ML020600134

Request for Additional Information for the Review of the Peach Bottom Atomic Power Station, Units 2 and 3

ML020600134
Person / Time
Site:	Peach Bottom
Issue date:	03/01/2002
From:	Anand R Division of Regulatory Improvement Programs
To:	Gallagher M Exelon Generation Co
Anand R, NRR/DRIP, 415-1146
References
Download: ML020600134 (7)

Text

Mr. Michael P. Gallagher Director-Licensing Exelon Corporation 200 Exelon Way Kennett Square, PA 19348

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3

Dear Mr. Gallagher:

By letter dated July 2, 2001, Exelon Generation Company, LLC (Exelon), submitted for Nuclear Regulatory Commission (NRC) review an application, pursuant to 10 CFR Part 54, to renew the operating licenses for the Peach Bottom Atomic Power Station, Units 2 and 3. The NRC staff is reviewing the information contained in this license renewal application and has identified, in the enclosure, areas where additional information is needed to complete its review. Specifically, the enclosed request for additional information (RAI) is from Section 3.5 Aging Management of Containment, Structures, and Component Supports.

Please provide a schedule by letter, or electronic mail for the submittal of your response within 30 days of the receipt of this letter. Additionally, the staff would be willing to meet with Exelon prior to the submittal of the response to provide clarification of the staffs request for additional information.

Sincerely, Raj K. Anand, Project Manager License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278

Enclosure:

As stated cc w/encl: See next page

Mr. Michael P. Gallagher Director-Licensing Exelon Corporation 200 Exelon Way Kennett Square, PA 19348

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3

Dear Mr. Gallagher:

By letter dated July 2, 2001, Exelon Generation Company, LLC (Exelon), submitted for Nuclear Regulatory Commission (NRC) review an application, pursuant to 10 CFR Part 54, to renew the operating licenses for the Peach Bottom Atomic Power Station, Units 2 and 3. The NRC staff is reviewing the information contained in this license renewal application and has identified, in the enclosure, areas where additional information is needed to complete its review. Specifically, the enclosed request for additional information (RAI) is from Section 3.5 Aging Management of Containment, Structures, and Component Supports.

Please provide a schedule by letter, or electronic mail for the submittal of your response within 30 days of the receipt of this letter. Additionally, the staff would be willing to meet with Exelon prior to the submittal of the response to provide clarification of the staffs request for additional information.

Sincerely, Raj K. Anand, Project Manager License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278

Enclosure:

As stated cc w/encl: See next page DISTRIBUTION: See next page Document Name:C:\MYFILES\Copies\Final RAI Sec 3_5.wpd OFFICE PM:RLSB LA SC: DE SC:RLEP PD:RLEP NAME RKAnand EGHylton K. Manoly/C. Munson PTKuo CIGrimes DATE 01/ /02 01/ /02 01/ /02 01/ /02 01/ /02 OFFICIAL RECORD COPY

DISTRIBUTION:

HARD COPY RLSB RF E. Hylton E-MAIL:

PUBLIC J. Johnson W. Borchardt D. Matthews C. Carpenter C. Grimes B. Zalcman J. Strosnider (RidsNrrDe)

E. Imbro G. Bagchi K. Manoly C. Munson B. Elliott W. Bateman J. Calvo C. Holden P. Shemanski S. Rosenberg G. Holahan B. Boger D. Thatcher G. Galletti B. Thomas J. Moore R. Weisman M. Mayfield A. Murphy W. McDowell S. Droggitis N. Dudley RLEP Staff

Division of Regulatory Improvement Programs COVER PAGE DATE: January 28, 2002

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 ORIGINATOR: R. Anand SECRETARY: S. Chey

!!!DRIP ROUTING LIST!!!

NAME DATE

1. R. Anand / /02

2. E. Hylton / /02

3. K. Manoly/ C. Munson / /02

4. P. T. Kuo / /02

5. C. Grimes / /02 DOCUMENT NAME: C:\MYFILES\Copies\Final RAI Sec 3_5.wpd ADAMS ACCESSION NUMBER: ML DATE ENTERED: / /01 FORM 665 ATTACHED and filled out: YES NO COMMITMENT FORM ATTACHED: YES NO

Peach Bottom Atomic Power Station, Units 2 and 3 cc:

Chief-Division of Nuclear Safety Mr. Edward Cullen PA Dept. of Environmental Protection Vice President & General Counsel P.O. Box 8469 Exelon Generation Company, LLC Harrisburg, PA 17105-8469 300 Exelon Way Kennett Square, PA 19348 Board of Supervisors Peach Bottom Township Mr. J. Doering R. D. #1 Site Vice President Delta, PA 17314 Peach Bottom Atomic Power Station 1848 Lay Road Public Service Commission of Maryland Delta, PA 17314 Engineering Division 6 St. Paul Center Mr. G. Johnston Baltimore, MD 21202-6806 Plant Manager Peach Bottom Atomic Power Station Mr. Richard McLean 1848 Lay Road Power Plant and Environmental Review Division Delta, PA 17314 Department of Natural Resources B-3, Tawes State Office Building Mr. A. Winter Annapolis, MD 21401 Regulatory Assurance Manager Peach Bottom Atomic Power Station Dr. Judith Johnsrud 1848 Lay Road National Energy Committee, Sierra Club Delta, PA 17314 433 Orlando Avenue State College, PA 16803 Resident Inspector U.S. Nuclear Regulatory Commission Manager-Financial Control & Co-Owner Affairs Peach Bottom Atomic Power Station Public Service Electric and Gas Company P.O. Box 399 P.O. Box 236 Delta, PA 17314 Hancocks Bridge, NJ 08038-0236 Regional Administrator, Region I Mr. Frederick W. Polaski U.S. Nuclear Regulatory Commission Manager License Renewal 475 Allendale Road Exelon Corporation King of Prussia, PA 19406 200 Exelon Way Kennett Square, PA 19348 Mr. Roland Fletcher Department of Environment Radiological Health Program 2400 Broening Highway Baltimore, MD 21224 Correspondence Control Desk Exelon Generation Company, LLC 200 Exelon Way, KSA 1-N-1 Kennett Square, PA 19348

Mr. Jeffrey A. Benjamin Vice President-Licensing Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Mr. Charles Pardee Senior Vice President Mid-Atlantic Regional Operating Group Exelon Generation Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348 Mr. John Skolds Chief Operating Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Mr. William Bohlke Senior Vice President, Nuclear Services Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Mr. James Meister Senior Vice President, Operations Support Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Mr. Alan Nelson Nuclear Energy Institute 1776 I Street, Suite 400 Washington, DC 20006

REQUEST FOR ADDITIONAL INFORMATION PEACH BOTTOM UNITS 2 AND 3 3.5 AGING MANAGEMENT OF CONTAINMENT, STRUCTURES, AND COMPONENT SUPPORTS RAI 3.5-1 Considering the vulnerability of concrete components, the staff has required previous license renewal applicants to implement an aging management program to manage the aging of concrete components. The staff position is that cracking, loss of material, and change in material properties are plausible and applicable aging effects for concrete components inside containment as well as for other structures outside containment. For inaccessible concrete components the staff does not require aging management if the applicant is able to show that the soil/water environment is nonaggressive; however, for all other concrete components inspection through an aging management program is required. Provide justification for concluding that there are no applicable aging effects for each of the concrete components, including concrete block walls, listed in Section 3.5 of the LRA.

RAI 3.5-2 Considering the vulnerability of steel components, the staff has required all previous license renewal applicants to implement an aging management program to manage the aging of steel components. The staff position is that loss of material is a plausible and applicable aging effect for steel components inside containment as well as for other structures outside containment. For steel imbedded in concrete in inaccessible areas, the staff does not require aging management if the applicant is able to show that the soil/water environment is nonaggressive. Provide justification for concluding that there are no applicable aging effects for each of the following steel components:

1. all carbon steel components inside containment (i.e., structural supports, pipe whip restraints, missile barriers, and radiation shields)

2. all carbon steel components in outdoor, sheltered, buried, and water environments outside containment:

a. reactor building (Table 3.5-2)

b. radwaste building and reactor auxiliary bay (Table 3.5.3)

c. turbine building and main control room complex (Table 3.5.4)

d. emergency cooling tower and reservoir (Table 3.5.5)

e. station blackout structure and foundation (Table 3.5.6)

f. yard structures (Table 3.5.7)

g. nitrogen storage building (Table 3.5.9)

h. diesel generator building (Table 3.5.10)

i. circulating water pump structure (Table 3.5.11)

j. recombiner building (Table 3.5.12)

k. component supports (Table 3.5.13)

l. hazard barriers and elastomers (Table 3.5.14)

m. miscellaneous steel (Table 3.5.15)

n. electrical and instrumentation enclosures and raceways (Table 3.5.16)

RAI 3.5-3 No aging effects are identified in Table 3.5.1- 3.5.14 in the LRA for the components listed below:

1. Bronze/graphite pressure suppression chamber lubrite plates (Table 3.5-1)

2. Cast iron sluice gates in raw water (Table 3.5-11)

3. Grout (Table 3.5-13)

4. Bronze/graphite lubrite plates (Table 3.5-13)

5. Neoprene Reactor Building blowout panel seals (Table 3.5-14)

6. Silicone Reactor Building metal siding gap seals (Table 3.5-14)

Lubrite plates are susceptible to loss of mechanical function, cast iron sluice gates in raw water are susceptible to loss of material, grout is susceptible to cracking, and neoprene and silicone seals are susceptible to change in material properties and cracking. Provide justification for concluding that there are no aging effects for each of these components.

3.5.1 Containment Structure RAI 3.5.1-1 The environment inside containment may accelerate the aging (i.e., cracking loss of material, change in material properties) of the structural steel and concrete components listed in Table 3.5-1 of the LRA. Please provide information regarding the operating temperature (range),

humidity, cumulative radiation (neutron, gamma) and medium (nitrogen, water, etc) for all the components in Table 3.5-1.

RAI 3.5.1-2 The reactor pedestal, foundation, and floor slab support the reactor vessel, interior floors, equipment, and piping in the drywell. Since these concrete components are also subjected to the harsh environment of containment (i.e., high temperatures and radiation), the staff considers cracking and possibly change in material properties to be plausible and applicable aging effects.

Please provide justification as to how their intended functions will be maintained without some type of aging management program during the period of extended operation.

RAI 3.5.1-3 The sacrificial shield wall performs the function of providing shielding as well as support for earthquake ties, which are required to stabilize the drywell during a postulated earthquake. The shield wall is subjected to varying temperatures (expansion and contraction), vibratory loads during SRV discharges (steam environment), and significant radiation. As such, the staff considers cracking, loss of material, and possibly change in material properties to be plausible and applicable aging effects for the sacrificial shield wall. Please provide justification as to how their intended functions will be maintained without some type of aging management program during the period of extended operation.

RAI 3.5.1-4 The columns, saddle supports, and seismic restraints associated with the pressure suppression chamber are affected by the expansion and contraction of the major diameter of the torus induced by SRV discharges and temperature transients. In one case, the staff has seen pullout of the anchor-bolts of the column supports due to such movements. The staff considers loss of material for the carbon steel components of the suppression chamber and loss of mechanical function of their associated lubrite plates to be plausible and applicable aging effects.

Please provide justification as to how their intended functions will be maintained without some type of aging management program during the period of extended operation.