ML070640041

Commitment Lists for Renewed Operating License (ROL) Plants with No Commitment Appendix Attached to Its ROL Sers/Nuregs for Use with IP-71003

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:

• Attachment 1.1 - Calvert Cliffs Nuclear Power Plant, Units 1 and 2

• Attachment 1.2 - Oconee Nuclear Station, Units 1, 2, and 2

• Attachment 1.3 - Arkansas Nuclear One, Unit 1

• Attachment 1.4 - Edwin I. Hatch Nuclear Plant, Units 1 and 2

• Attachment 1.5 - 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 Attachment 1.1 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 Prior to the end piping supports are not subject to American Society of Mechanical of the initial Engineers (ASME)Section XI inservice inspections (ISIs). Therefore, operating license additional sampling baseline walkdowns will be performed. These term.

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.

2 The Seismic Verification Project found the current condition of vibration Prior to the end isolators inspected to be acceptable, except for those that support the of the initial Control Room HVAC air handler. Prior to the Seismic Verification Project operating license walkdown, these supports were identified by the system engineer as term.

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.

3 Some Calvert Cliffs Nuclear Power Plant (CCNPP) PM Program, MN Prior to the end 102, tasks (repetitive tasks) will be modified to look for the effects of of the initial specific aging mechanisms. These inspections will explicitly present operating license inspection requirements for discovery of degraded coatings, material loss, term.

or other indications of aging degradation.

4 Program for discovery of corrosion due to potential boric acid leakage for Prior to the end the piping supports associated with the spent fuel pool (SFP) of the initial demineralizer and filter. operating license term.

5 Boric Acid Inspection Program (BACI) Program (MN-3-301) Prior to the end will be modified to specify examinations during refueling outages of: (a) of the initial the reactor vessel cooling shroud anchorage to the reactor vessel head operating license for evidence of boric acid leakage; and (b) all reactor vessel cooling term.

shroud structural support members for general corrosion/oxidation.

6 PM Program modified to explicitly present inspection requirements for Prior to the end discovery and management of general corrosion effects in carbon steel of the initial parts of the Spent Fuel Inspection Elevator, New Fuel Elevator, transfer operating license machine jib crane, SFCHC, PC, ISSGC, and reactor vessel head lift rig, term.

respectively, by performing visual inspections.

7 Procedure STP-M-663-1/2 provides instructions for the Containment Prior to the end Tendon Surveillance. These STPs discover and manage the effects of of the initial corrosion on the containment tendons by visual inspection and analysis of operating license the filler grease and for discovery and management of the effects of term.

weathering of grout by visual inspection.

8 The Structure and System Walkdowns Program guidance will be added Prior to the end to assist in functional adequacy determinations and for authority to of the initial deviate from scope or schedule. Program will be modified to specify operating license scope and control of periodic structure performance assessments. term.

9 Upcoming Baseline Inspections of Containment Structures will be used to Prior to the end verify that any freeze-thaw damage will not affect intended functions. of the initial operating license term.

10 A new CCNPP Caulking and Sealant Inspection Program will provide Prior to the end requirements and guidance for the identification, inspection frequencies, of the initial and acceptance criteria for caulking and sealant used in the Turbine operating license Building to ensure that their condition is maintained at a level that allows term.

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.

11 PM Program (MN-1-102) Repetitive Tasks 10092042, 10092043, Prior to the end 10092044, 10092045, 10092046, 10092047, 20092039, 20092040, of the initial 20092041, 20092042, 20092043, and 20092044 for Intake Structure operating license Cavity Repairs and Cleaning during Refueling Outages term.

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.

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, Prior to the end (Engineering Test Procedure 86-03R). The program will be modified to: of the initial (a) reevaluate the adequacy of the sampling intervals in monitoring operating license Carborundum and Boraflex condition through the period of extended term.

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 14 A new program will be developed to manage the effects of thermal Prior to the end embrittlement by identifying those components that may be susceptible to of the initial the effects of thermal embrittlement. The CASS Evaluation Program will: operating license (1) screen components; (2) review operating experience; (3) utilize term.

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.

15 Alloy 600 Program will be modified to include RCS nozzle thermal sleeves Prior to the end and non-pressure boundary components. Welds and base metals are of the initial implicitly included in this program. The Alloy 600 Program will be operating license modified to include all Alloy-600 components, not just those forming the term. Volumetric pressure boundary. 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 Prior to the end pumps (RCPs), motor-operated valves (MOVs), and pressurizer RVs to of the initial determine if these components are bounded by components and operating license transients currently included in the Fatigue Monitoring Program (FMP). If term.

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.

17 Age-Related Degradation Inspection (ARDI). NOTE: Susceptible Will be locations near the RWT penetrations will be included in this program, as performed prior necessary, based on the results of an engineering review of SCC at the to, and near, the RWT penetrations. 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 Prior to the end CEDM/RVLMS components to ensure that the components are bounded. of the initial operating license term.

20 RVLMS-2 will be modified to include statements that visual inspection of Prior to the end Grayloc clamps, the RVLMS flanges, the associated studs and nuts, and of the initial seal plug, and drive nut are to be performed each time the RVLMS operating license housings are reassembled. Components of the RVLMS will be replaced term.

as necessary, based on the results of the inspection.

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 Prior to the end made from CASS, and the results will be compared to the acceptable of the initial thresholds. Initial investigations revealed that formal calculations should operating license show delta ferrite levels are below the established thresholds for these term.

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.

23 ISI of ASME Code Section XI Components, existing program Prior to the end implementing procedures (MN-3-110). Until the data and analyses of the initial become available confirming that IASCC or neutron embrittlement should operating license not be considered a plausible ARDM, BGE will perform enhanced VT-1 term.

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.

24 A fatigue analysis will be performed to show that the stress ranges and Prior to the end expected number of transients for these components )CS (plates and ribs of the initial only), CSTR (tie rods, nuts, and set screws only), CSC, CSP) will be low operating license enough that thermal fatigue will not impair their intended function during term.

the period of extended operation.

25 Because the CEA shroud bolts and core shroud tie rod and bolts (CSTR) Prior to the end (tie rods, nuts, and set screws) are preloaded during initial installation, of the initial stress relaxation could affect their structural support function as a loss of operating license preload, which could lead to vibrations and accelerated mechanical term.

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.

26 A new program for buried pipe will include AFW piping and will provide Prior to the end assurance that the piping will remain capable of maintaining the system of the initial pressure boundary under all CLB conditions. Representative samples of operating license buried piping will be selected for inspection to ensure that the pipe term.

wrapping/coatings are adequately protecting the pipe from the external environment.

27 Technical Procedure TURB-01, "Auxiliary Feedwater Pump Turbine Prior to the end Overhaul," disassembles the turbine to inspect for damage. of the initial Measurements are taken to assure critical tolerances are within operating license acceptance criteria. Specific subcomponents are inspected for wear, term.

erosion, pitting, and/or surface cracking.

28 A new program for buried pipe inspection will include DFO and will Prior to the end provide assurance that the effects of aging are being effectively managed of the initial for the period of extended operation under CLB design loading conditions. operating license This program will consider variations in environmental conditions term.

(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.

29 A new Tank Internal Inspection Program is intended to provide assurance Prior to the end that the effects of plausible aging are being effectively managed. Under of the initial this program, BGE will perform an internal inspection of the FOSTs at operating license periodic intervals based on results of previous inspections. term.

30 Clean and Inspect EDG Air Start Distributor and CKVs (MPM13000) will Prior to the end be modified to inspect specifically for corrosion of piping and check for of the initial the presence of debris in valves that could indicate the piping in these operating license systems is undergoing corrosion. term.

31 Clean/Inspect 2B, 1B, and 2A EDG Lube Oil "Y" Strainers and Baskets Prior to the end (MPM13003, MPM13004/MPM13005) will be modified to check for signs of the initial of corrosion on the "Y" strainer internal surfaces. operating license term.

32 Disassemble, Inspect and Overhaul EDG CKV (MPM07006) will be Prior to the end modified to inspect specifically for corrosion of piping and check for the of the initial presence of debris in valves that could indicate the piping in these operating license systems is undergoing corrosion. term.

33 Inspect EDG Air Intake Filters (MPM07117) will be modified to inspect the Prior to the end attached piping for signs of corrosion. of the initial operating license term.

34 Inspect EDG Air Start Valves and Filters (MPM13002) will be modified to Prior to the end inspect specifically for corrosion of piping and check for the presence of of the initial debris in valves that could indicate the piping in these systems is operating license undergoing corrosion. term.

35 Perform Visual Examination for EDG Exhaust Components (MPM13110) Prior to the end will be modified to look for signs of fatigue on the external surfaces of the of the initial EDG exhaust piping and exhaust mufflers. operating license term.

36 Remove Relief Valve, Test and Reinstall (MPM01125) will be modified to Prior to the end inspect specifically for corrosion of piping and check for the presence of of the initial debris in valves that could indicate the piping in these systems is operating license undergoing corrosion. term.

37 To fully address fatigue for license renewal, CCNPP has initiated an Prior to the end additional evaluation, in conjunction with EPRI, to evaluate the effects of of the initial low cycle fatigue on the FWS, the pressurizer surge line, and the operating license charging/letdown lines. The evaluation will apply industry-developed term.

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.

38 In response to NRC Bulletin 88-08, "Thermal Stresses in Piping Prior to the end Connected to Reactor Coolant Systems," BGE identified the potential for of the initial thermal stratification in the piping between the SIT outlet CKVs and the operating license loop inlet CKVs, and subsequently confirmed the natural convection term.

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.

39 BGE will therefore complete an engineering review of SCC at the RWT Prior to the end penetrations that will either confirm that detection of minor leakage from of the initial the telltale holes will adequately manage SCC prior to a challenge to the operating license structural integrity of the penetrations under design basis conditions or term.

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.

40 PM Program (MN-1-102) Prior to the end For affected components: of the initial Repetitive tasks10122063 through 10122068; operating license 10122096 through 10122102; term.

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.

41 SRW Pump Overhaul (PUMP-15) will be modified to include inspections Prior to the end for general corrosion, crevice corrosion/pitting on the pump casing and of the initial bushings. operating license term.

42 Repetitive Task 10672001 will be modified to explicitly call for inspection Prior to the end of the components for signs of boric acid corrosion. of the initial operating license term.

43 Repetitive Tasks 00672007, 00672008 will be modified to explicitly Prior to the end present inspection requirements. 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 Prior to the end to include specific ARDMs where they are not presently included and/or of the initial additional specified components/ subcomponents where they are not operating license presently inspected. 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

Attachment 1.2 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 Prior to the end consists primarily of volumetric examinations (e.g., ultrasonic testing) for of the initial the discharge piping low-elevation point of the carbon dioxide system, the operating license piping between the control valves and the Keowee unit turbine head cover term.

in the depressing air system, and the piping between the air receiver tank and governor oil pressure tank in the governor air system.

4 Conduct a Once Through Steam Generator Upper Lateral Support Prior to the end Inspection of the initial operating license term.

5 Pressurizer Examinations, including cladding, spray line, spray head, and Prior to the end heater bundle penetration welds 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 Prior to the end due to PWSCC of Alloy 600 and Alloy 82/182 locations, including the of the initial Alloy 82/182 cladding in the hot leg flowmeter element. operating license term.

11 Reactor Vessel Internal Inspection: Committed to participate in the B&W Prior to the end Owners Group Reactor Vessel Internals Aging Management Program of the initial and other industry programs, as appropriate. The scope of this inspection operating license program covers cracking due to irradiation-assisted stress corrosion term.

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.

12 Implement Insulated Cables and Connections Aging Management Prior to the end Program of the initial operating license term.

13 A plant-specific analysis will be performed to demonstrate that, under Prior to the end loss-of-coolant-accident (LOCA) and seismic loading, the internals have of the initial adequate ductility to absorb local strain at the regions of maximum stress operating license intensity and that irradiation accumulated at the expiration of the renewal term.

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.

14 The Oconee Thermal Fatigue Management Program will be modified to Prior to the end incorporate a plant-specific resolution of Generic Safety Issue (GSI)- 190, of the initial "Fatigue Evaluation of Metal Components for 60-year Plant Life." operating license Plant-specific actions will be taken either in the manner that was term.

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.

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

Attachment 1.3 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 Prior to the end sump water; Q stainless piping of main steam system; a one-time of the initial inspection of the penetration 68 piping and components and the decay operating license heat pump room drain valves to ensure the seismic qualification is term.

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.

10 Incorporate additional guidance for coatings inspections as part of Prior to the end existing system and structural walkdowns during next revision of System of the initial Engineering Desk Guide operating license term.

11 New preventive maintenance activities that address inspection criteria for Prior to the end aging effects will be incorporated into existing preventive maintenance of the initial procedures 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

Attachment 1.4 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 Prior to the end water suppression system strainers which will be inspected for of the initial flow blockage and loss of material due to mechanisms such as corrosion. operating license term.

2 The enhanced examination methods and frequencies for the Flow Prior to the end Accelerated Corrosion Program will be based on industry and plant of the initial specific operating experience as opposed to computer modeling. operating license Examinations to detect erosion, erosion corrosion, as well as FAC, will be term.

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.

3 The Protective Coatings Program will be expanded to include the external Prior to the end surfaces of carbon steel commodities in-scope for License Renewal that of the initial are exposed to inside, outside, operating license submerged, and buried environments as made accessible. term.

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.

4 The Equipment and Piping Insulation Monitoring Program will be Prior to the end expanded to include inscope portions of inside equipment and piping of the initial insulation. Insulation will be periodically examined for holes, tears, operating license compaction, and material separation, wetting, missing insulation term.

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.

5 The scope of the Structures Monitoring Program, SMP will be expanded Prior to the end to include visual inspections of the following structures and components: of the initial

• Sealants in the joints between the reactor building exterior precast siding operating license panels. term.

• 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.

6 Galvanic Susceptibility Inspections will provide for condition monitoring via Prior to the end one time inspections that will provide objective evidence that of the initial galvanic susceptibility is being managed for specific components within the operating license scope of license renewal. term.

7 The plant Treated Water Systems Piping Inspections will provide for Prior to the end condition monitoring via one time examinations intended to provide of the initial objective evidence that existing Chemistry Control is managing aging in operating license piping that is not examined under another inspection program. term.

8 Gas Systems Component Inspections will provide for condition monitoring Prior to the end via one time condition monitoring aging management activities designed of the initial to provide objective evidence that the aging effects predicted for systems operating license with gases as internal environments are term.

being adequately managed.

9 Condensate Storage Tank (CST) Inspections will provide for condition Prior to the end monitoring via one time inspections intended to provide objective of the initial evidence that the aging effects predicted for the CST internal operating license environments are adequately managed by programs credited term.

for the renewal term.

10 The passive component inspection activities will be designed to collect, Prior to the end report and trend age-related data. This activity will verify the effectiveness of the initial of preventive or mitigative programs/activities credited for aging operating license management. term.

11 Residual Heat Removal (RHR) Heat Exchanger Augmented Inspection Prior to the end and Testing Program is a condition monitoring program that will provide of the initial enhanced aging management of both the shell and tube sides of the Unit operating license 1 and Unit 2 RHR heat exchangers. term.

The RHR heat exchangers will be visually inspected, and eddy current testing will be done on a regular basis.

12 The Torus Submerged Components Inspection Program is a condition Prior to the end monitoring activity that will provide a means for evaluating the of the initial effectiveness of the current suppression pool chemistry control in operating license preventing loss of material and cracking in the components within the term.

scope of license renewal.

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

Attachment 1.5 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 Prior to the end inspection will be performed on one of the cast iron bonnets of the of the initial auxiliary feedwater pump lube oil coolers to assess the extent of loss operating license of material due to corrosion. 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 Prior to the end containment coolers (ECC) tubes will be performed to determine of the initial the extent of loss of material due to erosion in the ECC tubes. operating license term.

4 A one-time visual inspection to determine the extent of corrosion on the Prior to the end internal surfaces of the field erected tanks for both units of the initial

-- including the Condensate Storage Tanks, the Demineralized Water operating license Storage Tank, and the Refueling Water Storage Tanks -- will be performed. 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 Prior to the end nozzles will be performed to determine if cracking is an aging effect of the initial requiring management during the period of extended operation. This one- operating license time inspection will address Class 1 piping less than 4 inches in diameter. term.

8 The Boraflex Surveillance Program will be enhanced to provide for Prior to the end density testing (or other approved testing methods if available) of the of the initial encapsulated Boraflex material in the spent fuel storage racks. operating license term.

9 The scope of the Boric Acid Wastage Surveillance Program will be Prior to the end enhanced to include systems and components outside containment. of the initial operating license term.

10 The scope of the Fire Protection Program will be enhanced to include Prior to the end inspection of additional components. of the initial operating license term.

11 The Flow Accelerated Corrosion Program will be enhanced to address Prior to the end internal and external loss of material of steam trap lines due to flow of the initial accelerated corrosion and general corrosion, respectively. operating license term.

12 The Intake Cooling Water System Inspection Program will be enhanced Prior to the end to improve documentation of scope and frequency of the intake of the initial cooling water piping crawl-through inspections and component cooling operating license water heat exchanger tube integrity inspections. term.

13 Specific enhancements to the scope and documentation of some Prior to the end inspections performed under the Periodic Surveillance and Preventive of the initial Maintenance Program will be implemented. operating license term.

14 Program documentation will be enhanced to integrate all aspects of the Prior to the end Reactor Vessel Integrity Program. of the initial operating license term.

15 The Systems and Structures Monitoring Program will be enhanced by Prior to the end restructuring it to address inspection requirements to manage of the initial certain aging effects in accordance with 10 CFR 54, modifying the scope operating license of specific inspections, and improving documentation requirements. 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