Containment Inspection Rule| ML031060003 |
| Person / Time |
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| Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane  |
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| Issue date: |
05/30/1997 |
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| From: |
Slosson M M Office of Nuclear Reactor Regulation |
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| To: |
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| References |
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| IN-97-029, NUDOCS 9705290064 |
| Download: ML031060003 (9) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane |
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Category:NRC Information Notice
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Crane]] </code>. |
K)UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555-0001May 30, 1997NRC INFORMATION NOTICE 97-29: CONTAINMENT INSPECTION RULE
Addressees
All holders of operating licenses or construction permits for nuclear power reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to clarifyfor addressees the containment inspection rule in accordance with 10 CFR 50.55a(a), whichin part endorses Subsections IWE and IWL of Section Xl of the American Society ofMechanical Engineers' Boiler and Pressure Vessel Code (ASME Code). The rule becameeffective on September 9, 1996. It is expected that recipients will review the information forapplicability to their facilities and consider actions, as appropriate. However, suggestionscontained in this information notice are not NRC requirements; therefore, no specific action orwritten response is required.
Description of Circumstances
In a Federal Register, dated August 8, 1996 (61 FR 41303), the NRC amended itsregulations (rule) to incorporate by reference the 1992 Edition and Addenda ofSubsections IWE and IWL of Section Xl of the ASME Code. Subsections IWE and IWL givethe requirements for inservice inspection (ISI) of Class CC (concrete containments), andClass MC (metallic containments) of light-water-cooled power plants. The amended rulebecame effective on September 9, 1996; it requires the licensees to incorporate the newrequirements into their ISI plans and to complete the first containment inspection within fiveyears (i.e., no later than September 9, 2001). Any repair or replacement (RIR) activity to beperformed on containments after the effective date of September 9, 1996, has to be carriedout in accordance with the respective requirements of Subsections IWE and IWL.Recognizing the potential industry concern related to the immediate implementation of therule for R/R activities, the Nuclear Energy Institute (NEI) wrote a letter to NRC (Reference 1)indicating a general industry interpretation of the rule that all containment ISI activities,including R/R activities should be effective from September 9, 2001. The NRC responded tothe NEI letter (Reference 2) stating that all R/R activities within the scope of Subsections IWEand IWL of the code conducted after September 9, 1996, must be conducted in accordancewith these subsectio#WO°& l o9 7-O49 970t-S 10,004 6 1-M O Pll_________________l_ qC.-
IN 97-29May 30, 1997 Additionally, the staff stated (Reference 2) that 10 CFR 50.55a(3) permits the Director of theOffice of Nuclear Reactor Regulation at his discretion to grant relief from the requirements of10 CFR 50.55a to licensees who submit a justifiable need to use an alternative that providesan acceptable level of safety or who encounter extreme hardship or unusual difficulty withouta compensating increase in the level of quality or safety. In general, the staff stated that withproper justification, relief requests from compliance with the RJR requirements of SubsectionsIWE and IWL for a period of about one year from September 9, 1996, would appear to bereasonable.Although NEI sent the response from NRC to many of the addressees, the NRC staff isissuing this information notice to inform all addressees about the NRC staff position.DiscussionAs discussed above, addressees are required to implement the rule for all containment-related R/R activities to be conducted after September 9, 1996. Even though a licensee isable to demonstrate hardship or unusual difficulties in the immediate implementation of therule, the licensee has to demonstrate that other procedures utilized for R/R activities willensure adequate safety of the containments and that proper quality assurance requirementshave been implemented.In some of the relief requests that the staff has reviewed, licensees have reportedappropriate "hardship and unusual difficulties" reasons for postponing the implementation ofthe rule, but did not describe the effectiveness of the procedures they plan to use during therelief period. Without such information, the staff has no way of concluding that the qualityand safety of containment RIR activities are adequate.
K> IN 97-29May 30, 1997 This information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact the technical contacts listedbelow or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.Marylee M. Slosson, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts: Seung Lee, NRR301-415-2737E-mail: sjl@nrc.govHans Ashar, NRR301-415-2851E-mail: hgaenrc.govReferences1. Letter from Alex Marion (NEI) to Brian Sheron (NRC), "Interpretation ofAmended 10 CFR 50.55a," dated 09119/96 (Accession No. 9704180074).2. Letter from Gus Lainas (NRC) to Alex Marion (NEI), "Implementation ofContainment Inspection Rule," dated 11/06/96 (Accession No. 9611130161).Attachment: List of Recently Issued NRC Information Noticeskit C- i4"( & p a
AttachmentIN 97-29May 30, 1997 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to97-2897-27Elimination of InstrumentResponse Time TestingUnder the Requirements of10 CFR 50.59Effect of IncorrectStrainer Pressure Dropon Available Net PositiveSuction HeadDegradation in Small-Radius U-Bend Regionsof Steam Generator Tubes05/30/9705/16/9705/19/97All holders of OLs or CPsAll holders of OLs or CPsfor light-water powerreactors, except thoselicensees who have per-manently ceased operationsand have certified thatfuel has been permanentlyremoved from the reactorvesselAll holders of OLs or CPsfor pressurized-waterreactors97-2687-10,Sup. 1Potential for WaterHammer During Restart ofResidual Heat RemovalPumpsDynamic Range Uncertain-ties in the Reactor VesselLevel Instrumentation05/15/9705/09/97All holders of OLs or CPsfor boiling-water reactorsAll holders of OLs or CPsfor Westinghouse pressurized-water reactors97-25OL = Operating LicenseCP = Construction Permit
IN 97-29May 30, 1997 IN 97-XXMay XX, 1997 This information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact the technical contacts listedbelow or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.Marylee M. Slosson, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts:Seung Lee, NRR(301) 415-2737E-mail: sjl~nrc.govHans Ashar, NRR(301) 415-2851E-mail: hga~nrc.govReferences1. Letter from Alex Marion (NEI) to Brian Sheron (NRC), "Interpretation ofAmended 10 CFR 50.55a," dated 09/19/96 (Accession No. 9704180074).2. Letter from Gus Lainas (NRC) to Alex Marion (NEI), "Implementation ofContainment Inspection Rule," dated 11/06/96 (Accession No. 9611130161).Attachment: List of Recently Issued NRC Information NoticesOFC PECB:DRPM ECGB:DE CIECGB:DE OGCNAME T. Greene* S. Lee* G. Bagchi* S. Treby*DATE 04/22/97 04/22/97 04/24/97 05/06/97See previous concurrenceOFC CIPECB:DRPM AD/DRPK 1NAME A. Chaffee6W M. Slosson XDATE ij/197 /97OFFICIAL RECORD 51 97DOCUMENT NAME: GATAGXINCONT
K> uIN 97-XXMay XX, 1997 DOCUMENT NAME: G:\TAGXINCONT
IN 97-XXApril XX, 1997 DOCUMENT NAME: G:\TAG\INCONT
IN 97-XXApril XX, 1997 ]DOCUMENT NAME: G:ITAGUNCONT
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| list | - Information Notice 1997-01, Improper Electrical Grounding Results in Simultaneous Fires in the Control Room and the Safe-Shutdown Equipment Room (8 January 1997, Topic: Safe Shutdown, Emergency Lighting)
- Information Notice 1997-02, Cracks Found in Jet Pump Riser Assembly Elbows at Boiling Water Reactors (6 February 1997, Topic: Intergranular Stress Corrosion Cracking)
- Information Notice 1997-03, Defacing of Labels to Comply with 10 CFR 20.1904(b) (20 February 1997)
- Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents (24 February 1997, Topic: Notice of Violation, Backfit)
- Information Notice 1997-05, Offsite Notification Capabilities (27 February 1997, Topic: Earthquake)
- Information Notice 1997-06, Weaknesses in Plant-Specific Emergency Operating Procedures for Refilling the Secondary Side of Dry Once-Through Steam Generators (4 March 1997)
- Information Notice 1997-07, Problems Identified During Generic Letter 89-10 Closeout Inspections (6 March 1997, Topic: Hot Short, Safe Shutdown, Weak link)
- Information Notice 1997-08, Potential Failures of General Electric Magne-Blast Circuit Breaker Subcomponents (12 March 1997, Topic: Coatings, Weak link)
- Information Notice 1997-09, Inadequate Main Steam Safety Valve (MSSV) Setpoints and Performance Issues Associated with Long MSSV Inlet Piping (12 March 1997)
- Information Notice 1997-10, Liner Plate Corrosion in Concrete Containments (13 March 1997)
- Information Notice 1997-11, Cement Erosion from Containment Subfoundations at Nuclear Power Plants (21 March 1997)
- Information Notice 1997-12, Potential Armature Binding in General Electric Type HGA Relays (24 March 1997, Topic: Basic Component)
- Information Notice 1997-13, Deficient Conditions Associated with Protective Coatings at Nuclear Power Plants (24 March 1997, Topic: Coatings)
- Information Notice 1997-14, Assessment of Spent Fuel Pool Cooling (28 March 1997, Topic: Time to boil, Coatings, Loss of Offsite Power)
- Information Notice 1997-15, Reporting of Errors and Changes in Large-Break Loss-of-Coolant Accident Evaluation Models of Fuel Vendors and Compliance with 10 CFR 50. 46(a)(3) (4 April 1997, Topic: Coatings, Fuel cladding)
- Information Notice 1997-16, Preconditioning of Plant Structures, Systems, and Components Before ASME Code Inservice Testing or Technical Specification Surveillance Testing (4 April 1997, Topic: Stroke time, Coatings)
- Information Notice 1997-17, Cracking of Vertical Welds in the Core Shroud and Degraded Repair (4 April 1997, Topic: Coatings, Intergranular Stress Corrosion Cracking)
- Information Notice 1997-18, Problems Identified During Maintenance Rule Baseline Inspections (14 April 1997, Topic: Probabilistic Risk Assessment, Coatings, Emergency Lighting)
- Information Notice 1997-19, Safety Injection System Weld Flaw at Sequcyah Nuclear Power Plant, Unit 2 (18 April 1997, Topic: Boric Acid, Thermal fatigue)
- Information Notice 1997-20, Identification of Certain Uranium Hexafluoride Cylinders That Do Not Comply with ANSI N14.1 Fabrication Standards (17 April 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-21, Availability of Alternate AC Power Source Designed for Station Blackout Event (18 April 1997, Topic: Main transformer failure, Loss of Offsite Power)
- Information Notice 1997-22, Failure of Welded-Steel Moment Resisting Frames During Northridge Earthquake (25 April 1997, Topic: Earthquake)
- Information Notice 1997-23, Evaluation and Reporting of Fires and Unplanned Chemical Reaction Events at Fuel Cycle Facilities (7 May 1997, Topic: Earthquake, Uranium Hexafluoride)
- Information Notice 1997-24, Failure of Packing Nuts on One-Inch Uranium Hexafluoride Cylinder Valves (8 May 1997, Topic: Eddy Current Testing, Uranium Hexafluoride)
- Information Notice 1997-25, Dynamic Range Uncertainties in the Reactor Vessel Level Instrumentation (9 May 1997, Topic: Earthquake)
- Information Notice 1997-26, Degradation in Small-Radius U-Bend Regions of Steam Generator Tubes (19 May 1997, Topic: Eddy Current Testing, Earthquake)
- Information Notice 1997-27, Effect of Incorrect Strainer Pressure Drop on Available Net Positive Suction Head (16 May 1997, Topic: Earthquake)
- Information Notice 1997-28, Elimination of Instrument Response Time Testing Under the Requirements of 10 CFR 50.59 (30 May 1997, Topic: Enforcement Discretion)
- Information Notice 1997-29, Containment Inspection Rule (30 May 1997)
- Information Notice 1997-30, Control of Licensed Material During Reorganizations, Employee-Management Disagreements, and Financial Crises (3 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-31, Failures of Reactor Coolant Pump Thermal Barriers and Check Valves in Foreign Plants (3 June 1997)
- Information Notice 1997-32, Defective Worm Shaft Clutch Gears in Limitorque Motor-Operated Valve Actuators (10 June 1997)
- Information Notice 1997-33, Unanticipated Effect of Ventilation System on Tank Level Indications and Engineering Safety Features Actuation System Setpoint (11 June 1997)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels In Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (Inc) IR100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (INC) Ir100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-36, Unplanned Intakes by Worker of Transuranic Airborne Radioactive Materials and External Exposure Due to Inadequate Control of Work (20 June 1997, Topic: Overexposure)
- Information Notice 1997-37, Main Transformer Fault with Ensuing Oil Spill Into Turbine Building (20 June 1997, Topic: Loss of Offsite Power)
- Information Notice 1997-38, Level-Sensing System Initiates Common-Mode Faulure of High-Pressure-Injection Pumps (24 June 1997, Topic: Hydrostatic)
- Information Notice 1997-39, Inadequate 10 CFR 72.48 Safety Evaluations of Independent Spent Fuel Storage Installations (26 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-40, Potential Nitrogen Accumulation Resulting from Backleakage from Safety Injection Tanks (26 June 1997, Topic: Gas accumulation)
- Information Notice 1997-41, Revised - Potentially Undersized Emergency Diesel Generator (EDG) Oil Coolers (27 June 1997)
- Information Notice 1997-42, Management Weaknesses Resulting in Failure to Comply with Shipping Requirements for Special Nuclear Material (27 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-43, License Condition Compliance (1 July 1997, Topic: Ultimate heat sink)
- Information Notice 1997-44, Failures of Gamma Metrics Wide-Range Linear Neutron Flux Channels (1 July 1997)
- Information Notice 1997-45, Environmental Qualification Deficiency for Cables & Containment Penetration Pigtails (2 July 1997)
- Information Notice 1997-46, Unisolable Crack in High-Pressure Injection Piping (9 July 1997, Topic: Flow Induced Vibration)
- Information Notice 1997-47, Inadequate Puncture Tests for Type B Packages Under 10 CFR 71.73(c)(3) (27 June 1997)
- Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures (9 July 1997, Topic: Safe Shutdown, Unanalyzed Condition, Fire Barrier, Emergency Lighting, Operability Determination, Continuous fire watch, Fire Protection Program, Fire Watch)
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