISCUSS THE MONTICELLO NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION JULY 14, 2005 Participants Affiliations Daniel Merzke U.S. Nuclear Regulatory Commission (NRC)
James Strnisha NRC George Georgiev NRC Jai Rajan NRC Richard McNally NRC Patrick Burke Nuclear Management Company, LLC (NMC)
Bill Roman NMC Bill OBrien NMC Jim Rootes NMC Joe Pairitz NMC Dave Musolf NMC Madelin OBrien NMC DRAFT REQUEST FOR ADDITIONAL INFORMATION (D-RAI)
MONTICELLO NUCLEAR GENERATING PLANT LICENSE RENEWAL APPLICATION July 14, 2005 The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of Nuclear Management Company, LLC (NMC) held a telephone conference call on July 14, 2005 to discuss and clarify the staffs draft requests for additional information (D-RAIs) concerning the Monticello Nuclear Generating Plant, license renewal application (LRA). The following D-RAIs were discussed during the telephone conference call.
D-RAI 3.3.2.3-1:
LRA Table 3.3.2-4 identifies stress cracking corrosion (SCC) as an aging effect requiring management for stainless steel piping and fittings in a primary containment air environment. To manage this aging effect, the applicant credits the System Condition Monitoring Program, LRA Section B2.1.32, which utilizes visual inspections of component external surfaces for detection of aging effects. The applicant is requested to provide operating experience or other bases used for determining that SCC is an aging effect in this environment. Also, since methods such as VT-1, liquid penetrant, or volumetric inspections are used to detect SCC, the applicant is requested to identify the methods and acceptance criteria used by the System Condition Monitoring Program to detect SCC for these components.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 3.3.2.3-2:
LRA Tables 3.3.2-6 and 3.3.2-8 identify heat transfer degradation due to fouling as an aging effect requiring management for copper heat exchangers (heat transfer and pressure boundary functions) in a lubricating oil environment. The applicant credits the One-Time Inspection Program to manage this aging effect. Previous staff positions stated the One-Time Inspection Program provides measures to verify the effectiveness of an aging management program and to confirm the absence of an aging effect. For fouling of heat exchangers in a lubricating oil environment, mitigation of the aging effect is dependent on a lubricating oil monitoring program to maintain the integrity of the oil. Therefore, an acceptable Aging Management Program should include a lubricating oil monitoring program to mitigate the aging effect and a one-time inspection to verify the effectiveness of the mitigation program. The applicant is requested to identify an aging management program to mitigate the effects of fouling in the heat exchangers during the period of extended operation and verify the effectiveness of that program with a one-time inspection.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 3.3.2.3-3:
Tables 3.3.2-3 and 3.3.2-16 identify no aging effects for rubber expansion joints in a raw water environment. Previously, the staff has identified hardening and loss of strength as aging effects for elastomer components in this environment and recommended the Open-Cycle Cooling Water Program to manage these aging effects. The applicant is requested to identify an aging management program to manage hardening and loss of strength for rubber expansion joints in a raw water environment, or provide the technical basis for why these aging effects are not applicable to MNGP.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 3.3.2.3-4:
Tables 3.3.2-3, 3.3.2-5, 3.3.2-6, 3.3.2-7 and 3.3.2-16 identify no aging effects for rubber expansion joints, piping and fittings, and elastomer ventilation seals in a plant indoor air environment. Previously, the staff has identified hardening and loss of strength as aging effects for rubber and elastomer components in this environment and recommended a plant-specific program to manage these aging effects. The plant-specific program should provide periodic inspections of the components to manage these aging effects. The applicant is requested to identify an Aging Management Program to manage hardening and loss of strength for these rubber and elastomer components located in a plant indoor air environment, or provide the technical basis for why these aging effects are not applicable to MNGP.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 3.3.2.3-5:
Tables 3.3.2-5 and 3.3.2-17 identify no aging effects for rubber accumulators, piping and fittings in a treated water environment. Previously, the staff has identified hardening and loss of strength as aging effects for rubber and elastomer components in this environment and recommended a plant specific program to manage these aging effects. The plant-specific program should provide periodic inspections of the components to manage these aging effects.
The applicant is requested to identify an aging management program to manage hardening and loss of strength for these rubber components located in a treated water environment, or provide the technical basis for why these aging effects are not applicable to MNGP.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 3.3.2.3-6:
Tables 3.3.2-6 and 3.3.2-7 identify no aging effects for rubber ventilation seals, piping and fittings in a gas and air internal environment. Previously, the staff has identified hardening and loss of strength as aging effects for rubber and elastomer components in this environment where the internal temperature exceeds 95°F and recommends a plant-specific program to manage these aging effects. The plant-specific program should provide periodic inspections of the components to manage these aging effects. The applicant is requested to identify an Aging Management Program to manage hardening and loss of strength for these rubber components located in a gas and air internal environment where the internal temperature exceeds 95°F.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 3.3.2.3-7:
Tables 3.3.2-6 and 3.3.2-9 identify no aging effects for stainless steel fasteners/bolting and copper alloy flame arresters in an environment exposed to weather. Previously, the staff has identified loss of material due to pitting and crevice corrosion as aging effects for stainless steel and copper alloy components in this environment and recommended a plant-specific program to manage these aging effects. The plant-specific program should provide inspections of the components to manage these aging effects. The applicant is requested to identify an aging management program to manage loss of material due to pitting and crevice corrosion for these stainless steel and copper alloy components located in an environment exposed to weather, or provide the technical basis for why these aging effects are not applicable to MNGP.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI B2.1.4-1:
Table item numbers 3.3.1-18, 3.3.1-24 and 3.4.1-08 in the LRA provide a general discussion of the Bolting Integrity Program as applied to the ESF, auxiliary and SPC systems. The discussion section for each system states that while loss of preload is not specifically identified as an aging effect in the respective AMR table, it is managed for carbon steel and stainless steel closure bolting used in pressure retaining joints by the Bolting Integrity Program through periodic inspections, material selection, thread lubrication control, assembly and torque requirements, and repair and replacement activities. Based on this discussion, the staff considers closure bolting in the ESF, auxiliary and SPC systems to be managed for loss of preload by the Bolting Integrity Program. The applicant is requested to discuss whether all closure bolting in the ESF, auxiliary and SPC systems is managed for loss of preload by the Bolting Integrity Program, although the AMR tables do not contain specific line items for this aging effect.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI B2.1.4-2:
The LRA states that the Primary Containment In-Service Inspection Program provides for visual examination of accessible surfaces of drywell, torus, etc. Recent experience with failed bolts on T-quencher supports at Hatch Nuclear Plant Unit 2 has shown that high strength bolts are susceptible to hydrogen induced cracking and may fail after 20 to 25 years of service. In order to assess the adequacy of Monticellos Bolting Integrity Program please provide the following information:
Has the applicant and/or his contractor reviewed the Hatch 2 bolt failure event for applicability to Monticello? If yes, what are the results from that review? Why does the applicant believe that this event cannot take place at Monticello? If no, when is the applicant planning to complete the review? Why does the applicant believe that this event is not applicable to its facility?
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI B2.1.4-3:
Does the Primary Containment In-Service Inspection Program include requirements for divers inspection of underwater bolting in the Torus? If not, why not?
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI B2.1.32-1:
The System Condition Monitoring Program in LRA Section B2.1.32, manages aging effects through visual inspection and monitoring of external surfaces for leakage and evidence of material degradation. The AMP does not address how inspection of accessible surfaces will provide reasonable assurance that inaccessible surfaces are managed. The applicant is requested to list any inaccessible surfaces of components (including lagged/insulated piping
<212°F) that will be managed by this program and discuss the bases for determining that the inaccessible surfaces will be adequately managed.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI B2.1.32-2:
The System Condition Monitoring Program is credited with managing the following aging effects located in various sections of the LRA:
a.
Change in material properties and cracking for neoprene ventilation seals in engineered safety features systems; b.
Stress cracking corrosion for stainless steel piping and fittings in auxiliary systems; c.
Crevice corrosion for steel and copper alloy components in the auxiliary systems; d.
Crevice corrosion for copper alloy components in the steam and power conversion systems; e.
Stress cracking corrosion and crevice corrosion for stainless steel spent fuel pool liner.
It is not apparent how these types of aging effects will be identified during a system walkdown visual inspection. The applicant is requested to discuss the inspection methods and techniques used to detect each of the above aging effects and the acceptance criteria for each aging effect.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.