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)
(Created page by program invented by StriderTol)
Line 14: Line 14:
| page count = 5
| page count = 5
}}
}}
{{#Wiki_filter:USORGIAL SSINS No.: 6835 IN 86-21 UNITED STATES NUCLEAR REGULATORY
{{#Wiki_filter:USORGIAL


COMMISSION
UNITED STATES


OFFICE OF INSPECTION
SSINS  No.: 6835 IN 86-21 NUCLEAR REGULATORY COMMISSION


===AND ENFORCEMENT===
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555 March 31, 1986 IE INFORMATION


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


OF AMERICAN SOCIETY OF MECHANICAL
MECHANICAL ENGINEERS ACCREDITATION


ENGINEERS
===ACCREDITATION===
PROGRAM FOR N STAMP HOLDERS
PROGRAM FOR N STAMP HOLDERS


==Addressees==
==Addressees==
:
:
All nuclear power facilities
All nuclear power facilities holding an operating license (OL) or a construction
 
holding an operating
 
license (OL) or a construction


permit (CP) and all recipients
permit (CP) and all recipients of NUREG-0040 (white book).
 
of NUREG-0040 (white book).


==Purpose==
==Purpose==
: This information
:
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


notice is provided to licensees, construction
Mechanical Engineers (ASME) Accreditation Program for holders of N, NPT, NA,
and NV stamps and Certificates of Authorization. It is expected that recipients


permit holders, and vendors to inform them of the NRC's recognition
will review the information for applicability to their facilities. However, suggestions contained in this information notice do not constitute NRC


of the American Society of Mechanical
requirements; therefore, no specific action or written response is required.


Engineers (ASME) Accreditation
Discussion:
In March 1981, representatives of the NRC, ASME, and the National Board of


Program for holders of N, NPT, NA, and NV stamps and Certificates
Boiler and Pressure Vessel Inspectors (NB) signed an Exchange of Correspondence


of Authorization.
that outlined an agreement to work toward establishing a single set of quality


===It is expected that recipients===
requirements and recognition by the NRC of ASME's Accreditation Program for N,
will review the information
NA, NPT, and NV stamps and the associated Certificates of Authorization.


for applicability
Quality System Certificates issued to Material Manufacturers (MM) and Material


to their facilities.
Suppliers (MS) are excluded from this recognition. The primary reasons for


However, suggestions
developing the Exchange of Correspondence were to eliminate overlapping require- ments and to allow NRC licensees and their subcontractors to use the results of


contained
the ASME/NB nuclear accreditation and inspection system as an acceptable method


in this information
for satisfying NRC requirements for evaluating the programmatic adequacy of


notice do not constitute
their suppliers' documented quality assurance (QA) programs.


NRC requirements;
In a meeting on December 10, 1985, representatives of the NRC, NB, and ASME
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
agreed that based on the requirements contained in the 1986 Edition of the ASME


that outlined an agreement
Boiler and Pressure Vessel Code all of the conditions established in the


to work toward establishing
Exchange of Correspondence as prerequisites for NRC recognition of the


a single set of quality requirements
Accreditation Program had been met. On this basis, the NRC has sent letters


and recognition
(see attached) to the National Board and ASME recognizing the holding of an


by the NRC of ASME's Accreditation
8603260277


Program for N, NA, NPT, and NV stamps and the associated
IN 86-21_
                                                                    March 31, 1986 ASME N, NA, NPT or NV Certificate of Authorization as evidence that


Certificates
the holder


of Authorization.
of the Certificate of Authorization has a documented QA program that


Quality System Certificates
meets the


issued to Material Manufacturers (MM) and Material Suppliers (MS) are excluded from this recognition.
requirements of Appendix B to 10 CFR 50.   In accordance with the Exchange of


The primary reasons for developing
Correspondence, the NRC will make the appropriate changes to Regulatory


the Exchange of Correspondence
Guides


were to eliminate
1.28 and 1.33 in the next revision. Licensees and their subcontractors, when


overlapping
assessing whether a potential supplier has an acceptable documented


require-ments and to allow NRC licensees
QA program, may rely on the fact that ASME has surveyed the supplier and issued


and their subcontractors
a Certificate


to use the results of the ASME/NB nuclear accreditation
of Authorization of appropriate scope and for the desired location


and inspection
without


system as an acceptable
performing any additional evaluation of the supplier's QA program.


method for satisfying
Licensees and construction permit holders that take credit for the ASME


NRC requirements
Accreditation Program may have to revise their QA Program. They


for evaluating
are reminded


the programmatic
that 10 CFR 50.54(a)(3) and 50.55(f)(3) set forth the requirements


adequacy of their suppliers'
for making
documented


quality assurance (QA) programs.In a meeting on December 10, 1985, representatives
changes to QA programs.


of the NRC, NB, and ASME agreed that based on the requirements
It should be noted that NRC's recognition applies only to the programmatic


contained
aspects of the ASME Accreditation Program.    Licensees, construction permit


in the 1986 Edition of the ASME Boiler and Pressure Vessel Code all of the conditions
holders, and their subcontractors are still responsible for ensuring


established
that the


in the Exchange of Correspondence
supplier is effectively implementing the approved QA program.


as prerequisites
No specific action or response is required by this information notice.


for NRC recognition
If you


of the Accreditation
have any questions regarding this notice, please contact the Regional


Program had been met. On this basis, the NRC has sent letters (see attached)
Administrator of the appropriate NRC regional office or the technical
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
contact


of Authorization
listed below.


as evidence that the holder of the Certificate
d a        rector


of Authorization
Divisi  of Emergency Preparedness and


has a documented
Engi eering Response


QA program that meets the requirements
Office of Inspection and Enforcement


of Appendix B to 10 CFR 50. In accordance
Technical Contacts:  E. T. Baker, IE


with the Exchange of Correspondence, the NRC will make the appropriate
301-492-4874 G. G. Zech, IE


changes to Regulatory
301-492-9663 Attachments:
1. Letter to ASME


Guides 1.28 and 1.33 in the next revision.
2. List of Recently Issued IE Information Notices


Licensees
Attachment 1 IN 86-21 UNITED STATES                March 31, 1986 NUCLEAR REGULATORY COMMISSION


and their subcontractors, when assessing
WASHINGTON, 0 C 20555 March 18. 1986


whether a potential
===Mr. Melvin R. Green, Managing Director===
Codes and Standards


supplier has an acceptable
===American Society of Mechanical Engineers===
345 East 47th Street


documented
===New York, New York 10017===
Dear Mr. Green:
SUBJECT:  NRC ENDORSEMENT OF ASME'S ACCREDITATION PROGRAM


QA program, may rely on the fact that ASME has surveyed the supplier and issued a Certificate
At the December 10, 1985 meeting of the NRC/ASME/NB Coordinating Committee it


of Authorization
was agreed that all conditions established in the Exchange of Correspondence


of appropriate
as prerequisites for NRC recognition and endorsement of the ASME Accreditation


scope and for the desired location without performing
Program had been met. At that meeting it was also agreed that the NRC would


any additional
publish an information notice communicating the NRC's recognition and endorse- ment of the Accreditation Program. Enclosed is a copy of the information


evaluation
notice which is being sent to all licensees and to other parties on the


of the supplier's
information notice distribution list.


QA program.Licensees
Sincerely,
                                                        , Director


and construction
ction and Enforcement


permit holders that take credit for the ASME Accreditation
Enclosure:
 
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
===Information Notice===


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


in the Exchange of Correspondence
WASHINGTON, D C 20555
0
                                            March 18, 1986 Mr. Donald J. McDonald, Executive Director


as prerequisites
National Board of Boiler & Pressure Vessel


for NRC recognition
Inspectors


and endorsement
1055 Crapper Avenue


of the ASME Accreditation
Columbus, Ohio 43229 Dear Mr. McDonald:
  SUBJECT:    NRC ENDORSEMENT OF ASME'S ACCREDITATION PROGRAM


Program had been met. At that meeting it was also agreed that the NRC would publish an information
At the December 10, 1985 meeting of the NRC/ASME/NB Coordinating Committee it


notice communicating
was agreed that all conditions established in the Exchange of Correspondence


the NRC's recognition
as prerequisites for NRC recognition and endorsement of the ASME Accreditation


and endorse-ment of the Accreditation
Program had been met. At that meeting it was also agreed that the NRC would


===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 information
notice which is being sent to all licensees and to other parties on the


notice distribution
information notice distribution list.


list.Sincerely, , Director ction and Enforcement
Sincerely, nspection and Enforcement


Enclosure:
Enclosure:
Information
  Information Notice


Notice
- V


ctot RECU 0 Attachment
Attachment 2 IN 86-21 March 31, 1986 LIST OF RECENTLY ISSUED


1 IN 86-21 March 31, 1986 UNITED STATES NUCLEAR REGULATORY
IE INFORMATION NOTICES


COMMISSION
Information                                  Date of


WASHINGTON, D C 20555 March 18, 1986 Mr. Donald J. McDonald, Executive
Notice No.     Subject                        Issue  Issued to


Director National Board of Boiler & Pressure Vessel Inspectors
86-20          Low-Level Radioactive Waste    3/28/86 All power reactor


1055 Crapper Avenue Columbus, Ohio 43229 Dear Mr. McDonald: SUBJECT: NRC ENDORSEMENT
Scaling Factors, 10 CFR                facilities holding


OF ASME'S ACCREDITATION
Part 61                                an OL or CP


PROGRAM At the December 10, 1985 meeting of the NRC/ASME/NB
86-19          Reactor Coolant Pump Shaft    3/21/86 All power reactor


Coordinating
Failure At Crystal River              facilities holding


Committee
an OL or CP


it was agreed that all conditions
86-18          NRC On-Scene Response During  3/26/86 All power reactor
 
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
A Major Emergency                      facilities holding


-V Attachment
an OL or CP


2 IN 86-21 March 31, 1986 LIST OF RECENTLY ISSUED IE INFORMATION
86-17          Update Of Failure Of Auto-    3/24/86 All power reactor


NOTICES Information
matic Sprinkler System Valves          facilities holding


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
To Operate                            an OL or CP


Radioactive
86-16          Failures To Identify Contain- 3/11/86  All power reactor


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
ment Leakage Due To Inadequate        facilities holding


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            an OL or CP


Local Testing Of BWR Vacuum Relief System Valves All power reactor facilities
Relief System Valves


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


holding an OL or CP All power reactor facilities
By Problems In Fiber Optics            facilities holding


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


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


holding an OL or CP All power reactor facilities
Turbine Control Problems              facilities holding


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


holding an OL or CP All BWR facilities
86-13          Standby Liquid Control        2/21/86 All BWR facilities


holding an OL or CP All power reactor facilities
System Squib Valves Failure            holding an OL or CP


holding an OL or CP All power reactor facilities
To Fire


holding an OL or CP Loss Of Offsite Power Caused By Problems In Fiber Optics Systems PWR Auxiliary
86-12          Target Rock Two-Stage SRV      2/25/86 All power reactor


Feedwater
Setpoint Drift                        facilities holding


Pump Turbine Control Problems Standby Liquid Control System Squib Valves Failure To Fire Target Rock Two-Stage
an OL or CP


SRV Setpoint Drift Inadequate
86-11          Inadequate Service Water      2/25/86 All power reactor


Service Water Protection
Protection Against Core Melt          facilities holding


Against Core Melt Frequency 3/10/86 3/10/86 2/21/86 2/25/86 2/25/86 OL = Operating
Frequency                             an OL or CP


License CP = Construction
OL = Operating License


Permit}}
CP = Construction Permit}}


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

Revision as of 02:04, 24 November 2019

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

UNITED STATES

SSINS No.: 6835 IN 86-21 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 UNITED STATES March 31, 1986 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

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

WASHINGTON, D C 20555

0

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 Low-Level Radioactive Waste 3/28/86 All power reactor

Scaling Factors, 10 CFR facilities holding

Part 61 an OL or CP

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

Failure At Crystal River facilities holding

an OL or CP

86-18 NRC On-Scene Response During 3/26/86 All power reactor

A Major Emergency facilities holding

an OL or CP

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

matic Sprinkler System Valves facilities holding

To Operate an OL or CP

86-16 Failures To Identify Contain- 3/11/86 All power reactor

ment Leakage Due To Inadequate facilities holding

Local Testing Of BWR Vacuum an OL or CP

Relief System Valves

86-15 Loss Of Offsite Power Caused 3/10/86 All power reactor

By Problems In Fiber Optics facilities holding

Systems an OL or CP

86-14 PWR Auxiliary Feedwater Pump 3/10/86 All power reactor

Turbine Control Problems facilities holding

an OL or CP

86-13 Standby Liquid Control 2/21/86 All BWR facilities

System Squib Valves Failure holding an OL or CP

To Fire

86-12 Target Rock Two-Stage SRV 2/25/86 All power reactor

Setpoint Drift facilities holding

an OL or CP

86-11 Inadequate Service Water 2/25/86 All power reactor

Protection Against Core Melt facilities holding

Frequency an OL or CP

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=2200103"