ML070640041
| ML070640041 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Calvert Cliffs, Oconee, Arkansas Nuclear, Turkey Point  |
| Issue date: | 03/06/2007 |
| From: | Tuan Le NRC/NRR/ADRO/DLR/RLRB |
| To: | |
| Le N. B., NRR/DLR/RLRB, 415-1458 | |
| References | |
| IP-71003 | |
| Download: ML070640041 (18) | |
Text
March 6, 2007 MEMORANDUM TO: File FROM:
Tommy Le, Sr. Project Manager /RA/
License Renewal Branch B Division of License Renewal Office of Nuclear Reactor Regulation
SUBJECT:
COMMITMENT LISTS FOR RENEWED OPERATING LICENSE (ROL)
PLANTS WITH NO COMMITMENT APPENDIX ATTACHED TO ITS ROL SAFETY EVALUATION REPORTS/NUREGS FOR USE WITH IP-71003 This memorandum makes the following enclosed commitment lists publicly available for the following ROL plants:
- .1 - Calvert Cliffs Nuclear Power Plant, Units 1 and 2
- .2 - Oconee Nuclear Station, Units 1, 2, and 2
- .3 - Arkansas Nuclear One, Unit 1
- .4 - Edwin I. Hatch Nuclear Plant, Units 1 and 2
- .5 - Turkey Point Nuclear Plant, Units 3 and 4 Docket Nos. 50-317, 50-318, 50-269, 50-270, 50-287, 50-313, 50-321, 50-366, 50-250, and 50-251
Enclosure:
As stated
ML070640041 OFFICE LA: DLR PM:RLRB:DLR NAME IKing TLe DATE 03/6/07 03/06/2007
.1 SITE-SPECIFIC LIST COMMITMENTS FOR POST-RENEWAL INSPECTION AT CALVERT CLIFFS Commitments No.
Commitment Implementation Schedule 1
Thirteen of the systems within the scope of license renewal that contain piping supports are not subject to American Society of Mechanical Engineers (ASME)Section XI inservice inspections (ISIs). Therefore, additional sampling baseline walkdowns will be performed. These walkdowns will consist of a sampling of the supports within the scope of license renewal for the 13 systems. The sample approach will be comparable to the approach required by ASME Section XI for piping supports of ASME Class 3 systems.
Prior to the end of the initial operating license term.
2 The Seismic Verification Project found the current condition of vibration isolators inspected to be acceptable, except for those that support the Control Room HVAC air handler. Prior to the Seismic Verification Project walkdown, these supports were identified by the system engineer as requiring replacement, and a modification is planned to replace the elastomer isolators with spring-type isolators. After these isolators are replaced, follow-on inspections will be adequate to manage aging of elastomer vibration isolator component supports for other equipment.
Prior to the end of the initial operating license term.
3 Some Calvert Cliffs Nuclear Power Plant (CCNPP) PM Program, MN 102, tasks (repetitive tasks) will be modified to look for the effects of specific aging mechanisms. These inspections will explicitly present inspection requirements for discovery of degraded coatings, material loss, or other indications of aging degradation.
Prior to the end of the initial operating license term.
4 Program for discovery of corrosion due to potential boric acid leakage for the piping supports associated with the spent fuel pool (SFP) demineralizer and filter.
Prior to the end of the initial operating license term.
5 Boric Acid Inspection Program (BACI) Program (MN-3-301) will be modified to specify examinations during refueling outages of: (a) the reactor vessel cooling shroud anchorage to the reactor vessel head for evidence of boric acid leakage; and (b) all reactor vessel cooling shroud structural support members for general corrosion/oxidation.
Prior to the end of the initial operating license term.
6 PM Program modified to explicitly present inspection requirements for discovery and management of general corrosion effects in carbon steel parts of the Spent Fuel Inspection Elevator, New Fuel Elevator, transfer machine jib crane, SFCHC, PC, ISSGC, and reactor vessel head lift rig, respectively, by performing visual inspections.
Prior to the end of the initial operating license term.
7 Procedure STP-M-663-1/2 provides instructions for the Containment Tendon Surveillance. These STPs discover and manage the effects of corrosion on the containment tendons by visual inspection and analysis of the filler grease and for discovery and management of the effects of weathering of grout by visual inspection.
Prior to the end of the initial operating license term.
8 The Structure and System Walkdowns Program guidance will be added to assist in functional adequacy determinations and for authority to deviate from scope or schedule. Program will be modified to specify scope and control of periodic structure performance assessments.
Prior to the end of the initial operating license term.
9 Upcoming Baseline Inspections of Containment Structures will be used to verify that any freeze-thaw damage will not affect intended functions.
Prior to the end of the initial operating license term.
10 A new CCNPP Caulking and Sealant Inspection Program will provide requirements and guidance for the identification, inspection frequencies, and acceptance criteria for caulking and sealant used in the Turbine Building to ensure that their condition is maintained at a level that allows them to perform their intended functions. The new program will require a baseline inspection to determine the material condition of the caulking and sealants for the Turbine Building. If unacceptable degradation exists, corrective actions will be taken.
Prior to the end of the initial operating license term.
11 PM Program (MN-1-102) Repetitive Tasks 10092042, 10092043, 10092044, 10092045, 10092046, 10092047, 20092039, 20092040, 20092041, 20092042, 20092043, and 20092044 for Intake Structure Cavity Repairs and Cleaning during Refueling Outages tasks will be modified to include specific age-related degradation mechanisms (ARDMs) where they are not presently included and/or additional specified components/subcomponents where they are not presently inspected.
Prior to the end of the initial operating license term.
12 Repetitive Tasks for Inspection of Sluice Gates Prior to the end of the initial operating license term.
13 Analysis of Neutron Absorbing Material in Spent Fuel Storage Racks, (Engineering Test Procedure 86-03R). The program will be modified to:
(a) reevaluate the adequacy of the sampling intervals in monitoring Carborundum and Boraflex condition through the period of extended operation; and (b) refine the process for scheduling sample packet removal from the SFP. The modified program will ensure that degradation of neutron-absorbing material is identified and corrected such that the SFP storage racks will be capable of performing their intended functions consistent with CLB design conditions Prior to the end of the initial operating license term.
14 A new program will be developed to manage the effects of thermal embrittlement by identifying those components that may be susceptible to the effects of thermal embrittlement. The CASS Evaluation Program will:
(1) screen components; (2) review operating experience; (3) utilize enhanced VT-1 inspection [a visual examination capable of 1/21/2 mil resolution] (for reactor vessel internals [RVI] only); and (4) follow industry programs to evaluate thermal embrittlement and change the program accordingly.
Prior to the end of the initial operating license term.
15 Alloy 600 Program will be modified to include RCS nozzle thermal sleeves and non-pressure boundary components. Welds and base metals are implicitly included in this program. The Alloy 600 Program will be modified to include all Alloy-600 components, not just those forming the pressure boundary.
Prior to the end of the initial operating license term. Volumetric inspections of the CEDM nozzles will occur no later than 2029 for Unit 1.
16 A one-time fatigue analysis will be performed for the reactor coolant pumps (RCPs), motor-operated valves (MOVs), and pressurizer RVs to determine if these components are bounded by components and transients currently included in the Fatigue Monitoring Program (FMP). If these components are not bounded they will be added to the FMP. The FMP will also assess the effect of the environment using statistical correlations developed by ANL in NUREG/CR-5704. The modified FMP will use the ANL statistical correlations to calculate an effective environmental factor to account for the reduction in fatigue life due to the reactor water environment. This factor will be applied to fatigue loads where the specified threshold criteria for strain rate and temperature have been exceeded. A factor of 1.5 will be used for evaluation of austenitic stainless steel components.
Prior to the end of the initial operating license term.
17 Age-Related Degradation Inspection (ARDI). NOTE: Susceptible locations near the RWT penetrations will be included in this program, as necessary, based on the results of an engineering review of SCC at the RWT penetrations.
Will be performed prior to, and near, the end of the current license period (e.g., no sooner than five years prior to expiration of the current license).
18 Comprehensive Reactor Vessel Surveillance Program (CRVSP)
Prior to the end of the initial operating license term. Unit 1 has two supplemental capsules that are designated for testing in 2000 and 2012.
19 The FMP will be modified to perform an engineering evaluation for CEDM/RVLMS components to ensure that the components are bounded.
Prior to the end of the initial operating license term.
20 RVLMS-2 will be modified to include statements that visual inspection of Grayloc clamps, the RVLMS flanges, the associated studs and nuts, and seal plug, and drive nut are to be performed each time the RVLMS housings are reassembled. Components of the RVLMS will be replaced as necessary, based on the results of the inspection.
Prior to the end of the initial operating license term.
21 Analysis of CEA Shroud Bolts Prior to the end of the initial operating license term.
22 The delta ferrite content will be determined for CCNPP's RVI components made from CASS, and the results will be compared to the acceptable thresholds. Initial investigations revealed that formal calculations should show delta ferrite levels are below the established thresholds for these components. The new calculations are expected to show that thermal aging is not plausible and would not affect the intended function of these components during the period of extended operation. If the new calculations show that thermal aging is plausible, then these components would be managed by the CASS Evaluation Program.
Prior to the end of the initial operating license term.
23 ISI of ASME Code Section XI Components, existing program implementing procedures (MN-3-110). Until the data and analyses become available confirming that IASCC or neutron embrittlement should not be considered a plausible ARDM, BGE will perform enhanced VT-1 inspections to detect cracks (if any occur) in the RVI components believed to be potentially most susceptible to IASCC. The inspections will be performed as part of the 10-year ISI program during the license renewal term. (The ISI Program is described in Section 3.1.) Plant-specific justification will be provided to the NRC in the event the analyses and data support elimination of the inspection.
Prior to the end of the initial operating license term.
24 A fatigue analysis will be performed to show that the stress ranges and expected number of transients for these components )CS (plates and ribs only), CSTR (tie rods, nuts, and set screws only), CSC, CSP) will be low enough that thermal fatigue will not impair their intended function during the period of extended operation.
Prior to the end of the initial operating license term.
25 Because the CEA shroud bolts and core shroud tie rod and bolts (CSTR)
(tie rods, nuts, and set screws) are preloaded during initial installation, stress relaxation could affect their structural support function as a loss of preload, which could lead to vibrations and accelerated mechanical fatigue, resulting in cracking. For each of these types of components, an evaluation will be conducted to demonstrate that this ARDM will not occur for the stress levels and radiation conditions.
Prior to the end of the initial operating license term.
26 A new program for buried pipe will include AFW piping and will provide assurance that the piping will remain capable of maintaining the system pressure boundary under all CLB conditions. Representative samples of buried piping will be selected for inspection to ensure that the pipe wrapping/coatings are adequately protecting the pipe from the external environment.
Prior to the end of the initial operating license term.
27 Technical Procedure TURB-01, "Auxiliary Feedwater Pump Turbine Overhaul," disassembles the turbine to inspect for damage.
Measurements are taken to assure critical tolerances are within acceptance criteria. Specific subcomponents are inspected for wear, erosion, pitting, and/or surface cracking.
Prior to the end of the initial operating license term.
28 A new program for buried pipe inspection will include DFO and will provide assurance that the effects of aging are being effectively managed for the period of extended operation under CLB design loading conditions.
This program will consider variations in environmental conditions (including cathodic protection) to select representative samples of the buried piping for inspection to ensure that the pipe coating/wrapping and cathodic protection system are adequately protecting the pipe from external ARDMs.
Prior to the end of the initial operating license term.
29 A new Tank Internal Inspection Program is intended to provide assurance that the effects of plausible aging are being effectively managed. Under this program, BGE will perform an internal inspection of the FOSTs at periodic intervals based on results of previous inspections.
Prior to the end of the initial operating license term.
30 Clean and Inspect EDG Air Start Distributor and CKVs (MPM13000) will be modified to inspect specifically for corrosion of piping and check for the presence of debris in valves that could indicate the piping in these systems is undergoing corrosion.
Prior to the end of the initial operating license term.
31 Clean/Inspect 2B, 1B, and 2A EDG Lube Oil "Y" Strainers and Baskets (MPM13003, MPM13004/MPM13005) will be modified to check for signs of corrosion on the "Y" strainer internal surfaces.
Prior to the end of the initial operating license term.
32 Disassemble, Inspect and Overhaul EDG CKV (MPM07006) will be modified to inspect specifically for corrosion of piping and check for the presence of debris in valves that could indicate the piping in these systems is undergoing corrosion.
Prior to the end of the initial operating license term.
33 Inspect EDG Air Intake Filters (MPM07117) will be modified to inspect the attached piping for signs of corrosion.
Prior to the end of the initial operating license term.
34 Inspect EDG Air Start Valves and Filters (MPM13002) will be modified to inspect specifically for corrosion of piping and check for the presence of debris in valves that could indicate the piping in these systems is undergoing corrosion.
Prior to the end of the initial operating license term.
35 Perform Visual Examination for EDG Exhaust Components (MPM13110) will be modified to look for signs of fatigue on the external surfaces of the EDG exhaust piping and exhaust mufflers.
Prior to the end of the initial operating license term.
36 Remove Relief Valve, Test and Reinstall (MPM01125) will be modified to inspect specifically for corrosion of piping and check for the presence of debris in valves that could indicate the piping in these systems is undergoing corrosion.
Prior to the end of the initial operating license term.
37 To fully address fatigue for license renewal, CCNPP has initiated an additional evaluation, in conjunction with EPRI, to evaluate the effects of low cycle fatigue on the FWS, the pressurizer surge line, and the charging/letdown lines. The evaluation will apply industry-developed methodologies to identify fatigue-sensitive component locations that may require further evaluation or inspection for license renewal, and evaluate environmental effects as necessary. The evaluation objective includes the development and justification of aging management practices for fatigue at various component locations for the renewal period.
Prior to the end of the initial operating license term.
38 In response to NRC Bulletin 88-08, "Thermal Stresses in Piping Connected to Reactor Coolant Systems," BGE identified the potential for thermal stratification in the piping between the SIT outlet CKVs and the loop inlet CKVs, and subsequently confirmed the natural convection phenomenon. Since the current piping analysis for the affected portions of the SI System does not include the additional stresses imposed by thermal stratification, BGE will complete an engineering review of the industry's task reports and determine: (a) any necessary changes to the piping analyses of record for the SI System; and (b) the impact of such changes on fatigue usage parameters used by the FMP.
Prior to the end of the initial operating license term.
39 BGE will therefore complete an engineering review of SCC at the RWT penetrations that will either confirm that detection of minor leakage from the telltale holes will adequately manage SCC prior to a challenge to the structural integrity of the penetrations under design basis conditions or that will include the RWT penetrations and associated welds in an ARDI Program to verify that unacceptable degradation due to SCC at these locations is not occurring.
Prior to the end of the initial operating license term.
40 PM Program (MN-1-102)
For affected components:
Repetitive tasks10122063 through 10122068; 10122096 through 10122102; 20122067 through 20122072; 20122100 through 20122106; 10122086 through 10122088; 10122107 through 10122110; and 20122092 through 20122094; 242. ChecklistsMPM04194; MPM01180; and MPM01181,MPM05000 and MPM05101 242. ProcedurePUMP-03 will be modified to include specific ARDMs where they are not presently included and/or additional specified components/ subcomponents where they are not presently inspected.
Prior to the end of the initial operating license term.
41 SRW Pump Overhaul (PUMP-15) will be modified to include inspections for general corrosion, crevice corrosion/pitting on the pump casing and bushings.
Prior to the end of the initial operating license term.
42 Repetitive Task 10672001 will be modified to explicitly call for inspection of the components for signs of boric acid corrosion.
Prior to the end of the initial operating license term.
43 Repetitive Tasks 00672007, 00672008 will be modified to explicitly present inspection requirements.
Prior to the end of the initial operating license term.
44 Cables Aging Management Program Prior to the end of the initial operating license term.
45 PM Program (MN-1-102) Certain existing repetitive tasks will be modified to include specific ARDMs where they are not presently included and/or additional specified components/ subcomponents where they are not presently inspected.
Prior to the end of the initial operating license term.
Reference Documents A.
Facility Operating License Date Facility Operating License Issued: Unit 1 - 7/31/1974; Unit 2 -
8/13/1976 Date New License Expires: Unit 1 - 7/31/2034; Unit 2 - 8/13/2036 Date Initial License Expires (prior to Period of Extended Operation):
Unit 1 - 7/31/2014; Unit 2 - 8/13/2016 B.
Safety Evaluation Report (SER) NUREG Number:1705, ML993330372 C.
Initial license renewal inspection reports numbers:50-317/99-02, 50-318/99-02, 50-317/99-04, 50-318/99-04, 50-317/99-12, 50-318/99-12
.2 SITE-SPECIFIC LIST OF COMMITMENTS FOR POST-RENEWAL INSPECTION AT OCONEE NUCLEAR STATION Commitments No.
Commitment Implementation Schedule 1
Conduct a one-time Cast Iron Selective Leaching Inspection Prior to the end of the initial operating license term.
2 Conduct a one-time Galvanic Susceptibility Inspection Prior to the end of the initial operating license term.
3 Keowee Air and Gas Systems Inspection (The inspection program consists primarily of volumetric examinations (e.g., ultrasonic testing) for the discharge piping low-elevation point of the carbon dioxide system, the piping between the control valves and the Keowee unit turbine head cover in the depressing air system, and the piping between the air receiver tank and governor oil pressure tank in the governor air system.
Prior to the end of the initial operating license term.
4 Conduct a Once Through Steam Generator Upper Lateral Support Inspection Prior to the end of the initial operating license term.
5 Pressurizer Examinations, including cladding, spray line, spray head, and heater bundle penetration welds Prior to the end of the initial operating license term.
6 Reactor Building Spray System Inspection Prior to the end of the initial operating license term.
7 Reactor Coolant Pump Motor Oil Collection System Inspection Prior to the end of the initial operating license term.
8 Conduct a Small Bore Piping Inspection Prior to the end of the initial operating license term.
9 Conduct a Treated Water System Stainless Steel Inspection Prior to the end of the initial operating license term.
10 Implement Alloy 600 Aging Management Program to manage cracking due to PWSCC of Alloy 600 and Alloy 82/182 locations, including the Alloy 82/182 cladding in the hot leg flowmeter element.
Prior to the end of the initial operating license term.
11 Reactor Vessel Internal Inspection: Committed to participate in the B&W Owners Group Reactor Vessel Internals Aging Management Program and other industry programs, as appropriate. The scope of this inspection program covers cracking due to irradiation-assisted stress corrosion cracking and SCC, reduction of fracture toughness due to irradiation embrittlement and thermal embrittlement, dimensional changes due to void swelling, and loss of closure integrity due to stress relaxation.
Prior to the end of the initial operating license term.
12 Implement Insulated Cables and Connections Aging Management Program Prior to the end of the initial operating license term.
13 A plant-specific analysis will be performed to demonstrate that, under loss-of-coolant-accident (LOCA) and seismic loading, the internals have adequate ductility to absorb local strain at the regions of maximum stress intensity and that irradiation accumulated at the expiration of the renewal license will not adversely affect deformation limits. Data will be developed to demonstrate that the internals will meet the deformation limits at the expiration of the renewal license.
Prior to the end of the initial operating license term.
14 The Oconee Thermal Fatigue Management Program will be modified to incorporate a plant-specific resolution of Generic Safety Issue (GSI)- 190, "Fatigue Evaluation of Metal Components for 60-year Plant Life."
Plant-specific actions will be taken either in the manner that was described in Duke letter to the NRC dated October 15, 1999, "Safety Evaluation Report - Oconee Nuclear Station License Renewal Application, Comments and Responses to Open items and Confirmatory Items, Response to Open Item 4.2.3-2," or by using another approach that is acceptable to the NRC staff.
Prior to the end of the initial operating license term.
Reference Documents A.
Facility Operating License Date Facility Operating License Issued: Unit 1 - 2/6/1973; Unit 2 -
10/6/1973; Unit 3 - 7/19/1974 Date New License Expires: Unit 1 - 2/6/2033; Unit 2 - 10/6/2033; Unit 3 - 7/19/2034 Date Initial License Expires (prior to Period of Extended Operation):
Unit 1 - 2/6/2013; Unit 2 - 10/6/2013; Unit 3 - 7/19/2014 B.
Safety Evaluation Report (SER) NUREG Number:1723, ML003695154 C.
Initial license renewal inspection reports numbers: 50-269/99-11, 50-270/99-11, 50-287/99-11; 50-269/99-12,50-270/99-12, 50-289/99-12; 50-269/2000-03, 50-270/2000-03, 50-289/2000-03
.3 SITE-SPECIFIC LIST OF COMMITMENTS FOR POST-RENEWAL INSPECTION AT ARKANSAS NUCLEAR ONE UNIT 1 Outstanding Commitments No.
Commitment Implementation Schedule 1
Implement Buried Piping Inspection Prior to the end of the initial operating license term.
2 Implement Electrical Component Inspection Prior to the end of the initial operating license term.
3 Implement Heat Exchanger Monitoring Prior to the end of the initial operating license term.
4 Implement Pressurizer Heater Bundle Penetration Welds Examination Prior to or during the period of extended operations.
5 Implement Reactor Vessel Internals Aging Management Begin during period of extended operations.
6 Implement Spent Fuel Pool Monitoring Prior to the end of the initial operating license term.
7 Implement Wall Thinning Inspection Prior to the end of the initial operating license term.
8 Conduct one-time ASME IWB Inspection of RCP casings Prior to the end of the initial operating license term.
9 Augmented Inspections of:welds on piping wetted by reactor building sump water; Q stainless piping of main steam system; a one-time inspection of the penetration 68 piping and components and the decay heat pump room drain valves to ensure the seismic qualification is maintained to manage the aging effects of loss of material and cracking; penetrations 10, 47, 58 and 64 to verify that there is no cracking in these penetrations.
Prior to the end of the initial operating license term.
10 Incorporate additional guidance for coatings inspections as part of existing system and structural walkdowns during next revision of System Engineering Desk Guide Prior to the end of the initial operating license term.
11 New preventive maintenance activities that address inspection criteria for aging effects will be incorporated into existing preventive maintenance procedures Prior to the end of the initial operating license term.
Reference Documents A.
Facility Operating License Date Facility Operating License Issued:5/21/1974 Date New License Expires:5/20/2034 Date Initial License Expires (prior to Period of Extended Operation):
5/20/2014 B.
Safety Evaluation Report (SER) NUREG Number:1743, ML011640099, ML011640177, ML011640217 C.
Initial license renewal inspection reports numbers: 50-313/00-17, 50-313/01-03
.4 SITE-SPECIFIC LIST OF COMMITMENTS FOR POST-RENEWAL INSPECTION AT EDWIN I. HATCH NUCLEAR PLANT Outstanding Commitments No.
Commitment Implementation Schedule 1
Fire protection activities will be enhanced to include periodic inspection of water suppression system strainers which will be inspected for flow blockage and loss of material due to mechanisms such as corrosion.
Prior to the end of the initial operating license term.
2 The enhanced examination methods and frequencies for the Flow Accelerated Corrosion Program will be based on industry and plant specific operating experience as opposed to computer modeling.
Examinations to detect erosion, erosion corrosion, as well as FAC, will be performed as part of the enhanced program.
For both units, the Flow Accelerated Corrosion Program will be expanded to include additional piping for certain systems that are already included in the current program.
For Unit 2 only, portions of the radioactive decay holdup volume (main steam and steam line drains, and condensate drains) will also be included.
Prior to the end of the initial operating license term.
3 The Protective Coatings Program will be expanded to include the external surfaces of carbon steel commodities in-scope for License Renewal that are exposed to inside, outside, submerged, and buried environments as made accessible.
The Protective Coatings Program will be revised to require periodic inspections of in-scope components to ensure that they are properly coated and free of significant age-related degradation.
Prior to the end of the initial operating license term.
4 The Equipment and Piping Insulation Monitoring Program will be expanded to include inscope portions of inside equipment and piping insulation. Insulation will be periodically examined for holes, tears, compaction, and material separation, wetting, missing insulation and general deterioration, using appropriate visual inspection techniques.
Aluminum and galvanized steel insulation jackets and their binders will be visually inspected for cracking and loss of material.
Prior to the end of the initial operating license term.
5 The scope of the Structures Monitoring Program, SMP will be expanded to include visual inspections of the following structures and components:
- Sealants in the joints between the reactor building exterior precast siding panels.
- Seismic Category I and Seismic Category II/I piping supports and tube tray supports.
- Seismic Category I HVAC duct supports.
- Seismic Category I and Seismic Category II/I cable trays and cable tray supports.
- Seismic Category I and Seismic Category II/I conduits and conduit supports.
- Seismic Category I Control room panels, racks and supports.
- Seismic Category I Auxiliary panels, racks and supports.
- Reactor building tornado vents.
The frequency of enhanced visual inspections will be based on specific plant experience, commensurate with prudent concern for adequately managing aging. Additional emphasis will be placed on the importance of inspecting and documenting the condition of normally inaccessible (underground or embedded) structures.
Prior to the end of the initial operating license term.
6 Galvanic Susceptibility Inspections will provide for condition monitoring via one time inspections that will provide objective evidence that galvanic susceptibility is being managed for specific components within the scope of license renewal.
Prior to the end of the initial operating license term.
7 The plant Treated Water Systems Piping Inspections will provide for condition monitoring via one time examinations intended to provide objective evidence that existing Chemistry Control is managing aging in piping that is not examined under another inspection program.
Prior to the end of the initial operating license term.
8 Gas Systems Component Inspections will provide for condition monitoring via one time condition monitoring aging management activities designed to provide objective evidence that the aging effects predicted for systems with gases as internal environments are being adequately managed.
Prior to the end of the initial operating license term.
9 Condensate Storage Tank (CST) Inspections will provide for condition monitoring via one time inspections intended to provide objective evidence that the aging effects predicted for the CST internal environments are adequately managed by programs credited for the renewal term.
Prior to the end of the initial operating license term.
10 The passive component inspection activities will be designed to collect, report and trend age-related data. This activity will verify the effectiveness of preventive or mitigative programs/activities credited for aging management.
Prior to the end of the initial operating license term.
11 Residual Heat Removal (RHR) Heat Exchanger Augmented Inspection and Testing Program is a condition monitoring program that will provide enhanced aging management of both the shell and tube sides of the Unit 1 and Unit 2 RHR heat exchangers.
The RHR heat exchangers will be visually inspected, and eddy current testing will be done on a regular basis.
Prior to the end of the initial operating license term.
12 The Torus Submerged Components Inspection Program is a condition monitoring activity that will provide a means for evaluating the effectiveness of the current suppression pool chemistry control in preventing loss of material and cracking in the components within the scope of license renewal.
Prior to the end of the initial operating license term.
Reference Documents A.
Facility Operating License Date Facility Operating License Issued: Unit 1 - 8/6/1974; Unit 2 -
6/13/1978 Date New License Expires: Unit 1 - 8/6/2034; Unit 2 - 6/13/2038 Date Initial License Expires (prior to Period of Extended Operation):
Unit 1 8/6/2014; Unit 2 - 6/13/2018 B.
Safety Evaluation Report (SER) NUREG Number:1803, ML020020160, ML020020291, ML020020301 C.
Initial license renewal inspection reports numbers:50-321/00-09, 50-366/00-09, 50-321/00-10, 50-366/00-10
.5 SITE-SPECIFIC LIST OF COMMITMENTS FOR POST-RENEWAL INSPECTION AT TURKEY POINT NUCLEAR PLANT Outstanding Commitments No.
Commitment Implementation Schedule 1
Auxiliary Feedwater Pump Oil Coolers Inspection. A one-time visual inspection will be performed on one of the cast iron bonnets of the auxiliary feedwater pump lube oil coolers to assess the extent of loss of material due to corrosion.
Prior to the end of the initial operating license term.
2 Implement Auxiliary Feedwater Steam Piping Inspection Program Prior to the end of the initial operating license term.
3 A one-time volumetric examination of a sample of emergency containment coolers (ECC) tubes will be performed to determine the extent of loss of material due to erosion in the ECC tubes.
Prior to the end of the initial operating license term.
4 A one-time visual inspection to determine the extent of corrosion on the internal surfaces of the field erected tanks for both units
-- including the Condensate Storage Tanks, the Demineralized Water Storage Tank, and the Refueling Water Storage Tanks -- will be performed.
Prior to the end of the initial operating license term.
5 Implement Galvanic Corrosion Susceptibility Inspection Program Prior to the end of the initial operating license term.
6 Implement Reactor Vessel Internals Inspection Program Prior to the end of the initial operating license term.
7 A volumetric inspection of a sample of small bore Class 1 piping and nozzles will be performed to determine if cracking is an aging effect requiring management during the period of extended operation. This one-time inspection will address Class 1 piping less than 4 inches in diameter.
Prior to the end of the initial operating license term.
8 The Boraflex Surveillance Program will be enhanced to provide for density testing (or other approved testing methods if available) of the encapsulated Boraflex material in the spent fuel storage racks.
Prior to the end of the initial operating license term.
9 The scope of the Boric Acid Wastage Surveillance Program will be enhanced to include systems and components outside containment.
Prior to the end of the initial operating license term.
10 The scope of the Fire Protection Program will be enhanced to include inspection of additional components.
Prior to the end of the initial operating license term.
11 The Flow Accelerated Corrosion Program will be enhanced to address internal and external loss of material of steam trap lines due to flow accelerated corrosion and general corrosion, respectively.
Prior to the end of the initial operating license term.
12 The Intake Cooling Water System Inspection Program will be enhanced to improve documentation of scope and frequency of the intake cooling water piping crawl-through inspections and component cooling water heat exchanger tube integrity inspections.
Prior to the end of the initial operating license term.
13 Specific enhancements to the scope and documentation of some inspections performed under the Periodic Surveillance and Preventive Maintenance Program will be implemented.
Prior to the end of the initial operating license term.
14 Program documentation will be enhanced to integrate all aspects of the Reactor Vessel Integrity Program.
Prior to the end of the initial operating license term.
15 The Systems and Structures Monitoring Program will be enhanced by restructuring it to address inspection requirements to manage certain aging effects in accordance with 10 CFR 54, modifying the scope of specific inspections, and improving documentation requirements.
Prior to the end of the initial operating license term.
Reference Documents A.
Facility Operating License Date Facility Operating License Issued: Unit 3 - 7/19/1972; Unit 4 -
4/10/1973 Date New License Expires: Unit 3 - 7/19/2032; Unit 4 - 4/10/2033 Date Initial License Expires (prior to Period of Extended Operation):
Unit 3 - 7/19/2012; Unit 4 - 4/10/2013 B.
Safety Evaluation Report (SER) NUREG Number:1759, ML021280496, ML021280532, ML021560094 C.
Initial license renewal inspection report numbers: 50-250/01-09, 50-252/01-09, 50-250/01-11, 50-252/01-11