ML041900370

Additional Information in Support of Applications for Renewed Operating Licenses

ML041900370
Person / Time
Site:	Millstone
Issue date:	07/07/2004
From:	Grecheck E Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
04-327
Download: ML041900370 (17)

Text

Dominion Nuclear Connecticut, Inc.

hl ill\ioiic lowtx Station Ropc Fcriv R d K~ircrtord,<T06385 J u l y 7, 2004 U.S. Nuclear Regulatory Commission Serial No.: 04-327 Attention: Document Control Desk LWELA RO Washington, D.C. 20555 Docket Nos.: 50-336 50-423 License Nos.: DPR-65 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC. (DNC)

MILLSTONE POWER STATION UNITS 2 AND 3 ADDITIONAL INFORMATION IN SUPPORT OF APPLICATIONS FOR RENEWED OPERATING LICENSES By letter dated January 20, 2004, DNC submitted the applications for renewed operating licenses (LRAs) for Millstone Power Station, Units 2 and 3. Based on questions from various audits and internal reviews, additional information in support of the Millstone Power Station, Units 2 and 3 LRAs is being submitted as Attachment 1.

Should you have any questions regarding this submittal, please contact Mr. William D.

Corbin, Director, Nuclear Projects, Dominion Resources Services, Inc., 5000 Dominion Blvd., Glen Allen, VA, 23060, (804) 273-2365.

Very truly yours, E. S. Grecheck Vice President - Nuclear Support Services Attachments:

1. Additional Information in Support of Applications for Renewec Operating icenses Commitments made in this letter:

None.

Serial No.04-327 Docket Nos.: 50-336/423 Additional Information in Support of Applications for Renewed Operating Licenses Page 2 of 4 cc: U.S. Nuclear Regulatory Honorable Chris Dodd Commission US Senate Region I 100 Great Meadow Road 475 Allendale Road Wethersfield, CT 06109 King of Prussia, PA 19406-1415 Mr. Michael Doyle Mr. V. Nerses Governors Eastern Office Senior Project Manager 171 Salem Turnpike U.S. Nuclear Regulatory Norwich, CT 06360 Commission One White Flint North Mr. William Meinert 11555 Rockville Pike MMWEC Mail Stop 8C2 P.O. Box426 Rockville, MD 20852-2738 Ludlow, MA 01056-0426 Mr. S. M. Schneider Honorable Melodie Peters NRC Senior Resident Inspector CT State Senate Millstone Power Station 25 Osceola Trail Old Lyme, CT 06371 Honorable Wayne L. Fraser First Selectman Honorable Gary Orefice P.O. Box 519 CT House of Representatives Niantic, CT 06357-0519 47 Columbus Avenue Niantic, CT 06357 Mr. Stephen Page Central VT PSC Honorable Robert Simmons 77 Grove Street US Congress Rutland, VT 06701 2 Courthouse Square Norwich, CT 06360 Honorable Andrea Stillman CT House of Representatives Mr. Thomas Wagner 5 Coolidge Court Town of Waterford Waterford, CT 06385 Town Planner 15 Rope Ferry Road Mr. Denny Galloway Waterford, CT 06385 Supervising Radiation Control Physicist Dr. Edward L. Wilds State of Connecticut - DEP Director, Division of Radiation Division of Radiation State of Connecticut - DEP 79 Elm Street 79 Elm Street Hartford, CT 06106-5127 Hartford, CT 06106-5127

Serial No.04-327 Docket Nos.: 50-336/423 Additional Information in Support of Applications for Renewed Operating Licenses Page 3 of 4 Chairman Donald Downes Mr. Jay Levin DPUC 23 Worthington Road 10 Franklin Square New London, CT 06320 New Britain, CT 06051 Mr. Jim Butler Honorable Dennis L. Popp Executive Director - Council of Chairman - Council of Governments Governments 8 Connecticut Avenue Municipal Building Nowich, CT 06360 295 Meridian Street Groton, CT 06340 Mr. Bill Palomba Executive Director, DPUC Chief Murray J. Pendleton 10 Franklin Square Director of Emergency New Britain, CT 06051 Management 41 Avery Lane Honorable Wade Hyslop Waterford, CT 06385-2806 State Representative, 3gthDistrict 32 Belden Street Honorable Richard Blumenthal New London, CT 06320 Attorney General 55 Elm Street Honorable Terry Backer Hartford, CT 06106-1774 CT State Representative Legislative Office Building Mr. John Markowicz Room 3902 Co-Chairman - NEAC Hartford, CT 06106 9 Susan Terrace Waterford, CT 06385 Honorable Kevin DelGobbo CT State Representative Mr. Evan Wmlacott 83 Meadow Street Co-Chairman - NEAC Naugautuck, CT 06770 128 Terry's Plain Road Simsbury, CT 06070 Honorable Thomas Herlihy CT Senate Honorable M. Jodi Rell 12 Riverwalk Governor Simsbury, CT 06089 State Capitol Hartford, CT 06106 Honorable Cathy Cook CT Senate, 18'h District Mr. Mark Powers 43 Pequot Avenue 4 Round Rock Road Mystic, CT 06355 Niantic, CT 06357

Serial No.04-327 Docket Nos.: 50-336/423 Additional Information in Support of Applications for Renewed Operating Licenses Page 4 of 4 Mr. Edward Mann Honorable Paul Eccard Office of Senator Dodd First Selectman Putnam Park Town of Waterford 100 Great Meadow Road 15 Rope Ferry Road Wethersfield, CT 06109 Waterford, CT 06385 Chairperson Pam Katz Mr. Richard Brown CT Siting Council City Manager 10 Franklin Square New London City Hall New Britain, CT 06051 181 State Street New London, CT 06320 Mr. Ken Decko CBlA Honorable Gaylord Gaynor 350 Church Street Mayor, New London Hartford, CT 06103 New London City Hall 181 State Street New London, CT 06320

SN: 04-327 Docket Nos.: 50-336/423

Subject:

Additional Information in Support of Renewed Operating Licenses COMMONWEALTH OF VIRGINIA )

)

COUNTY OF HENRICO )

The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Eugene S. Grecheck, who is Vice President -

Nuclear Support Services, of Dominion Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me this 7th day of July, 2004.

My Commission Expires: March 31, 2008.

(SEAL)

Serial No.04-327 Docket Nos.: 50-336/423 Additional Information in Support of Applications for Renewed Operating Licenses Attachment 1 Additional Information in Support of Applications for Renewed Operatinq Licenses Millstone Power Station Units 2 and 3 Dominion Nuclear Connecticut, Inc.

Serial No.04-327 Docket Nos.: 50-336/423 Additional Information in Support of Applications for Renewed Operating Licenses Attachment 1/Page 1 of 11 Additional Information in Support of Applications for Renewed Operatinq Licenses Millstone Unit 2 0 On Unit 2 drawing 25203-LR26005, Sh.2, there are Main Steam System components inadvertently highlighted as Condensate System components. The drawing has been revised and the list of LR drawings provided in Unit 2 Section 2.3.4.1 (page 2-160) should include drawing 25203-LR26005, Sh.2. There are no component type changes resulting from this change.

0 The aging effect of Buildup of Deposits does not apply for the copper alloy Pipe component type in Unit 2 Table 3.3.2-3 (page 3-206) since this piping is unlined.

0 The atmosphere/weather environment and associated information (i.e., Aging Effects Requiring Management, Aging Management Programs, etc,) for the aluminum Electrical Conduit, Cable Trays structural members was inadvertently included in Unit 2 Table 3.5.2-25 (page 3-532). It was determined that Unit 2 does not have these structural members constructed of aluminum in an atmosphere/weather environment.

0 The smoke detectors in the Unit 2 Control Room Air Conditioning System duct penetrate the duct and perform a pressure boundary intended function. Therefore, these components are within the scope of license renewal. A component type, Smoke Detectors, was added to the screening results and an aging management review was performed. This change affects the list of component types subject to aging management review in the Unit 2 Table 2.3.3-19 (page 2-133) by adding the component type Smoke Detectors with a Pressure Boundary intended function.

The aging management review results listed in Unit 2 Table 3.3.2-19 (page 3-257) should read as follows:

These added components are shown on license renewal drawing 25203-LR26027, Sheet 3 at location B-11.

Serial No.04-327 Docket Nos.: 50-336/423 Additional Information in Support of Applications for Renewed Operating Licenses Attachment 1/Page 2 of 11 The containment particulate and gaseous radiation monitors and associated components in the Unit 2 Process and Area Radiation Monitoring System perform an intended function to actuate isolation of the containment purge flow in the event of a fuel handling accident in the containment. Therefore, these components are within the scope of license renewal. The component types Fan/Blower Housings, Filter Housings, and Radiation Detectors were added to the screening results and an aging management review was performed. This change affects the list of component types subject to aging management review in Unit 2 Table 2.3.3-27 (page 2-141) by adding the component types Radiation Detectors, Fan/Blower Housings, and Filter Housings with a Pressure Boundary intended function. The aging management review results listed in Unit 2 Table 3.3.2-27 (page 3-271) should read as follows:

Component Aging Effect Aging Mgmt NUREG-1801 Table 1 Notes Intended Material Environment Requiring Programs vol.

Type Function(s) Item Manaaement These added components are shown on license renewal drawing 25203-LR26028, Sheet 2 between locations J-6 to J-11 and G-6 to G-11.

Serial No.04-327 Docket Nos.: 50-336/423 Additional Information in Support of Applications for Renewed Operating Licenses Attachment 1/Page 3 of 11 The diesel generator starting air compressors and components in the Unit 2 Diesel Generator System are credited with replenishing starting air tanks during certain 10CFR50, Appendix R fire scenarios. Therefore, these components are within the scope of license renewal. The components include the air compressors along with the piping and components downstream of the starting air tanks. The component types After-filter Housings, Compressor Casings, Dryers, and Pre-filter Housings were added to the screening results and an aging management review was performed. Piping and valve components in the diesel generator starting air subsystem are evaluated within existing component types. This change affects the list of component types subject to aging management review in Unit 2 Table 2.3.3-34 (page 2-149) by adding the component types After-filter Housings Compressor Casings, Dryers, and Pre-filter Housings with a Pressure Boundary intended function. The aging management review results in Unit 2 Table 3.3.2-34 (pages 3-300, 3-301, and 3-306) should read as follows:

Component Type After-Filter Housings Compressor Casings (E) Air None None G Stainless Work Dryers PB Loss of Steel (I) Air Control Vll.F2.4-a 3.3.1-05 C,2 Material Process (E) Air None None G Pre-Filter Stainless Work PB Loss of Housings Steel (I) Air Control VlLF2.4-a 3.3.1-05 C,2 Material

, Process ,

These added components are shown on license renewal drawing 25203-LR26018, Sheet 5 and include all previously non-highlighted portions.

Serial No.04-327 Docket Nos.: 50-336/423 Additional Information in Support of Applications for Renewed Operating Licenses Attachment 1/Page 4 of 11 The Unit 1 Turbine Building flood wall provides flood protection for Unit 2 Turbine Building. Therefore, this structure is within the scope of license renewal. The structural members Flood Barrier Wall and Masonry Block Walls were added to the screening results for the Unit 1 Turbine Building and an aging management review was performed. This change affects the list of structural members subject to aging management review in Unit 2 Table 2.4.2-5 (page 2-226) by adding the structural members Flood Barrier Wall and Masonry Block Walls with Flood Barrier and Structural Support intended functions. The aging management review results in Unit 2 Table 3.5.2-6 (page 3-469) should read as follows:

Millstone Unit 3 The Boric Acid Batching Tank in the Unit 3 Chemical and Volume Control System could potentially effect safety related equipment per the criteria of 10 CFR 54.4(a)(2). Therefore, this component is within the scope of license renewal. The component type Boric Acid Batching Tank was added to the screening results and an aging management review was performed. This change affects Unit 3 Table 2.3.3-15 (page 2-146) by adding the component type Boric Acid Batching Tank with Pressure Boundary and Limited Structural Integrity intended functions. The aging management review results listed in Unit 3 Table 3.3.2-15 (page 3-257) should read as follows:

This added component is shown on license renewal drawing 25212-LR26904, Sheet 3 at location M-5.

Serial No.04-327 Docket Nos.: 50-336/423 Additional Information in Support of Applications for Renewed Operating Licenses Attachment 1/Page 5 of 11 On Unit 3 drawings 25212-LR26937, Sh. 2 and 25212-LR26953, Sh. 1 there are Hot Water Heating components inadvertently highlighted as Hot Water Pre-heating. The drawings have been revised and the list of LR drawings provided in Unit 3 Section 2.3.4.8 (page 2-194) should include drawings 25212-LR26937, Sh. 2 and 25212-LR26953, Sh. 1. There are no component type changes resulting from this change.

The list of drawings provided in Unit 3 Section 2.3.4.9 (page 2-195) should add drawing 25212-LR26948 Sh. 2 since Hot Water Pre-heating components are highlighted on this drawing.

In the 2nd paragraph of Unit 3 Section 2.3.4.9, the phrase and non-safety-related components that are used to mitigate the effects of a high-energy line break was inadvertently added to the first sentence.

In addition, the 3rd paragraph of Unit 3 Section 2.3.4.9 is more correctly stated with the following:

The evaluation boundary includes the non-safety-related components with a spatial orientation near safety-related SSCs that are located in the Auxiliary Building and Fuel Building, and valves that isolate non-safety-related components with a spatial orientation near safety-related SSCs in the Service BuiIding.I The aging effect of Buildup of Deposits does not apply to the copper alloy Pipe component type in the Unit 3 Table 3.3.2-1 (page 3-216) and Table 3.3.2-2 (page 3-218) since the piping is unlined.

The atmosphere/weather environment and associated information (i.e., Aging Effects Requiring Management, Aging Management Programs, etc,) for the aluminum Electrical Conduit, Cable Trays structural members was inadvertently included in Unit 3 Table 3.5.2-36 (page 3-643). It has been determined that Unit 3 does not have these structural members constructed of aluminum in an atmosphere/weather environment.

Serial No.04-327 Docket Nos.: 50-3361423 Additional Information in Support of Applications for Renewed Operating Licenses Attachment 1/Page 6 of 11 Two in-line flow gauges for the Unit 3 Fire Protection System have been identified as providing a system pressure boundary intended function. Therefore, these components are within the scope of license renewal. The component type Flow Indicators was added to the screening results and an aging management review has been performed. This change affects the list of components subject to aging management review in Unit 2 Table 2.3.3-32 (page 2-146) and Unit 3 Table 2.3.3-37 (page 2-170) by adding the component type Flow Indicators with a Pressure Boundary intended function. The aging management review results listed in Unit 2 Table 3.3.2-32 (page 3-289) and Unit 3 Table 3.3.2-37 (page 3-344) should read as follows:

These added components are shown on license renewal drawing 25212-LR26946, Sheet 2 at locations N-7,8.

Serial No.04-327 Docket Nos.: 50-336/423 Additional Information in Support of Applications for Renewed Operating Licenses Attachment 1/Page 7 of 11 The hydraulic subsystem components associated with the Unit 3 Feedwater System feedwater isolation valve (FWIV) actuators are required for FWIV closure in response to a feedwater isolation actuation signal. Therefore, these components are within the scope of license renewal. The component types Control Blocks, Hydraulic Reservoirs, and Nitrogen Accumulators were added to the screening results and an aging management review was performed. Tubing and valve components of the FWIV hydraulic subsystem are evaluated within existing component types but were not previously evaluated for an oil environment. The oil environment was added to the list of environments in Unit 3 Section 3.4.2.1.2 (page 3-402). This change affects the list of component types subject to aging management review in Unit 3 Table 2.3.4-2 (page 2-201) by adding the component types Control Blocks, Hydraulic Reservoirs, and Nitrogen Accumulators with a Pressure Boundary intended function. The aging management review results listed in Unit 3 Table 3.4.2-2 (pages 3-425 and 3-426) should read as follows:

I ComDonent I Intended I .. . . , I- . I AgingEffect

- .. I Tubing Stainless (Additions PB (I) Oil None None G Steel Only)

Valves (Additions Onlv) 1 PB 1 Stainless Steel I (I) Oil None None G These added components are shown on license renewal drawing 25212-LR26930, Sheets 3 and 4 at locations F-2,3 and F-7,8 (both sheets).

Serial No.04-327 Docket Nos.: 50-336/423 Additional Information in Support of Applications for Renewed Operating Licenses Attachment 1/Page 8 of 11 Components needed to support post-accident calibration of the hydrogen analyzers in the Unit 3 Post-Accident Sampling Systems are necessary to maintain post-accident operability. Therefore, these components are within the scope of license renewal. The component types Hydrogen Tanks and Restricting Orifices were added to the screening results and an aging management review was performed.

Tubing and valve components which are part of the hydrogen analyzers calibration subsystem are evaluated within existing component types. This change affects the list of component types subject to aging management review in Unit 3 Table 2.3.3-46 (page 2-182) by adding the component types Hydrogen Tanks and Restricting Orifices with Pressure Boundary and Restricts Flow intended functions. The aging management review results in Unit 3 Table 3.3.2-46 (pages 3-387 and 3-388) should read as follows:

These added components are shown on license renewal drawing 25212-LR26955, Sheet 1 at locations bounded by 1-5,6 through L-5,6 and 1-8 through L-8.

Serial No.04-327 Docket Nos.: 50-336/423 Additional Information in Support of Applications for Renewed Operating Licenses Attachment 1/Page 9 of 11 The auxiliary feedwater pump lubricating oil subsystem in the Unit 3 Auxiliary Feedwater System should be included within the scope of license renewal. The component types Flow Indicators, Lube Oil Filters, and Oil Reservoirs were added to the screening results and an aging management review was performed.

Piping and valves components of the auxiliary feedwater pump lubricating oil subsystem are evaluated within existing component types but were not previously evaluated in an oil environment. This change affects the list of component types subject to aging management review in Unit 3 Table 2.3.4-5 (page 2-204)by adding the component types Flow Indicators, Lube Oil Filters, and Oil Reservoirs with a Pressure Boundary intended function. The aging management review results in Unit 3 Table 3.4.2-5(pages 3-433,3-434,and 3-435)should read as follows:

Component Intended Type Function(s)

Flow PB Indicators Lube Oil PB Filters Process Oil PB Carbon (E) Air Loss of General VIII.H.1-b 3.4.1-05 A,2 Reservoirs Steel Material Condition Monitoring (I) Oil Loss of Work VIII.G.5-d 3.4.1-04 C,2 Material Control Process Pipe PB Carbon (I) Oil Loss of Work VIII.G.5-d 3.4.1-04 C,2 (Additions Steel Material Control Only) Process Valves PB Carbon (I) Oil Loss of Work VIII.G.5-d 3.4.1-04 C,2 (Additions Steel Material Control Only) Process These added components are shown on Millstone Unit 3 FSAR Figure 10.2-2 at locations A,B-4 through A,B-11 and D,E-9 through D,E-11.

Serial No.04-327 Docket Nos.: 50-336/423 Additional Information in Support of Applications for Renewed Operating Licenses Attachment 1/Page 10 of 11 DNC identified a publication error that resulted in missing text in a portion of Section 3.1 in the Unit 3 application. Specifically, some information is missing from various subsections of Section 3.1.2.2, Further Evaluation of Aging Management as Recommended by NUREG-1801. The corrections for the pertinent missing information are identified as follows:

Section 3.1.2.2.6: the second paragraph should state the following:

Millstone will continue to implement all relevant ASME Section XI inspection requirements associated with reactor vessel internals. In addition, Millstone will follow the industry efforts on reactor vessel internals regarding such issues as thermal or neutron irradiation embrittlement (loss of fracture toughness), void swelling (change in dimensions), stress corrosion cracking (PWSCC and IASCC), and loss of pre-load for baffle and former-assembly bolts and will implement the appropriate recommendations resulting from this guidance.

This commitment is identified in Appendix A, Table A6.0-1 License Renewal Commitments, Item 13.

Section 3.1.2.2.7.1 : the first sentence should state the following:

Pressurizer Sprav Head/Nozzle Assemblv The pressurizer spray head assembly/nozzle assembly is fabricated from cast austenitic stainless steel which is subject to cracking due to SCC.

Cracking of the pressurizer spray head assembly/nozzle assembly is managed with the Chemistry Control for Primary Systems Program.

Section 3.1.2.2.7.3: the first sentence should state the following:

The pressurizer does not use nickel-based alloys in the instrumentation penetrations and heater sheaths and sleeves. However, Alloy 82/182 weld metal is used in the pressurizer spray, relief, safety and surge nozzle safe end welds. Primary water stress corrosion cracking of these locations is managed with the Chemistry Control for Primary Systems Program and the lnservice Inspection Program: Systems, Components and Supports.

Serial No.04-327 Docket Nos.: 50-336/423 Additional Information in Support of Applications for Renewed Operating Licenses Attachment 1/Page 11 of 11 0 Section 3.1.2.2.8: the first sentence should state the following:

Aging effects of baffle/former bolts will be managed with the Chemistry Control for Primary Systems Program and the lnservice Inspection Program:

Reactor Vessel Internals.

Section 3.1.2.2.9: the first sentence should state the following:

Loss of pre-load of baffle/former bolts is managed with the lnservice Inspection Program: Reactor Vessel Internals.

Section 3.1.2.2.1 1: the first sentence should state the following:

Cracking and loss of material in the steam generator tubes and tube plugs are managed by the Chemistry Control for Primary Systems Program, the Chemistry Control for Secondary Systems Program, and the Steam Generator Structural Integrity program.

Section 3.1.2.2.12: the following should be added:

Tube support lattice bars are not used in the steam generators. Therefore, this item is not applicable.

Section 3.1.2.2.1 3: the following should be added:

The steam generator tube support plates are fabricated from stainless steel.

Therefore, this item is not applicable.