Information Notice 1986-21, Recognition of American Society of Mechanical Engineers Accreditation Program for N Stamp Holders: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
Line 16: Line 16:
{{#Wiki_filter:USORGIAL
{{#Wiki_filter:USORGIAL


UNITED STATES
SSINS No.: 6835 IN 86-21
 
===UNITED STATES===
NUCLEAR REGULATORY COMMISSION


SSINS  No.: 6835 IN 86-21 NUCLEAR REGULATORY COMMISSION
===OFFICE OF INSPECTION AND ENFORCEMENT===
WASHINGTON, D.C.


OFFICE OF INSPECTION AND ENFORCEMENT
20555


WASHINGTON, D.C. 20555 March 31, 1986 IE INFORMATION NOTICE NO. 86-21:   RECOGNITION OF AMERICAN SOCIETY OF
===March 31, 1986===
IE INFORMATION NOTICE NO. 86-21:  


===RECOGNITION OF AMERICAN SOCIETY OF===
MECHANICAL ENGINEERS ACCREDITATION
MECHANICAL ENGINEERS ACCREDITATION


PROGRAM FOR N STAMP HOLDERS
===PROGRAM FOR N STAMP HOLDERS===


==Addressees==
==Addressees==
Line 39: Line 45:


Mechanical Engineers (ASME) Accreditation Program for holders of N, NPT, NA,
Mechanical Engineers (ASME) Accreditation Program for holders of N, NPT, NA,
and NV stamps and Certificates of Authorization. It is expected that recipients
and NV stamps and Certificates of Authorization.
 
===It is expected that recipients===
will review the information for applicability to their facilities.


will review the information for applicability to their facilities. However, suggestions contained in this information notice do not constitute NRC
However, suggestions contained in this information notice do not constitute NRC


requirements; therefore, no specific action or written response is required.
requirements; therefore, no specific action or written response is required.
Line 57: Line 66:
Quality System Certificates issued to Material Manufacturers (MM) and Material
Quality System Certificates issued to Material Manufacturers (MM) and Material


Suppliers (MS) are excluded from this recognition. The primary reasons for
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
developing the Exchange of Correspondence were to eliminate overlapping require- ments and to allow NRC licensees and their subcontractors to use the results of


Line 75: Line 85:
Exchange of Correspondence as prerequisites for NRC recognition of the
Exchange of Correspondence as prerequisites for NRC recognition of the


Accreditation Program had been met. On this basis, the NRC has sent letters
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
(see attached) to the National Board and ASME recognizing the holding of an


Line 82: Line 93:


IN 86-21_
IN 86-21_
                                                                    March 31, 1986 ASME N, NA, NPT or NV Certificate of Authorization as evidence that
March 31, 1986 ASME N, NA, NPT or NV Certificate of Authorization as evidence that the holder
 
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
of the Certificate of Authorization has a documented QA program that meets the


assessing whether a potential supplier has an acceptable documented
requirements of Appendix B to 10 CFR 50.


QA program, may rely on the fact that ASME has surveyed the supplier and issued
===In accordance with the Exchange of===
Correspondence, the NRC will make the appropriate changes to Regulatory Guides


a Certificate
1.28 and 1.33 in the next revision.


of Authorization of appropriate scope and for the desired location
===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


without
of Authorization of appropriate scope and for the desired location without


performing any additional evaluation of the supplier's QA program.
performing any additional evaluation of the supplier's QA program.
Line 112: Line 113:
Licensees and construction permit holders that take credit for the ASME
Licensees and construction permit holders that take credit for the ASME


Accreditation Program may have to revise their QA Program. They
Accreditation Program may have to revise their QA Program.
 
are reminded


that 10 CFR 50.54(a)(3) and 50.55(f)(3) set forth the requirements
===They are reminded===
 
that 10 CFR 50.54(a)(3) and 50.55(f)(3) set forth the requirements for making
for making


changes to QA programs.
changes to QA programs.
Line 124: Line 122:
It should be noted that NRC's recognition applies only to the programmatic
It should be noted that NRC's recognition applies only to the programmatic


aspects of the ASME Accreditation Program.   Licensees, construction permit
aspects of the ASME Accreditation Program.
 
holders, and their subcontractors are still responsible for ensuring


that the
===Licensees, construction permit===
holders, and their subcontractors are still responsible for ensuring that the


supplier is effectively implementing the approved QA program.
supplier is effectively implementing the approved QA program.
Line 138: Line 135:
have any questions regarding this notice, please contact the Regional
have any questions regarding this notice, please contact the Regional


Administrator of the appropriate NRC regional office or the technical
Administrator of the appropriate NRC regional office or the technical contact


contact
listed below.


listed below.
d a


d a        rector
rector


Divisi   of Emergency Preparedness and
Divisi


Engi eering Response
of Emergency Preparedness and


===Engi eering Response===
Office of Inspection and Enforcement
Office of Inspection and Enforcement


Technical Contacts:   E. T. Baker, IE
Technical Contacts:  


301-492-4874 G. G. Zech, IE
===E. T. Baker, IE===
301-492-4874


===G. G. Zech, IE===
301-492-9663 Attachments:
301-492-9663 Attachments:
1. Letter to ASME
1. Letter to ASME
Line 161: Line 161:
2. List of Recently Issued IE Information Notices
2. List of Recently Issued IE Information Notices


Attachment 1 IN 86-21 UNITED STATES                March 31, 1986 NUCLEAR REGULATORY COMMISSION
===Attachment 1===
IN 86-21
 
===March 31, 1986===
UNITED STATES
 
===NUCLEAR REGULATORY COMMISSION===
WASHINGTON, 0 C 20555


WASHINGTON, 0 C 20555 March 18. 1986
===March 18. 1986===
Mr. Melvin R. Green, Managing Director


===Mr. Melvin R. Green, Managing Director===
===Codes and Standards===
Codes and Standards
American Society of Mechanical Engineers


===American Society of Mechanical Engineers===
345 East 47th Street
345 East 47th Street


===New York, New York 10017===
New York, New York
Dear Mr. Green:
 
SUBJECT:   NRC ENDORSEMENT OF ASME'S ACCREDITATION PROGRAM
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
At the December 10, 1985 meeting of the NRC/ASME/NB Coordinating Committee it
Line 183: Line 192:
Program had been met. At that meeting it was also agreed that the NRC would
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
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
notice which is being sent to all licensees and to other parties on the


Line 190: Line 200:


Sincerely,
Sincerely,
                                                        , Director
, Director


ction and Enforcement
ction and Enforcement
Line 198: Line 208:
===Information Notice===
===Information Notice===


Attachment 1 ctot RECU                                                          IN 86-21 UNITED STATES                  March 31, 1986 NUCLEAR REGULATORY COMMISSION
ctot RECU
 
0
 
===Attachment 1===
IN 86-21
 
===March 31, 1986===
UNITED STATES


===NUCLEAR REGULATORY COMMISSION===
WASHINGTON, D C 20555
WASHINGTON, D C 20555
0
 
                                            March 18, 1986 Mr. Donald J. McDonald, Executive Director
===March 18, 1986===
Mr. Donald J. McDonald, Executive Director


National Board of Boiler & Pressure Vessel
National Board of Boiler & Pressure Vessel
Line 210: Line 230:
1055 Crapper Avenue
1055 Crapper Avenue


Columbus, Ohio 43229 Dear Mr. McDonald:
===Columbus, Ohio 43229===
  SUBJECT:   NRC ENDORSEMENT OF ASME'S ACCREDITATION PROGRAM
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
At the December 10, 1985 meeting of the NRC/ASME/NB Coordinating Committee it
Line 221: Line 243:
Program had been met. At that meeting it was also agreed that the NRC would
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
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
notice which is being sent to all licensees and to other parties on the


Line 230: Line 253:


Enclosure:
Enclosure:
  Information Notice


- V
===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


Attachment 2 IN 86-21 March 31, 1986 LIST OF RECENTLY ISSUED
Issued to


IE INFORMATION NOTICES
86-20
86-19
86-18
86-17
86-16
86-15
86-14
86-13
86-12
86-11 Low-Level Radioactive Waste


Information                                  Date of
===Scaling Factors, 10 CFR===
Part 61


Notice No.    Subject                        Issue  Issued to
===Reactor Coolant Pump Shaft===
Failure At Crystal River


86-20          Low-Level Radioactive Waste    3/28/86 All power reactor
NRC On-Scene Response During


Scaling Factors, 10 CFR                facilities holding
===A Major Emergency===
Update Of Failure Of Auto- matic Sprinkler System Valves


Part 61                                an OL or CP
To Operate


86-19          Reactor Coolant Pump Shaft    3/21/86 All power reactor
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


Failure At Crystal River              facilities holding
===All power reactor===
facilities holding


an OL or CP
an OL or CP


86-18          NRC On-Scene Response During  3/26/86 All power reactor
===All power reactor===
facilities holding
 
an OL or CP


A Major Emergency                      facilities holding
===All power reactor===
facilities holding


an OL or CP
an OL or CP


86-17          Update Of Failure Of Auto-    3/24/86 All power reactor
===All power reactor===
facilities holding


matic Sprinkler System Valves          facilities holding
an OL or CP


To Operate                            an OL or CP
===All power reactor===
facilities holding


86-16          Failures To Identify Contain- 3/11/86  All power reactor
an OL or CP


ment Leakage Due To Inadequate        facilities holding
===All power reactor===
facilities holding


Local Testing Of BWR Vacuum            an OL or CP
an OL or CP


Relief System Valves
===All power reactor===
facilities holding


86-15          Loss Of Offsite Power Caused  3/10/86 All power reactor
an OL or CP


By Problems In Fiber Optics            facilities holding
===All BWR facilities===
holding an OL or CP


Systems                                an OL or CP
===All power reactor===
facilities holding


86-14          PWR Auxiliary Feedwater Pump  3/10/86 All power reactor
an OL or CP


Turbine Control Problems              facilities holding
===All power reactor===
facilities holding


an OL or CP
an OL or CP


86-13          Standby Liquid Control        2/21/86 All BWR facilities
===Loss Of Offsite Power Caused===
 
By Problems In Fiber Optics
System Squib Valves Failure            holding an OL or CP


To Fire
Systems


86-12          Target Rock Two-Stage SRV      2/25/86 All power reactor
===PWR Auxiliary Feedwater Pump===
Turbine Control Problems


Setpoint Drift                        facilities holding
===Standby Liquid Control===
System Squib Valves Failure


an OL or CP
To Fire


86-11          Inadequate Service Water      2/25/86 All power reactor
Target Rock Two-Stage SRV


Protection Against Core Melt          facilities holding
===Setpoint Drift===
Inadequate Service Water


Frequency                             an OL or CP
===Protection Against Core Melt===
Frequency


OL = Operating License
3/10/86
3/10/86
2/21/86
2/25/86
2/25/86 OL = Operating License


CP = Construction Permit}}
CP = Construction Permit}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Latest revision as of 10:08, 16 January 2025

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 8603260277
Download: ML031220635 (5)
v • d • e


USORGIAL

SSINS No.: 6835 IN 86-21

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

PWR Auxiliary Feedwater Pump

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


Retrieved from "https://kanterella.com/w/index.php?title=Information_Notice_1986-21,_Recognition_of_American_Society_of_Mechanical_Engineers_Accreditation_Program_for_N_Stamp_Holders&oldid=5420847"