ML20170A443

From kanterella
Jump to navigation Jump to search
Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR-15.2, Rev. 1, License Renewal Supplement Programs and Activities for Managing the Effects of Aging
ML20170A443
Person / Time
Site: Fort Calhoun, 07100256  Omaha Public Power District icon.png
Issue date: 04/30/2020
From:
Omaha Public Power District
To:
Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards
Shared Package
ML20170A380 List: ... further results
References
LIC-20-0005
Download: ML20170A443 (7)


Text

Page 1 of 7 DSAR-15.2 License Renewal Supplement Programs and Activities for Managing the Effects of Aging Rev 1 Safety Classification: Usage Level:

Safety Information Change No.: EC 70072 Reason for Change: Revised to call out the tanks that have receipt testing performed on fuel deliveries. FO-10 will no longer have fuel receipt testing performed.

Preparer: T. Schulte Fort Calhoun Station

DSAR-15.2 Information Use Page 2 of 7 Programs and Activities for Rev. 1 Managing the Effects of Aging Table of Contents 15.2 Programs and Activities for Managing the Effects of Aging .................................... 3 15.2.1 Deleted .................................................................................................... 3 15.2.2 Bolting Integrity........................................................................................ 3 15.2.3 Boric Acid Corrosion Prevention Program ............................................... 3 15.2.4 Buried Piping and Components Program ................................................ 4 15.2.5 Chemistry ................................................................................................ 4 15.2.6 Deleted .................................................................................................... 4 15.2.7 Deleted .................................................................................................... 4 15.2.8 Service Water Reliability Program ........................................................... 4 15.2.9 Diesel Fuel Monitoring and Storage ........................................................ 5 15.2.10 Deleted .................................................................................................... 5 15.2.11 Fire Protection Program .......................................................................... 5 15.2.12 Deleted .................................................................................................... 5 15.2.13 General Corrosion of External Surfaces .................................................. 5 15.2.14 Inservice Inspection Program .................................................................. 5 15.2.15 Cables and Connections Program........................................................... 6 15.2.16 Deleted .................................................................................................... 6 15.2.17 Overhead Loads and Handling Equipment .............................................. 6 15.2.18 Periodic Surveillance and Preventive Maintenance Program .................. 7 15.2.19 Deleted .................................................................................................... 7 15.2.20 Deleted .................................................................................................... 7 15.2.21 Selective Leaching Program.................................................................... 7 15.2.22 Deleted .................................................................................................... 7 15.2.23 Structures Monitoring Program................................................................ 7 15.2.24 Deleted .................................................................................................... 7

DSAR-15.2 Information Use Page 3 of 7 Programs and Activities for Rev. 1 Managing the Effects of Aging 15.2 Programs and Activities for Managing the Effects of Aging This section provides summaries of the programs and activities credited for managing the effects of aging, in alphabetical order. The FCS Quality Assurance Program implements the requirements of 10 CFR 50, Appendix B, and is consistent with the summary in Section A.2 of NUREG 1800, Standard Review Plan for the Review of License Renewal Applications for Nuclear Power Plants, published July 2001. The Quality Assurance Program includes the elements of corrective action, confirmation process, and administrative controls, and is applicable to the safety-related and nonsafety-related structures, systems, and components that are within the scope of license renewal.

15.2.1 Deleted 15.2.2 Bolting Integrity Bolting Integrity activities include periodic inspection of closure and structural bolting for indications of potential problems, including loss of material, crack initiation, and loss of preload. Bolting Integrity implements guidelines on materials selection, strength and hardness properties, installation procedures, lubricants and sealants, corrosion considerations in the selection and installation of pressure-retaining bolting, and enhanced inspection techniques. It is based on (1) the Bolting integrity report delineated in NUREG-1339; Resolution of Generic Safety Issue 29: Bolting Degradation or Failure in Nuclear Power Plants; (2) industry's recommendations delineated in ERPRI NP-5769, Degradation and Failure of Bolting in Nuclear Power Plants, with the exceptions noted in NUREG-1339 for safety-related bolting; (3) EPRI TR-104213, Bolted Joint Maintenance and Application Guide, for pressure retaining bolting and structural bolting; and (4) routine examinations and inspections performed in accordance with the requirements of ASME Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components.

15.2.3 Boric Acid Corrosion Prevention Program The Boric Acid Corrosion (BAC) Prevention Program implements administrative controls to (1) perform visual inspections of external surfaces that are potentially exposed to borated water leakage, (2) ensure timely discovery of leak path and removal of the boric acid residues, (3) perform assessments of degradation, and (4) perform follow-up inspections for adequacy of corrective actions. The program is implemented in response to NRC GL 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants.

DSAR-15.2 Information Use Page 4 of 7 Programs and Activities for Rev. 1 Managing the Effects of Aging 15.2.4 Buried Piping and Components Program The Buried Piping and Components Program provides for inspection of buried piping, tanks, and valves whenever they are uncovered due to excavation for maintenance or modifications. Piping and component coatings and wrappings will be inspected for degraded conditions that could be indicative of possible surface corrosion of the protected metal beneath.

The scope and periodicity of inspections is based on NEI-09-14 guidelines and is adjusted based on the inspection results.

15.2.5 Chemistry FCS Chemistry as it applies to the license renewal Aging Management Programs (AMP), controls water chemistry to minimize contaminant concentration and provide chemical additions, such as corrosion inhibitors and biocides, to mitigate aging effects due to corrosion. The activities include specifications for chemical species, limits, representative sampling and analysis frequencies, and corrective actions for control of water chemistry. The activities are based on EPRI Guidelines, and the Closed Cooling Water Chemistry Guideline for closed-cycle cooling water corrosion inhibitor concentration.

15.2.6 Deleted 15.2.7 Deleted 15.2.8 Service Water Reliability Program The Service Water Reliability Program monitors and detects aging effects through inspection and nondestructive evaluations. The program also involves some mitigation activities of periodic flushing and draining. The programs aging management activities are based on EPRI TR-107396, Closed Cooling Water Chemistry Guideline, for closed-cycle cooling water systems and NRC GL 89-13, Service Water System Problems Affecting Safety-Related Equipment, for open-cycle cooling water systems.

DSAR-15.2 Information Use Page 5 of 7 Programs and Activities for Rev. 1 Managing the Effects of Aging 15.2.9 Diesel Fuel Monitoring and Storage FCS Diesel Fuel Monitoring and Storage as it applies to the license renewal AMP monitors and controls diesel fuel quality regarding water and other contaminants in accordance with the guidelines of ASTM Standards D2709, Standard Test Method for Water and Sediment in Middle Distillate Fuels by Centrifuge, and D4057, Standard Practice for Manual Sampling of Petroleum and Petroleum Products. Exposure to fuel oil contaminants such as water and microbiological organisms is minimized by removal of water and sediment from tanks. Exposure to these fuel oil contaminants is further minimized for tanks FO-1, Diesel Engine Fuel Oil Storage Tank, & FO-27, Diesel Fire Pump Fuel Oil Tank, by verifying the quality of new fuel oil before its introduction into the storage tanks.

15.2.10 Deleted 15.2.11 Fire Protection Program The FCS Fire Protection Program provides administrative requirements for ensuring the operability of fire protection equipment required to ensure plant safe shutdown. The program includes visual inspections, system flushing, and performance tests of fire barriers (penetration seals, fire doors, walls, ceilings, and floors), fire suppression system components (piping, valves, nozzles, yard hydrants and hose stations, sprinkler heads, and halon systems and cylinders), and the diesel fire pump. The FCS Fire Protection Program includes the requirements identified in 10 CFR 50.48(f)and is further described in Section 9.11 of the DSAR.

15.2.12 Deleted 15.2.13 General Corrosion of External Surfaces The General Corrosion of External Surfaces Program as it applies to the license renewal AMP, implements systematic inspections and observations to detect corrosion of external surfaces and conditions that can result in corrosion such as damaged coatings and fluid leaks. Inspections and observations include (1) rounds by operators and (2) system engineer walkdowns.

15.2.14 Inservice Inspection Program The Fort Calhoun Station Inservice Inspection Program implements the examination requirements of the ASME Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, Subsections IWB, IWC, IWD, IWF. The program consists of periodic volumetric, surface and/or visual examination of components and their supports for assessment, signs of degradation, and corrective actions. This program is in accordance with ASME Section XI, 1998 edition through the 2000 addenda.

DSAR-15.2 Information Use Page 6 of 7 Programs and Activities for Rev. 1 Managing the Effects of Aging 15.2.15 Cables and Connections Program The FCS Cables and Connections Program is a new program that provides aging management of (1) electrical cables and connections exposed to an adverse localized environment caused by heat, radiation, or moisture; (2) electrical cables used in instrumentation circuits that are sensitive to reduction in conductor insulation resistance, and are exposed to an adverse localized environment caused by heat, radiation, or moisture; and (3) inaccessible medium-voltage cables exposed to an adverse localized environment caused by moisture and voltage exposure.

Aging management is provided by the following actions:

(1) Accessible electrical cables and connections installed in adverse localized environments will be inspected prior to the period of extended operation and at least once every 10 years for cable and connector jacket surface anomalies, such as embrittlement, discoloration, cracking, swelling, or surface contamination.

(2) Electrical cables used in circuits with sensitive, low-level signals, such as radiation monitoring and nuclear instrumentation, are tested as part of the instrumentation loop calibration at the normal calibration frequency.

(3) In-scope medium voltage cables exposed to significant moisture and significant voltage will be tested prior to the period of extended operation and at least once every 10 years to provide an indication of the condition of the conductor insulation. The test will be a state-of-the-art test at the time the test is performed.

This program considers the technical information and guidance provided in NUREG/CR-5643, "Insights Gained from Aging Research;" SAND96-0344, "Aging Management Guidelines for Commercial Nuclear Power Plants-Electrical Cable and Terminations;" EPRI TR-109619, "Guidelines for the Management of Adverse Localized Equipment Environments;" EPRI TR-103834-P1-2.

15.2.16 Deleted 15.2.17 Overhead Loads and Handling Equipment The Overhead Loads and Handling Equipment Program implements FCS commitments made in response to NRC GL 81-07, Control of Heavy Loads at Nuclear Power Plants, and the maintenance monitoring requirements of 10 CFR 50.65. The program includes assessment of crane lift capabilities, periodic inspections of structural components, and functional tests to assure their integrity.

DSAR-15.2 Information Use Page 7 of 7 Programs and Activities for Rev. 1 Managing the Effects of Aging 15.2.18 Periodic Surveillance and Preventive Maintenance Program The Periodic Surveillance and Preventive Maintenance Program requires periodic inspections and examinations of specific system and structural components using established NDE techniques. The inspection and examination techniques used and the periodicity of their performance provide reasonable assurance that age related degradation will not compromise the structure or component intended function(s) before the next scheduled inspection.

15.2.19 Deleted 15.2.20 Deleted 15.2.21 Selective Leaching Program The FCS Selective Leaching Program implements inspection requirements for susceptible components for indication of selective leaching through dezincification or graphitization.

15.2.22 Deleted 15.2.23 Structures Monitoring Program The Structures Monitoring Program provides for periodic visual inspection of designated FCS structures and component supports to ensure that aging degradation will be detected, evaluated, and repaired prior to any loss of intended functions. The inspection requirements are based on the following industry documents: NRC Bulletin 80-11, Masonry Wall Design; NRC IN 87-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-11; NUMARC 93-01, Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants (Line-In/Line-Out Version), Rev. 2; NRC RG 1.160, Monitoring the Effectiveness of Maintenance at Nuclear Power Plants, Rev. 2.

15.2.24 Deleted