ML072770583
| ML072770583 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/26/2005 |
| From: | Cowan P AmerGen Energy Co |
| To: | Document Control Desk, NRC/SECY |
| SECY RAS | |
| References | |
| 50-219-LR, AmerGen-Applicant 2, RAS 14202 | |
| Download: ML072770583 (14) | |
Text
A 5 N5~O APPLICANT'S EXH. 2 Amer0wen., ArnerGen Energy Company. LLC 200 Exelon Way Kennett Square. PA 19348 2130-05-20159 July 26, 2005 www.exeloncorp.com U.S. NUCLEAR REGULATORY COMMISSION In the Matte of -A IE P~4I QO1 Docket 0 Official Exhibit No.OFFERED e Intervenor_
NR St ff Other ENTIFIED on
.Aci Tae~n: E EJECTED WITHDRAWN RM~eOwk An Exelon Company 10 CFR 50 10 CFR 51 10 CFR 54 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219 DOCKETED USNRC October 1, 2007 (10:45am)OFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF
Subject:
Application for Renewed Operating License -Reformatted CD-ROM Letter from C. N. Swenson (AmerGen Energy Company, LLC) to U. S. NRC"Application for Renewed Operating License" dated July 22, 2005
References:
AmerGen Energy Company, LLC (AmerGen) submitted an application for the renewal of the operating license for the Oyster Creek Generating Station (OCGS) pursuant to U. S. Nuclear Regulatory Commission (NRC) regulations 10 CFR 50, 51 and 54 in the above referenced letter.For clarity, the enclosed CD-ROM is being provided in a revised electronic file format that is intended to resolve issues with image resolution and embedded fonts. It is solely an administrative reformatting.
Specifically, Enclosure 2 is a single compact disc (CD), formatted in a manner that is consistent with "Guidance for Electronic Submissions to the Commission", referenced in the Federal Register on October 10, 2003 (68 FR 58826). This CD contains files suitable for entry into the NRC's record retrieval system, ADAMS.It is not practicable to provide fully text searchable files for Appendices B, C, D and E of the Environmental Report since they contain copies of documents and graphics that must be scanned as image files. Thus, AmerGen also is providing a paper copy of the complete Oyster Creek Generating Station "'Application for Renewed Operating License" in Enclosure 3 (four volumes).Inasmuch as this submittal only involves administrative changes to the electronic formatting, the Application for Renewed Operating License submitted by letter dated July 22, 2005, remains operative.
If you have any questions, please contact Fred Polaski, Manager License Renewal, at 610-765-5935.'Iem p I ae e~~cy- ogec5 July 26, 2005 Page 2 Respectfully, Pamela B. owan Director -Licensing and Regulatory Affairs AmerGen Energy Company, LLC
Enclosures:
- 1. Affidavit 2. CD-ROM labeled "Oyster Creek Generating Station, License Renewal Application, July 2005, Reformatted CD-ROM'3. Oyster Creek Generating Station, License Renewal Application (four volume paper copy)cc: Regional Administrator, USNRC Region 1, without enclosures NRC Project Manager, NRR -License Renewa:, Safety, without enclosures NRC Project Manager, NRR -License Renewa,, Environmental, without enclosures USNRC Senior Resident Inspector, OCGS, without enclosures Bureau of Nuclear Engineering, New Jersey Department of Environmental Protection, without enclosures File No. 05040 STATE OF PENNSYLVANIA CHESTER COUNTY IN THE MATTER OF: AMERGEN ENERGY COMPANY (AmerGen), LLC Oyster Creek Generating Station))) Docket Number) 50-219
SUBJECT:
Application for Renewed Operating License -Reformatted CD-ROM AFFIDAVIT I affirm that the content of this transmittal is true and correct to the best of my knowledge, information, and belief.Pamela B. Cowan Director -Licensing and Regulatory Affairs AmerGen Energy Company, LLC Subscribed and sworn to before me, a Notary Public in and for the State above named, this .26 day of____ ____ ___ ____ __,2005~i Notary Public COMMONWEALTH OF PENNSYLVANIA INotarsea I Vr~aV. Galimore.
bkAayPitI~c IKenmt1Square Born. ChestervOuty y Convnise EBqres Oct 6.2007 Member. Pennsylvania Association Of Notarfes Enclosure 2 consists of one CD-ROM labeled "Oyster Creek Generating Station, License Renewal Application, July 2005, Reformatted CD-ROM" containing the following 3 files: 01-LRA.pdf; 5,025 KB; publicly available 02-ER(TOC-Chap9).pdf; 14,027 KB; publicly available 03-ER(Appendix A-F).pdf; 40,194 KB; publicly available LICENSE RENEWAL APPLICATION OYSTER CREEK GENERATING STATION DOCKET No. 50-219 Facility Operating License No. DPR-16 Section 2.0 Scoping and Screening Methodology and Results 2.4.1 Primary Containment System Purpose The Primary Containment Structure is comprised of the primary containment, containment penetrations, and internal structures.
The structure is enclosed by the Reactor Building, which provides secondary containment, structural support, shielding, shelter, and protection, to the containment and components housed within, against external design basis events.The primary containment is a General Electric Mark I design and consists of a drywell, a pressure suppression chamber, and a vent system connecting the drywell and the suppression chamber. It is designed, fabricated, inspected, and tested in accordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section VIII, and Nuclear Code Cases1270N-5, 1271N and 1272N-5. The containment is safety related, classified Seismic Class 1 structure.
The drywell is a steel pressure vessel, in the shape of an inverted light bulb, with a spherical lower section and a cylindrical upper section. The lower spherical section is embedded externally in the reinforced concrete foundation and covered internally by a fill slab at the bottom of the dryweli. The top portion of the drywell vessel consists of a steel head that is removed during refueling operations.
The head is bolted to the drywell flange and is sealed with a double seal arrangement.
Access into the drywell is through a personnel axrlociJequipment hatch, with two mechanically interlocked doors, and other access hatches.The drywell houses the reactor pressure vessel, the reactor coolant recirculation system, safety relief valves, electromatic relief valves (EMRVs), branch connections of the reactor primary system, containment drywell spray header, and internal structures discussed below.The drywell shell and the enclosing reactor building concrete are separated by an air gap to allow for differential thermal expansion between the shell and the concrete during any mode of plant operation.
The pressuresuppression chamber is a toroidal shaped, steel pressure vessel encircling the base of drywell. The suppression chamber, commonly called the torus, is partially filled with demineralized water and includes internal steel framing, and access hatches. The suppression chamber is mounted on support structures that transmit loads to the reactor building foundation.
Major components inside the suppression chamber include Emergency Core Cooling Systems (ECCS) suction strainers, which are connected to the ECCS suction header located outside the chamber, torus spray header, and Y-Quenchers.
The vent system consists of ten circular vent lines, which form a connection between the drywell and the pressure suppression chamber. The lines enter the suppression chamber through penetrations provided with expansion bellows and join into a common header contained within the air space of the suppression chamber. The header discharge is through 120 downcomer pipes, which terminate below the water level in the torus. The header and the downcomer pipes are supported from the suppression chamber shell.The primary containment is provided with a vacuum breaker system to equalize the pressure between the drywell and the suppression chamber, and between the suppression chamber and the reactor building.
The vacuum breaker system assures that the external design pressure limits of the two chambers are not exceeded.Oyster Creek Generating station Page 2.4-2 License Renewal Application Section 2.0 Scoping and Screening Methodology and Results The primary containment is penetrated at several locations by piping, instrument lines, ventilation ducts, and electric leads. The penetrations consist of sleeves welded to drywell vessel or suppression chamber and are of two general types. Those required to accommodate thermal movements; and those, which experience relatively little thermal stress. Penetrations required to accommodate thermal movements are provided with expansion bellows.Internal structures consist of a fill slab, reactor pedestal, biological shield wall and its lateral support, and structural steel. The fill slab is reinforced concrete placed in the bottom of the drywell to provide a working base for supporting the reactor pedestal and other structures and components inside the drywell.The reactor pedestal is a reinforced concrete cylinder with an outside diameter of 26 feet. The pedestal provides structural support to the reactor pressure vessel, the biological shield wall, and floor framing. The biological shield wall extends above the reactor pedestal and is a composite steel, concrete cylinder with an inside diameter of approximately 21 feet. The wall is framed with steel columns covered with steel plate on each face and filled partly with normal density concrete and partly with high-density concrete.
The top of the wall is capped with a steel plate and laterally braced to the drywell vessel.Structural steel includes floor framing steel for the platforms inside the drywell, and a catwAlk inside the suppression chamber. It also includes miscellaneous steel inside the containment such as grating, ladders, connection plates; electrical cable trays, and electrical conduits.The purpose of the primary containment is to accommodate, with a minimum of leakage, the pressures and temperatures resulting from the break of any enclosed process pipe; and thereby, to limit the release of radioactive fission products to values, which will insure offsite dose rates well below 10CFR100 guideline limits. It also provides a source of water for ECCS and for pressure suppression in the event of a loss-of-coolant accident.
The primary containment and internal structures also provide structural support to the reactor pressure vessel, the reactor coolant systems, and other safety and nonsafety related systems, structures, and components housed within. The biological shield wall provides the added function of radiation shielding to maintain drywell environment within equipment qualification parameters.
Included in the evaluation boundary of the Primary Containment are the drywell, drywell head, suppression chamber, vent lines, downcomers, drywell and suppression chamber penetrations, vent line bellows, drywell penetration bellows, personnel air lock/equipment and other hatches, pressure retaining bolting, thermowells, and internal structures listed above.Not included in the evaluation boundary of the Primary Containment are safety relief valves and EMRVs, EMRV discharge lines, Y-Quenchers, drywell and torus spray headers, vacuum breakers, ECCS suction strainers and header, downcomer bracing, suppression chamber (torus) supports, and other component supports.
These components are separately evaluated with their respective license renewal systems. That is, safety relief valves, EMRVs, EMRV discharge lines, and Y-Quenchers are evaluated with Main Steam System. Drywell and torus spray headers, and ECCS suction strainers and header are evaluated with the Containment Spray System. Vacuum breakers are evaluated with the Containment Vacuum Breakers System. Downcomer bracing, suppression chamber supports, and other component supports are evaluated with the Component Supports Commodity Group.Oyster Creek Generating Station Page 2.4-3 License Renewal Application Section 2.0 Scoping and Screening Methodology and Results For more detailed information, see UFSAR Sections 3.8 and 6.2 Reason for Scope Determination The Primary Containment meets the scoping requirements of 10 CFR 54.4(a)(1) because it is a safety-related structure which is relied upon to remain functional during and following design basis events. It meets 10 CFR 54.4(a)(2) because failure of nonsafety related portions of the structure could prevent satisfactory accomplishment of function(s) identified for 10 CFR 54.4(a)(1).
It also meets 10 CFR 54.4(a)(3) because it is relied upon in the safety analyses and plant evaluations to perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48), ATWS (10 CFR 50.62), and Environmental Qualification (10 CFR 50.49). The Primary Containment is not relied upon in the safety analyses and plant evaluations to perform a function that demonstrates compliance with Station Blackout (10 CFR 50.63).System Intended Functions 1. Controls the release of fission products to the secondary containment in the event of design basis loss-of-coolant accidents (LOCA) so that off site consequences are within acceptable limits. (10 CFR 54.4(a)(1))
- 2. Provides sufficient air and water volumes to absorb the energy released to the containment in the event of design basis event so that pressure is within acceptable limits. (10 C FR 54.4(a)(1))
- 3. Provides a source of water for core spray, containment spray, and conGensate transfer systems. (10 CFR 54.4(a)(1))
- 4. Provides physical support, shelter, and protection for safety related systems, structures, and components (SSCs). 10 CFR 54.4(a)(1)
- 5. Provides physical support, shelter, and protection for nonsafety related systems, structures, and components (SSCs) whose failure could prevent satisfactory accomplishment of function(s) identified for 10 CFR 54.4(a)(1).
- 6. Relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the commission's regulations for Anticipated Transients without Scram (10 CFR 50.62). 10 CFR 54.4(a)(3)
- 7. Relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the commission's regulations for Fire Protection (10 CFR 50.48). 10 CFR 54.4(a)(3)
- 8. Relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with the commission's regulations for Environmental Qualification (10 CFR 50.49).10 CFR 54.4(a)(3)
UFSAR References 3.8 6.2 License Renewal Boundary Drawings LR-JC-1 9702 Oyster Creek Generating Station License Renewal Application Page 2.4-4 Section 2.0 Scoping and Screening Methodology and Results Table 2.4.1 Primary Containment Components Subject to Aging Management Review Component Type Intended Functions Access Hatch Covers Pressure Boundary Beam Seats Structural Support Biological Shield Wall -Concrete Shielding Biological Shield Wall -Lateral Support Structural Support Biological Shield Wall -Liner Plate Structural Support Biological Shield Wall -Structural Steel Structural Support Cable Tray Structural Support Class MC Pressure Retaining Bolting Pressure Boundary Concrete embedment Structural Support Conduits Enclosure Protection Structural Support Downcomers Pressure Boundary Drywell Head Pressure Boundary Structural Support Drywell Penetration Be'iows Pressure Boundary Drywell Penetration Sleeves Pressure Boundary Structural Support Drywell Shell Pressure Boundary Structural Support Drywell Support Skirt Structural Support Liner (Sump) Leakage Boundary Locks, Hinges, and Closure Mechanisms Pressure Boundary Structural Support Miscellaneous Steel (catwalks, handrails, Structural Support ladders, platforms, grating, and associated supports)Panels and Enclosures Enclosure Protection Structural Support Penetration Closure Plates and Caps Pressure Boundary (spare penetrations)
Personnel Airlock/Equipment Hatch Pressure Boundary Reactor Pedestal Structural Support Reinforced Concrete Floor Slab (fill slab) Enclosure Protection Structural Support Seals, Gaskets, and 0-rings Pressure Boundary Shielding Blocks and Plates Shielding Structural Bolting Structural Support Structural Steel (radial beams, posts, Structural Support bracing, plate, connections, etc.)Suppression Chamber Penetrations Pressure Boundary Structural Support Suppression Chamber Ring Girders Structural Support SuDDression Chamber Shell Pressure Boundary Oyster creek Generating Station Page 2.4-5 License Renewal Application Section 2.0 Scoping and Screening Methodology and Results Suppression Chamber Shell Structural Support Suppression Chamber Shell Hoop Straps Structural Support Thermowells Pressure Boundary Vent Header Deflector HELB Shielding Vent Jet Deflectors HELB Shielding Vent line bellows Pressure Boundary Vent line, and Vent Header Pressure Boundary The aging management review results for these components are provided in Table 3.5.2.1.1 Primary Containment-Summary of Aging Management Evaluation Oyster Creek Generating Station Ucense Renewal Application Page 2.4-6 Section 3.0 Aging Management Review Results (.Table 3.0-2 -Oyster Creek External Service Environments Oyster Creek Description Equivalent NUREG-1801 Environment Environment Adverse localized Environment, which could exist in limited plant areas Adverse Localized Environment caused by heat, radiation, moisture or voltage in the Environment presence of oxygen. Used for electrical insulation only.Aggressive Environment 1 Ground water and raw water environments are Aggressive Environment considered aggressive if pH < 5.5, or chlorides
> 500 ppm, or sulfates > 1500 ppm.Boiler Treated Water 2 Demineralized water subject to chemistry controls Treated Water recommended by the boiler manufacturer.
Water controls are implemented through plant procedures.
Closed Cooling Water Treated water subject to water chemistry controls Closed cycle cooling recommended in EPRI TR-1 07396, *Closed Cooling water Water Chemistry Guidelines." Closed Cooling Water includes Reactor Building Closed Cooling Water (RBCCW), and Turbine Building Closed Cooling Water (TBCCW).Closed Cooling Water < Closed cooling water below the temperature threshold Closed cycle cooling 140OF 3 for SCC in austenitic stainless steel components.
water Concrete Embedded or Encased in concrete Concrete C'1 This environment is not an exact match of aggressive environment defined in NUREG-1801, Table IX.D However it is an exact match of the aggressive environment used in NUREG-1 801 AMR tables, for example line Item III.A3-4 (T-05).2 This environment is not an exact match of the environment defined in NUREG-1801 because water chemistry is controlled to different guidelines.
However for aging management review considerations it is considered equivalent.
3 This environment is not an exact match of environments defined in NUREG-1 801; however it is bounded by the listed equivalent NUREG-1801 environment Oyster Creek Generation Station License Renewal Application Page 3.0-11 Section 3.0 Aging Management Review Results Table 3.0-2 -Oyster Creek External Service Environments Q Oyster Creek Description Equivalent NUREG-1801 Environment Environment Containment Atmosphere This environment is inert with nitrogen to render the Air -Indoor atmosphere non-flammable by maintaining the oxygen content below 4% by volume. The average normal Uncontrolled temperature inside the drywell is 139 0 F, with a humidity range of 20-40%. The upper elevations (above elev. Air with Reactor Coolant 95') of the drywell could be exposed to higher Leakage temperatures, up to 256'F. For bolting this environment includes potential leakage of treated water, steam, or Airwith Steam or Water raw water. Leakage Dry Gas Nitrogen Gas Air, Dry Encased Applies to components encapsulated in steel, or Environment not in aluminum.
Encased components are inaccessible, and NUREG-1801 not exposed to air, water, or other environments.
Fuel Oil Diesel oil used for the combustion engines and heating Fuel Oil boilers.Indoor Air Air in a sheltered environment, other than containment Air -indoor atmosphere.
Air temperature range is 65°F -140OF and the humidity is 100% maximum. For bolting this Uncontrolled environment includes potential.leakage of treated water, steam, sodium pentaborate, or raw water. Air with Reactor Coolant Leakage Air with Steam or Water Leakage Lubricating Oil Low to medium viscosity hydrocarbons used for Lubricating Oil lubrication of rotating equipment.
Outdoor Air Outdoor air environment is subject to local weather Air -Outdoor conditions.
The mean temperature range is 23.7 0 F -84°F and the average annual precipitation is approximately 42 inches.Q Oyster Creek Generation Station License Renewal Application Page 3.0-12 Section 3.0 Aging Management Review Results./Table 3.0-2 -Oyster Creek External Service Environments Oyster Creek Description Equivalent NUREG-1801 Environment Environment Raw Water -Fresh Water Fresh raw water is drawn from either a deep well or Raw Water from the Fire Pond Dam. Water taken from the deep wells is processed in the pretreatment facility and used for domestic water or treated further and used as Demineralized water and for make up to the condensate storage and transfer system.Fresh water drawn from the Fire Pond Dam is untreated and is used for fire suppression and to the circulating water and service water pumps seals, and dilution pump oil coolers. Recent chemistry results show that the pH =4.8, chlorides
= 12 ppm, and sulfates = 6 ppm.Raw Water -Salt Water Raw salt water is drawn from Bamegat Bay, which receives salt water from the Atlantic Ocean and fresh water runoff from streams, which border it on the western shore, including Oyster Creek and Forked River. Recent tests of water samples taken at the Intake Structure and Canal showed that the pH = 7.9, Chlorides
=14659 ppm, and Sulfates 1419 ppm. The average monthly water temperature range is 37 0 F in the winter and 80 0 F in summer.Soil External environment for structures and components Soil buried in soil. Buried structures and components may be exposed to groundwater if they are located below the local ground water elevation.
Site groundwater has been tested and determined non-aggressive to concrete.Steam Steam that is subject to BWR water chemistry controls Steam Oyster Creek Generation Station License Renewal Application Page 3.0-13 Section 3.0 Aging Management Review Results (7 Table 3.0-2 -Oyster Creek External Service Environments Oyster Creek Description Equivalent NUREG-1801 Environment Environment Treated Water Treated water is demineralized water and is the base Treated water water for all clean systems. Depending on the system, this demineralized water may require additional processing.
Treated water can be deaerated, include corrosion inhibitors, biocides, or some combination of these treatments.
Treated water is subject to BWR water chemistry controls.
Treated water includes reactor grade water, spent fuel pool water, torus water, and demineralized water.Treated Water < 140°F 1 Treated Water below the temperature threshold for SCC Treated water in austenitic stainless steel components.
Treated Water > 482 0 F Treated water above thermal embrittlement threshold for Treated water > 482OF CASS components.
Water -flowing Water that is refreshed, thus having larger impact on Water -flowing leaching of calciumhydroxide from concrete structures.
Water -standing Water that is stagnant and un-refreshed, thus possibly Water -standing resulting in increased ionic strength of solution up to saturation This environment is not an exact match of environments defined in NUREG-1801; however it is bounded by the listed equivalent NUREG-1801 environment Oyster Creek Generation Station License Renewal Application Page 3.0-14