Recognition of American Society of Mechanical Engineers Accreditation Program for N Stamp Holders ML031220635 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 , 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 , 05000000 , Zimmer , Fort Saint Vrain , Shoreham , Satsop , Trojan , Atlantic Nuclear Power Plant , Skagit , Marble Hill , Crane Issue date:
03/31/1986 From:
Jordan E NRC/IE To:
References IN-86-021 , NUDOCS 8603260277Download: ML031220635 (5)
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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 ,
05000000 ,
Zimmer ,
Fort Saint Vrain ,
Shoreham ,
Satsop ,
Trojan ,
Atlantic Nuclear Power Plant ,
Skagit ,
Marble Hill ,
Crane 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 [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] OR [[:Crane]] </code>.
USORGIAL
SSINS No.: 6835 IN 86-21
Contents
1 UNITED STATES
2 OFFICE OF INSPECTION AND ENFORCEMENT
3 March 31, 1986
4 RECOGNITION OF AMERICAN SOCIETY OF
5 PROGRAM FOR N STAMP HOLDERS
6 Addressees
7 Purpose
7.1 It is expected that recipients
7.2 The primary reasons for
7.3 On this basis, the NRC has sent letters
7.4 In accordance with the Exchange of
7.5 Licensees and their subcontractors, when
7.6 They are reminded
7.7 Licensees, construction permit
7.8 Engi eering Response
7.9 E. T. Baker, IE
7.10 G. G. Zech, IE
7.11 Attachment 1
7.12 March 31, 1986
7.13 NUCLEAR REGULATORY COMMISSION
7.14 March 18. 1986
7.15 Codes and Standards
7.16 Enclosed is a copy of the information
7.17 Information Notice
7.18 Attachment 1
7.19 March 31, 1986
7.20 NUCLEAR REGULATORY COMMISSION
7.21 March 18, 1986
7.22 Columbus, Ohio 43229
7.23 Enclosed is a copy of the information
7.24 Information Notice
7.25 Attachment 2
7.26 March 31, 1986
7.27 IE INFORMATION NOTICES
7.28 Scaling Factors, 10 CFR
7.29 Reactor Coolant Pump Shaft
7.30 A Major Emergency
7.31 Local Testing Of BWR Vacuum
7.32 All power reactor
7.33 All power reactor
7.34 All power reactor
7.35 All power reactor
7.36 All power reactor
7.37 All power reactor
7.38 All power reactor
7.39 All BWR facilities
7.40 All power reactor
7.41 All power reactor
7.42 Loss Of Offsite Power Caused
7.43 PWR Auxiliary Feedwater Pump
7.44 Standby Liquid Control
7.45 Setpoint Drift
7.46 Protection Against Core Melt
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON , D.C.
20555
March 31, 1986
IE INFORMATION NOTICE NO. 86-21:
RECOGNITION OF AMERICAN SOCIETY OF
MECHANICAL ENGINEERS ACCREDITATION
PROGRAM FOR N STAMP HOLDERS
Addressees
All nuclear power facilities holding an operating license (OL ) or a construction
permit (CP ) and all recipients of NUREG-0040 (white book).
Purpose
This information notice is provided to licensees, construction permit holders, and vendors to inform them of the NRC's recognition of the American Society of
Mechanical Engineers (ASME ) Accreditation Program for holders of N, NPT, NA,
and NV stamps and Certificates of Authorization.
It is expected that recipients
will review the information for applicability to their facilities.
However, suggestions contained in this information notice do not constitute NRC
requirements; therefore, no specific action or written response is required.
Discussion:
In March 1981, representatives of the NRC, ASME , and the National Board of
Boiler and Pressure Vessel Inspectors (NB) signed an Exchange of Correspondence
that outlined an agreement to work toward establishing a single set of quality
requirements and recognition by the NRC of ASME 's Accreditation Program for N,
NA, NPT, and NV stamps and the associated Certificates of Authorization.
Quality System Certificates issued to Material Manufacturers (MM) and Material
Suppliers (MS) are excluded from this recognition.
The primary reasons for
developing the Exchange of Correspondence were to eliminate overlapping require- ments and to allow NRC licensees and their subcontractors to use the results of
the ASME/NB nuclear accreditation and inspection system as an acceptable method
for satisfying NRC requirements for evaluating the programmatic adequacy of
their suppliers' documented quality assurance (QA ) programs.
In a meeting on December 10, 1985, representatives of the NRC, NB, and ASME
agreed that based on the requirements contained in the 1986 Edition of the ASME
Boiler and Pressure Vessel Code all of the conditions established in the
Exchange of Correspondence as prerequisites for NRC recognition of the
Accreditation Program had been met.
On this basis, the NRC has sent letters
(see attached) to the National Board and ASME recognizing the holding of an
8603260277
IN 86-21_
March 31, 1986 ASME N, NA, NPT or NV Certificate of Authorization as evidence that the holder
of the Certificate of Authorization has a documented QA program that meets the
requirements of Appendix B to 10 CFR 50 .
In accordance with the Exchange of
Correspondence, the NRC will make the appropriate changes to Regulatory Guides
1.28 and 1.33 in the next revision.
Licensees and their subcontractors, when
assessing whether a potential supplier has an acceptable documented QA program, may rely on the fact that ASME has surveyed the supplier and issued a Certificate
of Authorization of appropriate scope and for the desired location without
performing any additional evaluation of the supplier's QA program.
Licensees and construction permit holders that take credit for the ASME
Accreditation Program may have to revise their QA Program.
They are reminded
that 10 CFR 50.54(a)(3) and 50.55(f)(3) set forth the requirements for making
changes to QA programs.
It should be noted that NRC's recognition applies only to the programmatic
aspects of the ASME Accreditation Program.
Licensees, construction permit
holders, and their subcontractors are still responsible for ensuring that the
supplier is effectively implementing the approved QA program.
No specific action or response is required by this information notice.
If you
have any questions regarding this notice, please contact the Regional
Administrator of the appropriate NRC regional office or the technical contact
listed below.
d a
rector
Divisi
of Emergency Preparedness and
Engi eering Response
Office of Inspection and Enforcement
Technical Contacts:
E. T. Baker, IE
301-492-4874
G. G. Zech, IE
301-492-9663 Attachments:
1. Letter to ASME
2. List of Recently Issued IE Information Notices
Attachment 1
IN 86-21
March 31, 1986
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON , 0 C 20555
March 18. 1986
Mr. Melvin R. Green, Managing Director
Codes and Standards
American Society of Mechanical Engineers
345 East 47th Street
New York , New York
10017 Dear Mr. Green:
SUBJECT:
NRC ENDORSEMENT OF ASME 'S ACCREDITATION PROGRAM
At the December 10, 1985 meeting of the NRC/ASME/NB Coordinating Committee it
was agreed that all conditions established in the Exchange of Correspondence
as prerequisites for NRC recognition and endorsement of the ASME Accreditation
Program had been met. At that meeting it was also agreed that the NRC would
publish an information notice communicating the NRC's recognition and endorse- ment of the Accreditation Program.
Enclosed is a copy of the information
notice which is being sent to all licensees and to other parties on the
information notice distribution list.
Sincerely,
, Director
ction and Enforcement
Enclosure:
Information Notice
ctot RECU
0
Attachment 1
IN 86-21
March 31, 1986
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON , D C 20555
March 18, 1986
Mr. Donald J. McDonald, Executive Director
National Board of Boiler & Pressure Vessel
Inspectors
1055 Crapper Avenue
Columbus, Ohio 43229
Dear Mr. McDonald:
SUBJECT:
NRC ENDORSEMENT OF ASME 'S ACCREDITATION PROGRAM
At the December 10, 1985 meeting of the NRC/ASME/NB Coordinating Committee it
was agreed that all conditions established in the Exchange of Correspondence
as prerequisites for NRC recognition and endorsement of the ASME Accreditation
Program had been met. At that meeting it was also agreed that the NRC would
publish an information notice communicating the NRC's recognition and endorse- ment of the Accreditation Program.
Enclosed is a copy of the information
notice which is being sent to all licensees and to other parties on the
information notice distribution list.
Sincerely, nspection and Enforcement
Enclosure:
Information Notice
-
V
Attachment 2
IN 86-21
March 31, 1986
LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issue
Issued to
86-20
86-19
86-18
86-17
86-16
86-15
86-14
86-13
86-12
86-11 Low-Level Radioactive Waste
Scaling Factors, 10 CFR
Part 61
Reactor Coolant Pump Shaft
Failure At Crystal River
NRC On-Scene Response During
A Major Emergency
Update Of Failure Of Auto- matic Sprinkler System Valves
To Operate
3/28/86
3/21/86
3/26/86
3/24/86 Failures To Identify Contain- 3/11/86 ment Leakage Due To Inadequate
Local Testing Of BWR Vacuum
Relief System Valves
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 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 or CP
All power reactor
facilities holding
an OL or CP
All BWR facilities
holding an OL or CP
All power reactor
facilities holding
an OL or CP
All power reactor
facilities holding
an OL or CP
Loss Of Offsite Power Caused
By Problems In Fiber Optics
Systems
Turbine Control Problems
Standby Liquid Control
System Squib Valves Failure
To Fire
Target Rock Two-Stage SRV
Setpoint Drift
Inadequate Service Water
Protection Against Core Melt
Frequency
3/10/86
3/10/86
2/21/86
2/25/86
2/25/86 OL = Operating License
CP = Construction Permit
list Information Notice 1986-01, Failure of Main Feedwater Check Valves Causes Loss of Feedwater System Integrity and Water-Hammer Damage (6 January 1986 , Topic : Feedwater Heater )Information Notice 1986-02, Failure of Valve Operator Motor During Environmental Qualification Testing (6 January 1986 )Information Notice 1986-03, Potential Deficiencies in Enviromental Qualification of Limitorque Motor Valve Operator Wiring (14 January 1986 )Information Notice 1986-04, Transient Due to Loss of Power to Intergrated Control System at a Pressurized Water Reactor Designed by Babcock & Wilcox (31 January 1986 )Information Notice 1986-05, Main Steam Safety Valve Test Failures and Ring Setting Adjustments (31 January 1986 )Information Notice 1986-06, Failure of Lifting Rig Attachment, While Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986 , Topic : Control of Heavy Loads )Information Notice 1986-06, Failure of Lifting Rig Attachment, while Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986 )Information Notice 1986-07, Lack of Detailed Instruction & Inadequate Observance of Precautions During Maintenance & Testing of Diesel Generator Woodward Governors (3 February 1986 , Topic : Overspeed trip , Overspeed )Information Notice 1986-08, Licensee Event Report (LER) Format Modification (3 February 1986 , Topic : GOTHIC )Information Notice 1986-09, Failure of Check & Stop Check Valves Subjected to Low Flow Conditions (3 February 1986 )Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. (5 January 1995 , Topic : Boric Acid , Stress corrosion cracking )Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion (5 January 1995 , Topic : Boric Acid , Stress corrosion cracking )Information Notice 1986-10, Feedwater Line Break (10 November 1988 , Topic : Coatings , Anchor Darling )Information Notice 1986-11, Anomalous Behavior of Recirculation Loop Flow in Jet Pump BWR Plants (31 December 1986 )Information Notice 1986-13, Standby Liquid Control Squib Valves Failure to Fire (5 August 1986 , Topic : Squib )Information Notice 1986-13, Standby Liquid Control System Squib Valves Failure to Fire (21 February 1986 , Topic : Squib )Information Notice 1986-14, Overspeed Trips of Afw, HPCI & RCIC Turbines (26 August 1991 , Topic : Overspeed trip , Overspeed )Information Notice 1986-14, Overspeed Trips of AFW, HPCI & RCIC Turbines (26 August 1991 , Topic : Overspeed trip , Overspeed )Information Notice 1986-15, Loss of Offsite Power Caused by Problems in Fiber Optics Systems (10 March 1986 , Topic : Squib , Loss of Offsite Power )Information Notice 1986-16, Failures to Identify Containment Leakage Due to Inadequate Local Testing of BWR Vacuum Relief System Valves (11 March 1986 , Topic : Squib , Local Leak Rate Testing , Integrated leak rate test )Information Notice 1986-17, Update of Failure of Automatic Sprinkler System Valves to Operate (24 March 1986 , Topic : Squib )Information Notice 1986-18, NRC On-Scene Response During a Major Emergency (26 March 1986 , Topic : Squib , Backfit )Information Notice 1986-19, Reactor Coolant Pump Shaft Failure at Crystal River (21 March 1986 , Topic : Squib )Information Notice 1986-20, Low-Level Radioactive Waste Scaling Factors, 10 CFR Part 61 (28 March 1986 , Topic : Squib )Information Notice 1986-21, Recognition of American Society of Mechanical Engineers Accreditation Program for N Stamp Holders (31 March 1986 , Topic : Squib )Information Notice 1986-22, Underresponse of Radiation Survey Instrument to High Radiation Fields (31 March 1986 , Topic : High Radiation Area , Squib )Information Notice 1986-23, Excessive Skin Exposures Due to Contamination with Hot Particles (9 April 1986 , Topic : Loss of Offsite Power )Information Notice 1986-23, Excessive Skin Exposures due to Contamination with Hot Particles (9 April 1986 , Topic : Loss of Offsite Power )Information Notice 1986-24, Respirator Users Notice: Increased Inspection Frequency for Certain Self-Contained Breathing Apparatus Air Cylinders (11 April 1986 , Topic : Hydrostatic )Information Notice 1986-25, Traceability and Material Control of Material and Equipment, Particularly Fasteners (11 April 1986 )Information Notice 1986-26, Potential Problems in Generators Manufactured by Electrical Products Incorporated (17 April 1986 )Information Notice 1986-27, Access Control at Nuclear Facilities (21 April 1986 , Topic : Contraband )Information Notice 1986-28, Telephone Numbers to the NRC Operations Center and Regional Offices (24 April 1986 )Information Notice 1986-29, Effects of Changing Valve Moter-Operator Switch Settings (25 April 1986 )Information Notice 1986-30, Design Limitations of Gaseous Effluent Monitoring Systems (29 April 1986 )Information Notice 1986-31, Unauthorized Transfer and Loss of Control of Industrial Nuclear Gauges (14 July 1986 )Information Notice 1986-32, Request for Collection of Licensee Radioactivity Measurements Attributed to Chernobyl Nuclear Plant Accident (2 May 1986 , Topic : Chernobyl , Potassium iodide )Information Notice 1986-33, Information for Licensee Regarding the Chernobyl Nuclear Plant Accident (6 May 1986 , Topic : Chernobyl , Potassium iodide )Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & their Actuators (13 May 1986 )Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & Their Actuators (13 May 1986 )Information Notice 1986-35, Fire in Compressible Material at Dresden Unit 3 (15 May 1986 , Topic : Chernobyl )Information Notice 1986-36, Change in NRC Practice Regarding Issuance of Confirming Letters to Principal Contractors (16 May 1986 , Topic : Chernobyl )Information Notice 1986-37, Degradation of Station Batteries (16 May 1986 , Topic : Chernobyl )Information Notice 1986-38, Deficient Operator Actions Following Dual Function Valve Failures (20 May 1986 , Topic : Chernobyl )Information Notice 1986-39, Failures of RHR Pump Motors and Pump Internals (20 May 1986 , Topic : Chernobyl )Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in Bwrs (5 June 1986 , Topic : Chernobyl )Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in BWRs (5 June 1986 , Topic : Chernobyl )Information Notice 1986-41, Evaluation of Questionable Exposure Readings of Licensee Personnel Dosimeters (9 June 1986 , Topic : Chernobyl )Information Notice 1986-42, Improper Maintenance of Radiation Monitoring Systems (9 June 1986 , Topic : Temporary Modification , Chernobyl )Information Notice 1986-43, Problems with Silver Zeolite Sampling of Airborne Radioiodine (10 June 1986 , Topic : Chernobyl )... further results