Information Notice 1986-36, Change in NRC Practice Regarding Issuance of Confirming Letters to Principal Contractors

Change in NRC Practice Regarding Issuance of Confirming Letters to Principal Contractors

ML031250021
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, 05000347, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill
Issue date:	05/16/1986
From:	Jordan E NRC/IE
To:
References
IN-86-036, NUDOCS 8605130024
Download: ML031250021 (3)

SSINS No.: 6835 IN 86-36 UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

WASHINGTON, D.C. 20555 May 16, 1986 IE INFORMATION NOTICE NO. 86-36: CHANGE IN NRC PRACTICE REGARDING ISSUANCE OF

CONFIRMING LETTERS TO PRINCIPAL CONTRACTORS

Addressees

All nuclear power reactor facilities holding an operating license (OL) or a

construction permit (CP).

Purpose

This notice is to inform recipients of a change in the NRC practice of issuing

confirming letters to principal contractors regarding the continuing adequacy

of their QA programs. This change, which is discussed in the Preface of the

Licensee Contractor and Vendor Inspection Status Report, October 1985-December 1985, NUREG-0040, Vol. 9, No. 4 (White Book), affects licensee implementation of their

QA programs in accordance with the requirements of Appendix B to 10 CFR 50

Criterion VII. It is expected that the recipients will review the information

for applicability to their facilities and consider appropriate actions. However, the information contained in this notice does not constitute new NRC requirements;

therefore, no specific action or written response is required.

Description of Circumstances

When design and construction activities for new nuclear power plants were

numerous, firms designing nuclear steam supply systems, architect engineering

firms designing nuclear power plants, and certain major equipment vendors were

inspected on a regular basis by the NRC. The purpose of these inspections was

to ascertain through direct observation of QA activities whether these design

firms and vendors were satisfactorily implementing their QA programs in accordance

with topical reports previously reviewed and accepted by the NRC. When the NRC

inspections had determined that the QA programs were being satisfactorily

implemented, the NRC issued confirming letters to the principal contractors.

Those letters were issued every three years, provided that the QA programs

continued to be satisfactorily implemented. The confirming letters could be

used by licensees and applicants, at their option, to fulfill their obligation

under 10 CFR 50, Appendix B, Criterion VII, that requires them to perform

initial source evaluation audits and subsequent periodic audits to verify QA

program implementation.

8605130024

y.*  ; IN 86-36 May 16, 1986 However, with the substantial decline in new plant design activities, the NRC

inspection of QA program implementation by principal contractors has been

deemphasized. As discussed in the Preface of the "White Book," future NRC

inspections will focus on selected areas instead of addressing the broad

implementation of the QA programs. Therefore, the NRC will no longer issue

confirming letters to principal contractors, and those letters that have already

exceeded their 3-year period of effectivity will not be renewed. Confirming

letters issued less than 3-years ago will remain in effect until the stated

period expires.

With the expiration of confirming letters, licensees and applicants will no

longer have the option to take credit for the NRC acceptance of the implementation

of a principal contractor's QA program. In accordance with commitments to meet

the provisions of Appendix B to 10 CFR 50, licensees and applicants will be

responsible for the conduct of initial source evaluation audits and subsequent

periodic audits to verify QA program implementation. The NRC will continue to

review revisions to the QA programs of principal contractors as described in

topical reports when submitted and, when approved, will issue approval letters.

The latest approved topical report revision number and date of the approval

letter will be published quarterly in the "White Book."

Since compliance with Criterion VII of Appendix B to 10 CFR 50 is already

required, no new specific action or written response is required by this

information notice. If you have any questions regarding this matter, please

contact the Regional Administrator of the appropriate regional office or this

office.

wad Jordan, Director

Divisio of Emergency Preparedness

and Engineering Response

Office of Inspection and Enforcement

W. P. Haass, IE

(301) 492-9041 Attachment: List of Recently Issued IE Information Notices

- <

Attachment 1 IN 86-36 May 16, 1986 LIST OF RECENTLY ISSUED

IE INFORMATION NOTICES

Information Date of

Notice No. Subject Issue Issued to

86-35 Fire In Compressible Material 5/15/86 All power reactor

At Dresden Unit 3 facilities holding

an OL or CP

86-34 Improper Assembly, Material 5/13/86 All power reactor

Selection, And Test Of Valves facilities holding

And Their Actuators an OL or CP

86-33 Information For Licensee 5/6/86 Fuel cycle licensees

Regarding The Chernobyl and Priority 1 material

Nuclear Plant Accident licensees

86-32 Request For Collection Of 5/2/86 All power reactor

Licensee Radioactivity facilities holding

Measurements Attributed To an OL or CP

The Chernobyl Nuclear Plant

Accident

86-31 Unauthorized Transfer and 5/6/86 All power reactor

Loss of Control of facilities holding

Industrial Nuclear Gauges an OL or a CP

86-30 Design Limitations of 4/29/86 All power reactor

Gaseous Effluent Monitoring facilities holding

Systems an OL or a CP

86-29 Effects of Changing Valve 4/25/86 All power reactor

Motor-Operator Switch facilities holding

Settings an OL or a CP

86-28 4/28/86

86-27 Access Control at Nuclear 4/21/86 All power reactor

Facilities facilities holding

an OL or CP, research

and nonpower reactor

facilities, and fuel

fabrication & pro- cessing facilities

OL = Operating License

CP = Construction Permit