|
|
Line 14: |
Line 14: |
| | page count = 5 | | | page count = 5 |
| }} | | }} |
| {{#Wiki_filter:SSINS No.: 6835IN 85-66UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF INSPECTION AND ENFORCEMENTWASHINGTON, D.C. 20555August 7, 1985IE INFORMATION NOTICE NO. 85-66: DISCREPANCIES BETWEEN AS-BUILT CONSTRUCTIONDRAWINGS AND EQUIPMENT INSTALLATIONS | | {{#Wiki_filter:SSINS No.: 6835 IN 85-66 UNITED STATES NUCLEAR REGULATORY |
| | |
| | COMMISSION |
| | |
| | OFFICE OF INSPECTION |
| | |
| | ===AND ENFORCEMENT=== |
| | WASHINGTON, D.C. 20555 August 7, 1985 IE INFORMATION |
| | |
| | NOTICE NO. 85-66: DISCREPANCIES |
| | |
| | BETWEEN AS-BUILT CONSTRUCTION |
| | |
| | DRAWINGS AND EQUIPMENT |
| | |
| | ===INSTALLATIONS=== |
|
| |
|
| ==Addressees== | | ==Addressees== |
| :All nuclear power reactor facilities holding an operating license (OL) or aconstruction permit (CP). | | : |
| | All nuclear power reactor facilities |
| | |
| | holding an operating |
| | |
| | license (OL) or a construction |
| | |
| | permit (CP). |
|
| |
|
| ==Purpose== | | ==Purpose== |
| :This information notice is to alert recipients of a potentially significantgeneric problem regarding as-built construction drawings not correctly orcompletely reflecting equipment installations. Modifications of existinginstallations also may be susceptible to the problems discussed in this infor-mation notice. It is expected that recipients will review the information forapplicability to their facilities and consider actions, if appropriate, topreclude a similar problem occurring at their facilities. However, suggestionscontained in this information notice do not constitute NRC requirements;therefore, no specific action or written response is required. | | : This information |
| | |
| | notice is to alert recipients |
| | |
| | of a potentially |
| | |
| | significant |
| | |
| | generic problem regarding |
| | |
| | as-built construction |
| | |
| | drawings not correctly |
| | |
| | or completely |
| | |
| | reflecting |
| | |
| | equipment |
| | |
| | installations. |
| | |
| | Modifications |
| | |
| | of existing installations |
| | |
| | also may be susceptible |
| | |
| | to the problems discussed |
| | |
| | in this infor-mation notice. It is expected that recipients |
| | |
| | will review the information |
| | |
| | for applicability |
| | |
| | to their facilities |
| | |
| | and consider actions, if appropriate, to preclude a similar problem occurring |
| | |
| | at their facilities. |
| | |
| | ===However, suggestions=== |
| | contained |
| | |
| | in this information |
| | |
| | notice do not constitute |
| | |
| | NRC requirements; |
| | therefore, no specific action or written response is required.Description |
| | |
| | of Circumstances: |
| | Fermi Unit 2 During routine NRC prelicensing |
| | |
| | inspections |
| | |
| | of as-built design and construction |
| | |
| | drawings and specifications |
| | |
| | at Fermi Nuclear Power Plant Unit 2, from April 1984 to October 1984 several discrepancies |
| | |
| | in the electrical |
| | |
| | and instrumenta- tion and control (I&C) installations |
| | |
| | were discovered, which construction |
| | |
| | and preoperational |
| | |
| | testing had not identified. |
| | |
| | In response to the NRC findings at Fermi, the licensee conducted |
| | |
| | an approxi-mately 100 percent reinspection |
| | |
| | of electrical |
| | |
| | and I&C installations. |
| | |
| | That inspection |
| | |
| | effort resulted in the identification |
| | |
| | of over 7300 discrepancies |
| | |
| | and errors between as-built field configurations |
| | |
| | and associated |
| | |
| | design and con-struction |
| | |
| | drawings and specifications. |
| | |
| | There were 154 discrepancies |
| | |
| | which, if left uncorrected, could result in the loss or incorrect |
| | |
| | function of a safety-related |
| | |
| | component |
| | |
| | or system. Examples of these discrepancies |
| | |
| | were wiring errors, unidentified |
| | |
| | jumpers, wrong tubing connections, and wrong installed |
| | |
| | components. |
| | |
| | There were 300 discrepancies |
| | |
| | that had correct design documents |
| | |
| | but incorrect |
| | |
| | installations |
| | |
| | that could impair safe operations. |
| | |
| | 8508050449 IN 85-66 August 7, 1985 Examples of these discrepancies |
| | |
| | were ungrounded |
| | |
| | cable shields, missing hard-ware, and wrong nameplates. |
| | |
| | There were 1900 discrepancies |
| | |
| | which had correct as-built hardware but deficient |
| | |
| | drawings. |
| | |
| | ===Examples of these discrepancies=== |
| | included wiring installed |
| | |
| | that was not shown on the applicable |
| | |
| | drawing, wiring details that differed from the installation |
| | |
| | drawing, and incorrect |
| | |
| | cable numbers on the drawings. |
| | |
| | There were 5000 additional |
| | |
| | minor discrepancies |
| | |
| | which would not have impacted or impaired safe plant operations |
| | |
| | directly such as incorrect |
| | |
| | wire tags, equipment |
| | |
| | layouts that did not match the drawings, and inconsistencies |
| | |
| | in wire tagging methods. Extensive |
| | |
| | actions by the applicant were necessary |
| | |
| | to correct the most significant |
| | |
| | discrepancies |
| | |
| | before an operat-ing license was issued by the NRC.Rancho Seco A reactor coolant system high point vent line addition was made at Rancho Seco during the 1983 refueling |
| | |
| | outage as part of the TMI required modifications. |
| | |
| | Part of the modification |
| | |
| | included adding cross bracing and revising supports for the adjacent nitrogen supply line. Although records indicate this work had been done and inspected |
| | |
| | it had actually not been performed. |
| | |
| | In addition, a removable |
| | |
| | piping spool piece used to isolate the nitrogen supply was not replaced by a rigid piece as required. |
| | |
| | The resulting |
| | |
| | unsupported |
| | |
| | 4 foot length of 1 inch diameter pipe caused a fatigue failure at a high point vent weld resulting |
| | |
| | in a-20-gallon |
| | |
| | per minute non-isolatable |
| | |
| | primary coolant leak. This event is similar to previous discrepancies |
| | |
| | identified |
| | |
| | between the as-built and as-designed |
| | |
| | piping systems at a number of nuclear power plants that led to issuance of IE Bulletin 79-14, "Seismic Analyses for As-Built Safety-Related |
| | |
| | Piping Systems." Resolution |
| | |
| | of the actions requested |
| | |
| | by that bulletin has resulted in extensive |
| | |
| | reanalysis |
| | |
| | and/or modifications |
| | |
| | of piping systems in many nuclear power plants.Construction |
| | |
| | Appraisal |
| | |
| | ===Team Inspections=== |
| | A number of problems with construction |
| | |
| | activities |
| | |
| | which may lead to discrepan- cies between equipment |
| | |
| | installations |
| | |
| | and as-built drawings were identified |
| | |
| | by NRC Construction |
| | |
| | Appraisal |
| | |
| | Team (CAT) inspections |
| | |
| | at 10 facilities |
| | |
| | from Septem-ber 1982 to January 1985.Discussion: |
| | To assure that an adequate level of safety exists or will exist at all nuclear power plants, it is required that all safety related as-built design and construction |
| | |
| | drawings match the plant hardware. |
| | |
| | Requirements |
| | |
| | and measures to control documents |
| | |
| | are identified |
| | |
| | in 10 CFR 50, Appendix B; NUREG-0800, Standard Review Plan, Rev. 2 of Section 17.1; ANSI N45.2-1977, Section 7; and ANSI N.8.7-1976, Section 5.2.15, as applicable. |
| | |
| | IN 85-66 August 7, 1985 No specific action or written response is required by this information |
| | |
| | notice.If you have any questions |
| | |
| | about this matter, please contact the Regional Administrator |
| | |
| | of the appropriate |
| | |
| | regional office or this office.' wad .Jordan, Director Divisi n of Emergency |
| | |
| | ===Preparedness=== |
| | and gineering |
| | |
| | Response Office of Inspection |
| | |
| | and Enforcement |
| | |
| | Technical |
| | |
| | Contact: James C. Stewart, IE (301) 492-9061 Attachments: |
| | 1. Discrepancies |
| | |
| | Identified |
| | |
| | ===During Construction=== |
| | Appraisal |
| | |
| | ===Team Inspections=== |
| | 2. List of Recently Issued IE Information |
| | |
| | Notices |
| | |
| | Attachment |
| | |
| | 1 IN 85-66 August 7, 1985 Discrepancies |
| | |
| | Identified |
| | |
| | During Construction |
| | |
| | Appraisal |
| | |
| | ===Team Inspections=== |
| | During the Braidwood |
| | |
| | CAT inspection |
| | |
| | the NRC team noted a failure to annotate unincorporated |
| | |
| | design changes on controlled |
| | |
| | design documents. |
| | |
| | The most signif-icant finding in this area was design change documents |
| | |
| | written against super-seded revisions |
| | |
| | of the approved drawings; |
| | this resulted in a pipe support being installed |
| | |
| | and inspected |
| | |
| | to other than the latest approved design.Programmatic |
| | |
| | concerns were noted by the NRC team in two areas during the Shearon Harris CAT inspection: |
| | (1) lack of verification |
| | |
| | of piping and pipe support/restraint |
| | |
| | location to original design requirements |
| | |
| | and (2) lack of an ongoing program to effectively |
| | |
| | identify and resolve hardware clearance |
| | |
| | problems early in the construction |
| | |
| | process. Both of these concerns involve practices that could result in extensive |
| | |
| | inspection, analyses, and rework efforts very late in the construction |
| | |
| | schedule.The River Bend CAT inspection |
| | |
| | noted that numerous cable tray supports did not meet the drawing configurations |
| | |
| | that were utilized for determining |
| | |
| | support loading. The applicant |
| | |
| | failed to consider the generic implications |
| | |
| | of identi-fied deficiencies. |
| | |
| | Improper or inadequate |
| | |
| | fastener locking was identified, including |
| | |
| | unbent or missing cotter pins, no staking of threads, loose or missing locknuts, and inadequate |
| | |
| | lock wiring. These deficiencies |
| | |
| | indicated both inadequate |
| | |
| | field quality control (FQC) inspection |
| | |
| | and alteration |
| | |
| | of completed |
| | |
| | and accepted work by construction |
| | |
| | personnel. |
| | |
| | The Nine Mile Point 2 CAT inspection |
| | |
| | identified |
| | |
| | problems in the document control program that indicated |
| | |
| | the crafts and inspectors |
| | |
| | may not have been using the latest design documents |
| | |
| | in the performance |
| | |
| | of their work. Inspection |
| | |
| | reports often did not reflect the drawing revision to which the installation |
| | |
| | was inspected. |
| | |
| | Adding to the document control problem was the high rate of design change initiation |
| | |
| | and the inability |
| | |
| | to maintain and revise construction |
| | |
| | drawings in a timely manner to reflect such changes. The NRC CAT inspectors |
| | |
| | identified |
| | |
| | that over 30 percent of all design change documents |
| | |
| | resulted from errors or inadequate |
| | |
| | information |
| | |
| | provided on previously |
| | |
| | issued changes.Furthermore, rather than taking measures to identify the reasons for the high change notice generation |
| | |
| | rate, a procedural |
| | |
| | requirement |
| | |
| | for incorporation |
| | |
| | of changes in drawings had simply been circumvented |
| | |
| | by the licensee to allow construction |
| | |
| | to continue without timely design change update.The results of the Comanche Peak CAT inspection |
| | |
| | indicated |
| | |
| | a breakdown |
| | |
| | in fabrication, installation, and inspection |
| | |
| | in the HVAC area. The licensee's |
| | |
| | quality assurance |
| | |
| | program had not ensured that certain hanger, support, elec-trical and mechanical |
| | |
| | equipment |
| | |
| | was installed |
| | |
| | to the latest design documents, and commensurately |
| | |
| | that the appropriate |
| | |
| | inspection |
| | |
| | was conducted |
| | |
| | to the latest design documents. |
| | |
| | Attachment |
| | |
| | 2 IN 85-66 August 7, 1985 LIST OF RECENTLY ISSUED IE INFORMATION |
| | |
| | NOTICES Information |
| | |
| | Date of Notice No. Subject Issue Issued to 85-65 85-64 85-63 85-62 Crack Growth In Steam Generator |
| | |
| | Girth Welds 7/31/85 BBC Brown Boveri Low-Voltage |
| | |
| | 7/26/85 K-Line Circuit Breakers, With Deficient |
| | |
| | Overcurrent |
| | |
| | Trip Devices Models OD-4 and 5 Potential |
| | |
| | for Common-Mode |
| | |
| | 7/25/85 Failure of Standby Gas Treat-ment System on Loss of Off-Site Power Backup Telephone |
| | |
| | Numbers to 7/23/85 the NRC Operations |
| | |
| | ===Center All PWR facilities=== |
| | holding an OL or CP All power reactor facilities |
| | |
| | holding an OL or CP All power reactor facilities |
| | |
| | holding an OL or CP All power reactor facilities |
| | |
| | holding an OL and certain fuel facilities |
| | |
| | 85-61 -Misadministrations |
| | |
| | to Patients 7/22/85 Undergoing |
| | |
| | Thyroid Scans All power reactor facilities |
| | |
| | holding an OL and certain fuel facilities |
| | |
| | 85-60 85-59 85-58 85-57 Defective |
| | |
| | Negative Pressure 7/17/85 Air-Purifying, Fuel Facepiece Respirators |
| | |
| | Valve Stem Corrosion |
| | |
| | Failures 7/17/85 Failure Of A General Electric 7/17/85 Type AK-2-25 Reactor Trip Breaker All power reactor facilities |
| | |
| | holding an OL or CP All power reactor facilities |
|
| |
|
| ==Description of Circumstances==
| | holding an OL or CP All power reactor facilities |
| :Fermi Unit 2During routine NRC prelicensing inspections of as-built design and constructiondrawings and specifications at Fermi Nuclear Power Plant Unit 2, from April1984 to October 1984 several discrepancies in the electrical and instrumenta-tion and control (I&C) installations were discovered, which construction andpreoperational testing had not identified.In response to the NRC findings at Fermi, the licensee conducted an approxi-mately 100 percent reinspection of electrical and I&C installations. Thatinspection effort resulted in the identification of over 7300 discrepancies anderrors between as-built field configurations and associated design and con-struction drawings and specifications. There were 154 discrepancies which, ifleft uncorrected, could result in the loss or incorrect function of asafety-related component or system. Examples of these discrepancies werewiring errors, unidentified jumpers, wrong tubing connections, and wronginstalled components. There were 300 discrepancies that had correct designdocuments but incorrect installations that could impair safe operations.8508050449 IN 85-66August 7, 1985 Examples of these discrepancies were ungrounded cable shields, missing hard-ware, and wrong nameplates. There were 1900 discrepancies which had correctas-built hardware but deficient drawings. Examples of these discrepanciesincluded wiring installed that was not shown on the applicable drawing, wiringdetails that differed from the installation drawing, and incorrect cablenumbers on the drawings. There were 5000 additional minor discrepancies whichwould not have impacted or impaired safe plant operations directly such asincorrect wire tags, equipment layouts that did not match the drawings, andinconsistencies in wire tagging methods. Extensive actions by the applicantwere necessary to correct the most significant discrepancies before an operat-ing license was issued by the NRC.Rancho SecoA reactor coolant system high point vent line addition was made at Rancho Secoduring the 1983 refueling outage as part of the TMI required modifications.Part of the modification included adding cross bracing and revising supportsfor the adjacent nitrogen supply line. Although records indicate this work hadbeen done and inspected it had actually not been performed. In addition, aremovable piping spool piece used to isolate the nitrogen supply was notreplaced by a rigid piece as required. The resulting unsupported 4 foot lengthof 1 inch diameter pipe caused a fatigue failure at a high point vent weldresulting in a-20-gallon per minute non-isolatable primary coolant leak. Thisevent is similar to previous discrepancies identified between the as-built andas-designed piping systems at a number of nuclear power plants that led toissuance of IE Bulletin 79-14, "Seismic Analyses for As-Built Safety-RelatedPiping Systems." Resolution of the actions requested by that bulletin hasresulted in extensive reanalysis and/or modifications of piping systems in manynuclear power plants.Construction Appraisal Team InspectionsA number of problems with construction activities which may lead to discrepan-cies between equipment installations and as-built drawings were identified byNRC Construction Appraisal Team (CAT) inspections at 10 facilities from Septem-ber 1982 to January 1985.Discussion:To assure that an adequate level of safety exists or will exist at all nuclearpower plants, it is required that all safety related as-built design andconstruction drawings match the plant hardware. Requirements and measures tocontrol documents are identified in 10 CFR 50, Appendix B; NUREG-0800, StandardReview Plan, Rev. 2 of Section 17.1; ANSI N45.2-1977, Section 7; andANSI N.8.7-1976, Section 5.2.15, as applicable.
| |
|
| |
|
| IN 85-66August 7, 1985 No specific action or written response is required by this information notice.If you have any questions about this matter, please contact the RegionalAdministrator of the appropriate regional office or this office.' wad .Jordan, DirectorDivisi n of Emergency Preparednessand gineering ResponseOffice of Inspection and Enforcement
| | designed by B&W and CE holding an OL or CP All power reactor facilities |
|
| |
|
| ===Technical Contact:===
| | holding an OL or CP; fuel facilities; |
| James C. Stewart, IE(301) 492-9061Attachments:1. Discrepancies Identified During ConstructionAppraisal Team Inspections2. List of Recently Issued IE Information Notices
| | and material licensees Lost Iridium-192 Source Resulting |
|
| |
|
| Attachment 1IN 85-66August 7, 1985 Discrepancies Identified DuringConstruction Appraisal Team InspectionsDuring the Braidwood CAT inspection the NRC team noted a failure to annotateunincorporated design changes on controlled design documents. The most signif-icant finding in this area was design change documents written against super-seded revisions of the approved drawings; this resulted in a pipe support beinginstalled and inspected to other than the latest approved design.Programmatic concerns were noted by the NRC team in two areas during theShearon Harris CAT inspection: (1) lack of verification of piping and pipesupport/restraint location to original design requirements and (2) lack of anongoing program to effectively identify and resolve hardware clearance problemsearly in the construction process. Both of these concerns involve practicesthat could result in extensive inspection, analyses, and rework efforts verylate in the construction schedule.The River Bend CAT inspection noted that numerous cable tray supports did notmeet the drawing configurations that were utilized for determining supportloading. The applicant failed to consider the generic implications of identi-fied deficiencies. Improper or inadequate fastener locking was identified,including unbent or missing cotter pins, no staking of threads, loose ormissing locknuts, and inadequate lock wiring. These deficiencies indicatedboth inadequate field quality control (FQC) inspection and alteration ofcompleted and accepted work by construction personnel.The Nine Mile Point 2 CAT inspection identified problems in the documentcontrol program that indicated the crafts and inspectors may not have beenusing the latest design documents in the performance of their work. Inspectionreports often did not reflect the drawing revision to which the installationwas inspected. Adding to the document control problem was the high rate ofdesign change initiation and the inability to maintain and revise constructiondrawings in a timely manner to reflect such changes. The NRC CAT inspectorsidentified that over 30 percent of all design change documents resulted fromerrors or inadequate information provided on previously issued changes.Furthermore, rather than taking measures to identify the reasons for the highchange notice generation rate, a procedural requirement for incorporation ofchanges in drawings had simply been circumvented by the licensee to allowconstruction to continue without timely design change update.The results of the Comanche Peak CAT inspection indicated a breakdown infabrication, installation, and inspection in the HVAC area. The licensee'squality assurance program had not ensured that certain hanger, support, elec-trical and mechanical equipment was installed to the latest design documents,and commensurately that the appropriate inspection was conducted to the latestdesign documents.
| | In The Death Of Eight Persons In Morocco 7/16/85 OL = Operating |
|
| |
|
| Attachment 2IN 85-66August 7, 1985LIST OF RECENTLY ISSUEDIE INFORMATION NOTICESInformation Date ofNotice No. Subject Issue Issued to85-6585-6485-6385-62Crack Growth In SteamGenerator Girth Welds7/31/85BBC Brown Boveri Low-Voltage 7/26/85K-Line Circuit Breakers, WithDeficient Overcurrent TripDevices Models OD-4 and 5Potential for Common-Mode 7/25/85Failure of Standby Gas Treat-ment System on Loss of Off-Site PowerBackup Telephone Numbers to 7/23/85the NRC Operations CenterAll PWR facilitiesholding an OL or CPAll power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL and certainfuel facilities85-61 -Misadministrations to Patients 7/22/85Undergoing Thyroid ScansAll power reactorfacilities holdingan OL and certainfuel facilities85-6085-5985-5885-57Defective Negative Pressure 7/17/85Air-Purifying, Fuel FacepieceRespiratorsValve Stem Corrosion Failures 7/17/85Failure Of A General Electric 7/17/85Type AK-2-25 Reactor TripBreakerAll power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CPAll power reactorfacilities designedby B&W and CE holdingan OL or CPAll power reactorfacilities holdingan OL or CP; fuelfacilities; andmaterial licenseesLost Iridium-192 SourceResulting In The Death OfEight Persons In Morocco7/16/85OL = Operating LicenseCP = Construction PermitII
| | License CP = Construction |
|
| |
|
| }} | | Permit II}} |
|
| |
|
| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Discrepancies Between As-Built Construction Drawings and Equipment InstallationsML031180224 |
Person / Time |
---|
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, Three Mile Island, 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, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
---|
Issue date: |
08/07/1985 |
---|
From: |
Jordan E L NRC/IE |
---|
To: |
|
---|
References |
---|
IN-85-066, NUDOCS 8508050449 |
Download: ML031180224 (5) |
|
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, Three Mile Island, 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, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
---|
Category:NRC Information Notice
MONTHYEARInformation Notice 2020-02, Flex Diesel Generator Operational Challenges2020-09-15015 September 2020 Flex Diesel Generator Operational Challenges ML20225A0322020-09-0303 September 2020 NRC Choice Letter to NAC International with Attached Safety Inspection Report, IR 0721015/2020201, February 24-27, 2020 and July 22, 2020, Inspection of NAC International in Norcross, Georgia Information Notice 2012-09, PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.2019-11-30030 November 2019 PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs. Information Notice 2011-20, NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011)2019-07-24024 July 2019 NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011) ML19196A2452019-07-15015 July 2019 Public Notice - Sequoyah Nuclear Plant, Unit 2 - Exigent Amendment to Facility Operating License Information Notice 2019-01, Inadequate Evaluation of Temporary Alterations2019-03-12012 March 2019 Inadequate Evaluation of Temporary Alterations ML16028A3082016-04-27027 April 2016 NRC Information Notice; IN 2016-05: Operating Experience Regarding Complications From a Loss of Instrumentation Air Information Notice 2015-05, Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps Information Notice 2015-05, Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps Information Notice 2013-20, OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-20, Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-11, OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2013-11, Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Contain2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Con2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notic2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 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 [[:Three Mile Island]] 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 [[: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 [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>.
[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 [[:Three Mile Island]] 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 [[: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 [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>. |
SSINS No.: 6835 IN 85-66 UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF INSPECTION
AND ENFORCEMENT
WASHINGTON, D.C. 20555 August 7, 1985 IE INFORMATION
NOTICE NO. 85-66: DISCREPANCIES
BETWEEN AS-BUILT CONSTRUCTION
DRAWINGS AND EQUIPMENT
INSTALLATIONS
Addressees
All nuclear power reactor facilities
holding an operating
license (OL) or a construction
permit (CP).
Purpose
- This information
notice is to alert recipients
of a potentially
significant
generic problem regarding
as-built construction
drawings not correctly
or completely
reflecting
equipment
installations.
Modifications
of existing installations
also may be susceptible
to the problems discussed
in this infor-mation notice. It is expected that recipients
will review the information
for applicability
to their facilities
and consider actions, if appropriate, to preclude a similar problem occurring
at their facilities.
However, suggestions
contained
in this information
notice do not constitute
NRC requirements;
therefore, no specific action or written response is required.Description
of Circumstances:
Fermi Unit 2 During routine NRC prelicensing
inspections
of as-built design and construction
drawings and specifications
at Fermi Nuclear Power Plant Unit 2, from April 1984 to October 1984 several discrepancies
in the electrical
and instrumenta- tion and control (I&C) installations
were discovered, which construction
and preoperational
testing had not identified.
In response to the NRC findings at Fermi, the licensee conducted
an approxi-mately 100 percent reinspection
of electrical
and I&C installations.
That inspection
effort resulted in the identification
of over 7300 discrepancies
and errors between as-built field configurations
and associated
design and con-struction
drawings and specifications.
There were 154 discrepancies
which, if left uncorrected, could result in the loss or incorrect
function of a safety-related
component
or system. Examples of these discrepancies
were wiring errors, unidentified
jumpers, wrong tubing connections, and wrong installed
components.
There were 300 discrepancies
that had correct design documents
but incorrect
installations
that could impair safe operations.
8508050449 IN 85-66 August 7, 1985 Examples of these discrepancies
were ungrounded
cable shields, missing hard-ware, and wrong nameplates.
There were 1900 discrepancies
which had correct as-built hardware but deficient
drawings.
Examples of these discrepancies
included wiring installed
that was not shown on the applicable
drawing, wiring details that differed from the installation
drawing, and incorrect
cable numbers on the drawings.
There were 5000 additional
minor discrepancies
which would not have impacted or impaired safe plant operations
directly such as incorrect
wire tags, equipment
layouts that did not match the drawings, and inconsistencies
in wire tagging methods. Extensive
actions by the applicant were necessary
to correct the most significant
discrepancies
before an operat-ing license was issued by the NRC.Rancho Seco A reactor coolant system high point vent line addition was made at Rancho Seco during the 1983 refueling
outage as part of the TMI required modifications.
Part of the modification
included adding cross bracing and revising supports for the adjacent nitrogen supply line. Although records indicate this work had been done and inspected
it had actually not been performed.
In addition, a removable
piping spool piece used to isolate the nitrogen supply was not replaced by a rigid piece as required.
The resulting
unsupported
4 foot length of 1 inch diameter pipe caused a fatigue failure at a high point vent weld resulting
in a-20-gallon
per minute non-isolatable
primary coolant leak. This event is similar to previous discrepancies
identified
between the as-built and as-designed
piping systems at a number of nuclear power plants that led to issuance of IE Bulletin 79-14, "Seismic Analyses for As-Built Safety-Related
Piping Systems." Resolution
of the actions requested
by that bulletin has resulted in extensive
reanalysis
and/or modifications
of piping systems in many nuclear power plants.Construction
Appraisal
Team Inspections
A number of problems with construction
activities
which may lead to discrepan- cies between equipment
installations
and as-built drawings were identified
by NRC Construction
Appraisal
Team (CAT) inspections
at 10 facilities
from Septem-ber 1982 to January 1985.Discussion:
To assure that an adequate level of safety exists or will exist at all nuclear power plants, it is required that all safety related as-built design and construction
drawings match the plant hardware.
Requirements
and measures to control documents
are identified
in 10 CFR 50, Appendix B; NUREG-0800, Standard Review Plan, Rev. 2 of Section 17.1; ANSI N45.2-1977, Section 7; and ANSI N.8.7-1976, Section 5.2.15, as applicable.
IN 85-66 August 7, 1985 No specific action or written response is required by this information
notice.If you have any questions
about this matter, please contact the Regional Administrator
of the appropriate
regional office or this office.' wad .Jordan, Director Divisi n of Emergency
Preparedness
and gineering
Response Office of Inspection
and Enforcement
Technical
Contact: James C. Stewart, IE (301) 492-9061 Attachments:
1. Discrepancies
Identified
During Construction
Appraisal
Team Inspections
2. List of Recently Issued IE Information
Notices
Attachment
1 IN 85-66 August 7, 1985 Discrepancies
Identified
During Construction
Appraisal
Team Inspections
During the Braidwood
CAT inspection
the NRC team noted a failure to annotate unincorporated
design changes on controlled
design documents.
The most signif-icant finding in this area was design change documents
written against super-seded revisions
of the approved drawings;
this resulted in a pipe support being installed
and inspected
to other than the latest approved design.Programmatic
concerns were noted by the NRC team in two areas during the Shearon Harris CAT inspection:
(1) lack of verification
of piping and pipe support/restraint
location to original design requirements
and (2) lack of an ongoing program to effectively
identify and resolve hardware clearance
problems early in the construction
process. Both of these concerns involve practices that could result in extensive
inspection, analyses, and rework efforts very late in the construction
schedule.The River Bend CAT inspection
noted that numerous cable tray supports did not meet the drawing configurations
that were utilized for determining
support loading. The applicant
failed to consider the generic implications
of identi-fied deficiencies.
Improper or inadequate
fastener locking was identified, including
unbent or missing cotter pins, no staking of threads, loose or missing locknuts, and inadequate
lock wiring. These deficiencies
indicated both inadequate
field quality control (FQC) inspection
and alteration
of completed
and accepted work by construction
personnel.
The Nine Mile Point 2 CAT inspection
identified
problems in the document control program that indicated
the crafts and inspectors
may not have been using the latest design documents
in the performance
of their work. Inspection
reports often did not reflect the drawing revision to which the installation
was inspected.
Adding to the document control problem was the high rate of design change initiation
and the inability
to maintain and revise construction
drawings in a timely manner to reflect such changes. The NRC CAT inspectors
identified
that over 30 percent of all design change documents
resulted from errors or inadequate
information
provided on previously
issued changes.Furthermore, rather than taking measures to identify the reasons for the high change notice generation
rate, a procedural
requirement
for incorporation
of changes in drawings had simply been circumvented
by the licensee to allow construction
to continue without timely design change update.The results of the Comanche Peak CAT inspection
indicated
a breakdown
in fabrication, installation, and inspection
in the HVAC area. The licensee's
quality assurance
program had not ensured that certain hanger, support, elec-trical and mechanical
equipment
was installed
to the latest design documents, and commensurately
that the appropriate
inspection
was conducted
to the latest design documents.
Attachment
2 IN 85-66 August 7, 1985 LIST OF RECENTLY ISSUED IE INFORMATION
NOTICES Information
Date of Notice No. Subject Issue Issued to 85-65 85-64 85-63 85-62 Crack Growth In Steam Generator
Girth Welds 7/31/85 BBC Brown Boveri Low-Voltage
7/26/85 K-Line Circuit Breakers, With Deficient
Overcurrent
Trip Devices Models OD-4 and 5 Potential
for Common-Mode
7/25/85 Failure of Standby Gas Treat-ment System on Loss of Off-Site Power Backup Telephone
Numbers to 7/23/85 the NRC Operations
Center All PWR facilities
holding an OL or CP All power reactor facilities
holding an OL or CP All power reactor facilities
holding an OL or CP All power reactor facilities
holding an OL and certain fuel facilities
85-61 -Misadministrations
to Patients 7/22/85 Undergoing
Thyroid Scans All power reactor facilities
holding an OL and certain fuel facilities
85-60 85-59 85-58 85-57 Defective
Negative Pressure 7/17/85 Air-Purifying, Fuel Facepiece Respirators
Valve Stem Corrosion
Failures 7/17/85 Failure Of A General Electric 7/17/85 Type AK-2-25 Reactor Trip Breaker All power reactor facilities
holding an OL or CP All power reactor facilities
holding an OL or CP All power reactor facilities
designed by B&W and CE holding an OL or CP All power reactor facilities
holding an OL or CP; fuel facilities;
and material licensees Lost Iridium-192 Source Resulting
In The Death Of Eight Persons In Morocco 7/16/85 OL = Operating
License CP = Construction
Permit II
|
---|
|
list | - Information Notice 1985-01, Continuous Supervision of Irradiators (10 January 1985)
- Information Notice 1985-02, Improper Installation and Testing of Differential Pressure Transmitters (11 January 1985)
- Information Notice 1985-03, Separation of Primary Reactor Coolant Pump Shaft and Impeller (15 January 1985)
- Information Notice 1985-04, Inadequate Management of Security Response Drills (17 January 1985)
- Information Notice 1985-05, Pipe Whip Restraints (23 January 1985)
- Information Notice 1985-06, Contamination of Breathing Air Systems (23 January 1985)
- Information Notice 1985-07, Contaminated Radiography Source Shipments (29 January 1985)
- Information Notice 1985-08, Industry Experience on Certain Materials Used in Safety-Related Equipment (30 January 1985)
- Information Notice 1985-09, Isolation Transfer Switches and Post-Fire Shutdown Capability (31 January 1985, Topic: Safe Shutdown)
- Information Notice 1985-10, Posttensioned Containment Tendon Anchor Head Failure (6 February 1985)
- Information Notice 1985-11, Licensee Programs for Inspection of Electrical Raceway and Cable Installations (11 February 1985)
- Information Notice 1985-12, Recent Fuel Handling Events (11 February 1985)
- Information Notice 1985-13, Consequences of Using Soluble Dams (21 February 1985, Topic: Hydrostatic)
- Information Notice 1985-14, Failure of a Heavy Control Rod (B4C) Drive Assembly to Insert on a Trip Signal (22 February 1985)
- Information Notice 1985-15, Nonconforming Structural Steel for Safety-Related Use (22 February 1985)
- Information Notice 1985-16, Time/Current Trip Curve Discrepancy of ITE/Siemens-Allis Molded Case Circuit Breaker (27 February 1985)
- Information Notice 1985-17, Possible Sticking of Asco Solenoid Valves (1 March 1985)
- Information Notice 1985-18, Failures of Undervoltage Output Circuit Boards in the Westinghouse-Designed Sold State Protection System (7 March 1985)
- Information Notice 1985-19, Alleged Falsification of Certifications and Alteration of Markings on Piping, Valves, and Fittings (11 March 1985)
- Information Notice 1985-20, Motor-Operated Valve Failures Due to Hampering Effect (12 March 1985)
- Information Notice 1985-21, Main Steam Isolation Valve Closure Logic (18 March 1985)
- Information Notice 1985-22, Failure of Limitorque Motor-Operated Valves Resulting from Incorrect Installation of Pinion Gear (21 March 1985)
- Information Notice 1985-23, Inadequate Surveillance and Postmaintenance and Postmodification System Testing (22 March 1985)
- Information Notice 1985-24, Failures of Protective Coatings in Pipes and Heat Exchangers (26 March 1985, Topic: Ultimate heat sink, Coatings)
- Information Notice 1985-25, Consideration of Thermal Conditions in the Design and Installation of Supports for Diesel Generator Exhaust Silencers (2 April 1985, Topic: Coatings)
- Information Notice 1985-26, Vacuum Relief System for Boiling Water Reactor Mark I and Mark II Containments (2 April 1985, Topic: Coatings)
- Information Notice 1985-27, Notifications to the NRC Operations Center and Reporting Events in Licensee Event Reports (3 April 1985, Topic: Coatings)
- Information Notice 1985-28, Partial Loss of AC Power and Diesel Generator Degradation (9 April 1985, Topic: Coatings)
- Information Notice 1985-30, Microbiologically Induced Corrosion of Containment Service Water System (19 April 1985, Topic: Hydrostatic, Coatings, Biofouling)
- Information Notice 1985-31, Buildup of Enriched Uranium in Ventilation Ducts and Associated Effluent Treatment Systems (19 April 1985, Topic: Coatings)
- Information Notice 1985-32, Recent Engine Failures of Emergency Diesel Generators (22 April 1985, Topic: Coatings)
- Information Notice 1985-33, Undersized Nozzle-To-Shell Welded Joints in Tanks and Heat Exchangers Constructed Under the Rules of the ASME Boiler and Pressure Vessel Code (22 April 1985)
- Information Notice 1985-34, Heat Tracing Contributes to Corrosion Failure of Stainless Steel Piping (30 April 1985, Topic: Hydrostatic)
- Information Notice 1985-35, Failure of Air Check Valves to Seat (30 April 1985)
- Information Notice 1985-35, Failure of Air Check Valves To Seat (30 April 1985)
- Information Notice 1985-37, Chemical Cleaning of Steam Generators at Millstone 2 (14 May 1985)
- Information Notice 1985-38, Loose Parts Obstruct Control Rod Drive Mechanism (21 May 1985)
- Information Notice 1985-39, Auditability of Electrical Equipment Qualification Records at Licensees' Facilities (22 May 1985)
- Information Notice 1985-40, Deficiencies in Equipment Qualification Testing and Certification Process (22 May 1985)
- Information Notice 1985-43, Radiography Events at Power Reactors (30 May 1985, Topic: High Radiation Area, Scaffolding)
- Information Notice 1985-44, Emergency Communication System Monthly Test (30 May 1985, Topic: Health Physics Network)
- Information Notice 1985-46, Clarification of Several Aspects of Removable Radioactive Surface Contamination Limits for Transport Packages (10 June 1985)
- Information Notice 1985-47, Potential Effect of Line-Induced Vibration on Certain Target Rock Solenoid-Operated Valves (18 June 1985)
- Information Notice 1985-48, Respirator Users Notice: Defective Self Contained Breathing Apparatus Air Cylinders (19 June 1985, Topic: Hydrostatic)
- Information Notice 1985-49, Relay Calibration Problem (1 July 1985)
- Information Notice 1985-50, Complete Loss of Main and Auxiliary Feedwater at a PWR Designed by Babcock & Wilcox (8 July 1985)
- Information Notice 1985-51, Inadvertent Loss or Improper Actuation of Safety-Related Equipment (10 July 1985)
- Information Notice 1985-52, Errors in Dose Assessment Computer Codes and Reporting Requirements Under 10 CFR Part 21 (10 July 1985)
- Information Notice 1985-53, Performance of NRC-Licensed Individuals While on Duty (12 July 1985)
- Information Notice 1985-54, Teletherapy Unit Malfunction (15 July 1985)
... further results |
---|