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

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, 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, 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
Issue date:	03/31/1986
From:	Jordan E NRC/IE
To:
References
IN-86-021, NUDOCS 8603260277
Download: ML031220635 (5)

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