Information Notice 1988-95, Inadequate Procurement Requirements Imposed by Licensees on Vendors

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Inadequate Procurement Requirements Imposed by Licensees on Vendors
ML031150017
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, Crane
Issue date: 12/08/1988
From: Rossi C
Office of Nuclear Reactor Regulation
To:
References
IN-88-095, NUDOCS 8812020287
Download: ML031150017 (8)


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATI6R

WASHINGTON, D.C. 20555

December 8, 1988 NRC INFORMATION NOTICE NO. 88-95:

INADEQUATE PROCUREMENT REQUIREMENTS

IMPOSED BY LICENSEES ON VENDORS

Addressees

All holders of operating licenses or construction permits for nuclear power

reactors.

Purpose

This information notice is being provided to alert addressees to potential

problems resulting from inadequate procurement requirements being imposed by

licensees on vendors supplying components under the ASME Code which may result

in the vendor's failure to implement critical portions of 10 CFR Part 50,

Appendix B, Quality Assurance (QA) requirements. It is expected that recipi- ents will review the information for applicability to their facilities and

consider actions, as appropriate, to avoid similar problems. However, sugges- tions contained in this information notice do not constitute NRC requirements;

therefore, no specific action or written response is required.

Description of Circumstances

On August 15-19, 1988, the NRC staff inspected Anchor/Darling Industries, Inc.

(A/DI), Hatfield, PA. The inspection included a review of A/DI's QA program, as it relates to the manufacture of mechanical shock suppressors (snubbers) for

safety-related applications. A/DI is a material supplier and is accredited by

the American Society of Mechanical Engineers (ASME) under a Quality Systems

Certificate.

As such, the quality requirements of the ASME Boiler and Pressure

Vessel Code,Section III, Article NCA-3800, apply.

A/DI's QA manual specifies that only load-bearing parts of the snubber are

subject to the quality requirements of Section III, Division 1, of the ASME

Code.

Subsection NF-2121 of Section III, "Permitted Material Specification,"

specifies that gaskets, seals, bushings, springs, compression spring

end-plates, bearings, retaining rings, washers, wear shoes, hydraulic fluids, etc., are exempt from the requirements of Article NF-2000, 'Material," and as

such do not require a Material Manufacturer's Certificate of Compliance pursu- ant to the provisions of NF-2130. The A/DI QA program does not address the

procurement and QA controls of the ASME Code exempt load-bearing parts. The

inspectors noted that A/DI considers several parts in the direct load path of

the A/DI mechanical snubber to be exempt from QA requirements because of the

NF-2121 exemption. These parts include the ball nut, ball bushing, thrust

881222j

/

/

IN 88-95 December 8, 1988 race, ball bearing, and the load member on the AD-125 model snubber (125,000-

pound rated load). These parts are purchased commercial grade and appear not

to have the benefit of a dedication process or any other quality controls

necessary to assure adequacy of the critical characteristics of the parts.

Therefore, safety-related snubbers produced by A/DI contain direct load path

parts, procured commercially, that may not conform to the original tested

configuration.

In another example, the NRC received a 10 CFR Part 21 report on August 8, 1988 from the Southern California Edison Company regarding a deviation found on

parts in storage at the San Onofre Nuclear Generating Station (SONGS).

The

deviation involved cracks discovered in spare safety valve guide and bearing

assemblies in storage.

SONGS filed the Part 21 report on the basis that

failure of the valve'guide or bearing assembly could affect the operability of

the valve. The parts are utilized in Units 2 and 3 main steam safety valves

and were supplied by Crosby Valve and Gage Company, Wrentham, Massachusetts.

Because the valve guide and bearing assemblies are not pressure boundary parts, the parts were manufactured and supplied as commercial grade.

Crosby did not

consider these components to be critical and did not retain pertinent manufac- turing, procurement, and inspection records.

SONGS has since revised their

purchasing requirements to impose Appendix B or ANSI N45.2 requirements on

safety-related parts excluded from Section III requirements.

Discussion:

It is important that licensees place adequate requirements in procurement

documents to vendors to control the quality of safety-related components, equipment, and services and subsequently verify compliance through periodic

audits of the vendor's QA program.

Licensees are reminded that safety-related

components are to be manufactured under a QA program that meets 10 CFR Part 50

Appendix B requirements.

The NRC has determined that compliance with Section

III of the ASME Boiler and Pressure Vessel Code satisfies Appendix B require- ments for items covered by the Code.

However, this is not sufficient to ensure

that safety-related items exempt from Code requirements comply with Appendix B.

Licensees are reminded that they are responsible for ensuring that their

vendors meet Appendix B requirements for safety-related items.

Considering the

two above-described examples, it appears that past licensee audits of A/DI and

Crosby have not been effective in assuring compliance with regulatory

requirements.

It is important that purchase orders to companies specify compliance with

Appendix B as well as the ASME Code to assure that all parts with safety

functions have adequate quality assurance applied.

These examples further

reinforce the NRC's belief that additional attention is needed to improve the

effectiveness of licensee imposed procurement requirements on vendors to

control the quality of safety-related items.

IN 88-95 December 8, 1988 NRC previously conveyed concerns in Information Notice 88-35, "Inadequate

Licensee Performed Vendor Audits," that licensee audits of vendors may not be

effectively evaluating the vendor's QA program and its implementation, specifi- cally in the area of procurement. The examples discussed in this notice

indicate that licensee audits are not assuring that vendors apply adequate

quality requirements for all parts within an ASME component that have a safety

function.

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

If you have any questions about this matter, please contact the technical

contact listed below or the Regional Administrator of the appropriate regional

office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

Robert L. Pettis, Jr., NRR

(301) 492-3214 Attachment:

List of Recently Issued NRC Information Notices

IN 88-95 December 8, 1988 NRC previously conveyed concerns in Information Notice 88-35, "Inadequate

Licensee Performed Vendor Audits," that licensee audits of vendors may not be

effectively evaluating the vendor's QA program and its implementation, specifi- cally in the area of procurement.

The examples discussed in this notice

indicate that licensee audits are not assuring that vendors apply adequate

quality requirements for all parts within an ASME component that have a safety

function.

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

If you have any questions about this matter, please contact the technical

contact listed below or the Regional Administrator of the appropriate regional

office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

Robert L. Pettis, Jr., NRR

(301) 492-3214 Attachment:

List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCE PAGE.

OFC

VIB:DRIS:NRR
VIB:DRIS:NRR :VIB:DRIS:NRR
TECH EDITOR
C:VIB:DRIS:NRR:D:DRIS:NRR

______

________________

______________

______________

______________

______________

_____________

NAME

RLPettis:jeh*
ETBaker*
UPotapovs*
RSanders*
EWBrach*
BKGrimes*

DATE

10/07/88:mgc
10/16/88
10/18/88
10/18/88
11/25/88
11/28/88 OFC
D:DOEA:NRR
DD/DLPQ:NRR
C/OGCB:DOEA:NRR:

NAME

CERossi
JZwolinski
CHBerlinger*

 :-------------1

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_

____________

DATE

12/ /88

/ :12/;Z/88

11/30/88:::

I

IN 88-XX

December XX, 1988 NRC previously conveyed concerns in Information Notice 88-35 that licensee

audits of vendors may not be effectively evaluating the vendor's QA program

and its implementation, specifically in the area of procurement.

The examples

discussed in this notice indicate that licensee audits are not assuring that

vendors apply adequate quality requirements for all parts within an ASME

component that have a safety function.

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

If you have any questions about this matter, please contact the technical

contact listed below or the Regional Administrator of the appropriate regional

office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

Robert L. Pettis, Jr., NRR

(301) 492-3214 Attachment:

List of Recently Issued NRC Information Notice

  • SEE PREVIOUS CONCURRENCE PAGE.

OFC

VIB:DRIS:NRR
VIB:DRIS:NRR :VIB:DRIS:NRR
TECH EDITOR
C:VIB:DRIS:NRR:D:

______

________________-

____------------:--------------:


--------------o5sff- NAME
RLPettis:jeh*
ETBaker*
UPotapovs*
RSanders*
EWBrach*

_ _ ---:----------------:--------------: -------------- : -------------- :------------)

DATE

10/07/88:mgc
10/16/88
10/18/88
10/18/88
11/25/88
111Z6/88 OFC
D:DOEA:NRRo

0bF-i:Hld

______

_____

_____

____



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NAME

CERossi

DATE__11/_/8_- -


DATE

11/

/88 *#5/

IN 88-XX

December XX, 1988 NRC previously conveyed concerns in Information Notice 88-35 that licensee

audits of vendors may not be effectively evaluating the vendor's QA program

and its implementation, specifically in the area of procurement. The examples

discussed in this notice indicate that licensee audits are not assuring that

vendors apply adequate quality requirements for all parts within an ASME

component that have a safety function.

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

If you have any questions about this matter, please contact the technical

contact listed below or the Regional Administrator of the appropriate regional

office.

Charles E. Rossi, Director

Division of Operation Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

Robert L. Pettis, Jr., NRR

(301) 492-3214 Attachment:

List of Recently Issued NRC Information Notice

  • SEE PREVIOUS CONCURRENCE PAGE.

t

OFC

VIB:DRIS:NRR
VIB:DRIS:NRR :VIB:DRIS:NRR :TECH EDITOR
C:VID:DRIS:NRR:D:DRIS:NRR

___

________________

_________-------

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____--

______-_____-----

-_

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-____________

NAME :RLPettis:jeh*

ETBaker*
UPotapovs*
RSanders*
E4Bth
BKGrimes

DATE :10/07/88:mgc

10/16/88
10/18/88
10/18/88
11/tSf88
11/

/88 OFC

D:DOEA:NRR

NAME

CERossi

DATE :11/

/88

IN 88-35 October

, 1988 No spe

  • c action or written response is required by this IN. If yo 1have

any quest

s about this matter, please contact the technical contac

sted

below or the

ional Administrator of the appropriate regional of ce.

Charles E. Rossi, Direc r

Division of Operation

ents Assessment

Office of Nuclear Re tor Regulation

Technical Contact:

Robert L. P tis, Jr., NRR

(301) 492-321 Attachment:

List of Recently Issued NRC Informat

Noti

  • SEE PREVIOUS CONCU

E PAGE.

OFC

VIB:DRIS:NR!XM

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NAME

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BKGrimes

DATE :10/07/88:mg

10/ /88
10//88
10/iS/88
10

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10/ /88 OFC

D: DOEA: N H

NAME :CERoss


 :----


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DATE :101

/

88:::::

IN 88-35 October

, 1988 No specific action or written response is required by this IN. If you have

any questions about this matter, please contact the technical contact listed

below or the Regional Administrator of the appropriate regional office.

Charles E. Rossi, Director

Division of Operation Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

Robert L. Pettis, Jr., NRR

(301) 492-3214 Attachment:

List of Recently Issued NRC Information Notice

OFC

VIB:DRIS:NRR
VIB:DRIS:NRR :VIB:DRIS:NRR :TECH EDITOR
C:VIB:DRIS:NRR:D:DRIS:NRR

NAME

.

RLPett

jeh

':ETBaker

UPotapovs
EWBrach
BKGrimes

_____

---


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_-:-___________-____________

-__________

DATE :10/ 7/88:mgc/

10/

/88

10/ /88
10/

/88

10/ /88
10/ /88 OFC
D:DOEA:NRR'

NAME :CERossi

DATE :10/ /88