Discrepancies Between As-Built Construction Drawings and Equipment InstallationsML031180224 |
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, 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 |
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Issue date: |
08/07/1985 |
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From: |
Jordan E NRC/IE |
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To: |
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References |
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IN-85-066, NUDOCS 8508050449 |
Download: ML031180224 (5) |
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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, 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 |
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Category:NRC Information Notice
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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 Crack Growth In Steam 7/31/85 All PWR facilities
Generator Girth Welds holding an OL or CP
85-64 BBC Brown Boveri Low-Voltage 7/26/85 All power reactor
K-Line Circuit Breakers, With facilities holding
Deficient Overcurrent Trip an OL or CP
Devices Models OD-4 and 5
85-63 Potential for Common-Mode 7/25/85 All power reactor
Failure of Standby Gas Treat- facilities holding
ment System on Loss of Off- an OL or CP
Site Power
85-62 Backup Telephone Numbers to 7/23/85 All power reactor
the NRC Operations Center facilities holding
an OL and certain
fuel facilities
85-61 - Misadministrations to Patients 7/22/85 All power reactor
Undergoing Thyroid Scans facilities holding
an OL and certain
fuel facilities
85-60 Defective Negative Pressure 7/17/85 All power reactor
Air-Purifying, Fuel Facepiece facilities holding
Respirators an OL or CP
85-59 Valve Stem Corrosion Failures 7/17/85 All power reactor
facilities holding
an OL or CP
85-58 Failure Of A General Electric 7/17/85 All power reactor
Type AK-2-25 Reactor Trip facilities designed
Breaker by B&W and CE holding
an OL or CP
85-57 Lost Iridium-192 Source 7/16/85 All power reactor
Resulting In The Death Of facilities holding
Eight Persons In Morocco an OL or CP; fuel
facilities; and
material licensees
OL = Operating License
CP = Construction Permit
II
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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)
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