ML20129G487

Fourth Partial Response to FOIA Request for Documents. Records in App F Encl & Being Placed in PDR

ML20129G487
Person / Time
Site:	Crane
Issue date:	09/17/1996
From:	Racquel Powell NRC OFFICE OF ADMINISTRATION (ADM)
To:	Dekok D AFFILIATION NOT ASSIGNED
Shared Package
ML20126B025	List: IA-96-214, Recommends Specific Changes to Ensure That QA Requirements for Class Items Will Conform to 10CFR50 App B Requirements ML20126B024 ML20126B028 ML20126B031 ML20126B035 ML20129G487 ML20136B021 ML20136B027 ML20136B033 ML20136B041 ML20136B044 ML20136B879 ML20136C099 ML20136C107 ML20136C124
References
FOIA-96-214 NUDOCS 9610030067
Download: ML20129G487 (5)

Text

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U.S. NUCLEAR RE!ULATORY COMMISSION NHC Foia HtoutST NuMBE,.(S) g.g (j

FOIA -

96-214 A,

RESPONSE TYPE

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RESPONSE TO FREEDOM OF lnNAL lX l PARTIAL ( g }

(e gg7g INFORMATION ACT (FOIA) REQUEST DATE nse DOCK L T NUMBE H(S) (t/ app / cable /

REQUESTE.1 Mr. David DeKok PART 1.-AGENCY RECORDS RELEASED OR NOT LOCATED (Seecheckedboxes)

No agency records subject to the request have been located.

N 3 additional agency records subject to the request have been located.

Requested records are available through another public distrioution program. See Comments section.

Agency records subject to the request that are identified in Append;x(es) are already available for public inspection and copying at the j

NRC Public Document Room,2120 L Street, N.W., Washington, DC.

j Agency records rubject to the re Juest that are identified in Appendin(es)

I are being made available for public inspection and copying

)(

at the NRC Public Document Roorn,2120 L Street. N.W., Washington, DC,in a folder under this FOI A number.

The nonproprietary version of the proposal (s) that you agreed to accept in a telephone conversation with a member of my staff is now being made available for public inspection and copying at the N RC Public Document Room,2120 L Street, N.W., Washington, DC, in a folder unoer this FOI A number, 1

Agency records subject to the request that are identified in Appendix (es) may be unpected and copied at the NRC Local Public Document i

Room identified in the Comments secticn.

Enclosed is information on how you may obtain access to and the charges for copymg records located at the NRC Public Document Room,2120 L Street, N.W., Washington, DC.

Agency records subject to the request are enclosed Records subject to the request have been referred to another Federal agency (ies) for review and direct response to you.

Fees You will be billed by the NRC for fees totali.; $

You will receive a refund from the NRC in the amount of $

In vi1w of N RC's response to this request, no further action is being taken on appeal letter dated

, No.

1 PART 18. A-INFORMATION WITHHELD FROM PUBLIC DISCLOSURE j

Cert;in information in the requested records is being withheld from public disclosure pursuant to the exemptions described in and for the reasons stated in Part 11, B, C, and D. Any rele. sed portions of the documents for which only part of the record is bein0 withheld are bein0 made available for public inspection and copying in the NRC Public Document Room,2120 L Street, N.W., Washington, DC in a folder under this FOIA number, COMMENTS The recorde identified on enclosed Appendix F are subject to your request.

Copies of these records are being placed in NRC's Public Document Room as you requested.

The staff is reviewing some additional records which may be subject to your request.

j You will be notified promptly once this review is complete.

i 4j k sio Ecto vt OF F RE L INFORMATWN ANO PUBUCATIONS $tRVICES 9610030067 960917 PDR FOIA DEKOK96-214 PDR

t

('t FOIA-96-214 i

APPENDIX f l

l (Documents to be Released)

From Subiect.

1. Pages pggg To 1.

2/19/73 P. Collins N. Elliott In an effort to update 21 AEC (NRC)

B&W and make the Babcock &

4 Wilcox (B&W) training

[

programs....

w/

Enclosures:

(1) Copy of revised

~

" cold" license training

_ program r

i (2) Summary of experience levels of B&W instructors i

2.

9/17/73 P. Collins N. Elliott Enclosed is a copy of B&W's 5

l AEC (NRC)

B&W proposed replacement operator training program....

3.

08/30/74 P. Collins N. Elliott In reference to our recent 1

AEC (NRC)

B&W conversation with respect to the conduct of the reactor operator's certification examination.....

I I

4.

12/15/76 Notes for W. Morrison Two problem areas were 16 I

Attendees AEC (NRC) discussed during this at the 11/30/76 meeting.....

meeting...

w/ Enclosures (1) Proposed draft letter i

Bosnak to H. Dobel, B&W Subj:

Consideration of Class 3 Quality Assurance Requirements 5.

01/07/77 W. Gibbons, Jr.

J. Milhoan Mr. Dobel in his letter 8

Bechtel Corp.

Office of to you of 5/5/76....

Standards Subj:

Revision of the Development Code to Reflect Criterion I

.of Appendix B to 10 CFR Part 50 w/

Enclosures:

(1) Response to H. Dobel request concerning Rev. to NA-4133.1 (Now Designated NCA-4134.1)

(2) Proposed Rewording of NA-4133.1 i

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. FOIA-96-214 l

i patg To From Subiect

1. Paces 6.

01/17/77 H. Dobel R. Bosnak My letter to you of 6/8/76... 13 B&W (AEC) NRR Re:

Consideration of Class 3 Quality Assurance Requirements

Enclosure:

Comparison:

Coverage of the code for quality assurance requirements for Class I, 2, MC, CS, CB, and CC construction with the quality assurance requirements for Class 3 construc' tion 7.

01/27/77 Interoffice-W. Morrison Minutes of the 1/13/77 6

QA Task Force Chmn, Task Meeting of the Interoffice Force, NRR Quality Assurance Task Force 8.

02/18/77 G. Cavis J. Cady, Jr.

W.O.

2555-02 79 United Burns & Roe JCP&L Co.

Engineers Transmittal of i

Field Change Request (FCR)

Constructors

& Associated Documents w/TMI, Unit 2 l

Field Change Request No. 2329.1 dated 2/11/77 and associated attachments 9.

05/28/77 Document No. TM-0841 4

i (1) Machinery History Card (2) Motor Bumping Check List 4

(3) United Engineers &

Construction TMI Power Station Equipment Data Sheet Motor Operated Valves 10.

06/14/77 L. Tsaggaris B. Street Metropolitan Edision Company 6

Met. Ed. Co.

B&W Documentaton -

B&W Ref. 601-8027 T9 (1) Attachments:

Simulater Training Sheet (2)

Plant Operations Training (3)

Simulater Training Summary w/ attached letter as follows:

03/18/77 L. Tsaggaris N. Elliott Subj:

Cold License Training Meted Co.

B&w l

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_ ~. _ _. _. _. _... _ _ -, _.-, _.. _ _. -. _ _ _ _.. _. _

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i e FOIA-96-214 i

?

l Date To-From Subiect

'# Paces 11.

06/22/77 D. Goodman B. Street Meted'Co. Documentation -

3 l

Meted Co.

B&W B&W Ref. 601-8027-06 j

w/ Attachments as follows:

j (1) Simulator Training Summary Sheet (2) Plant Operations Training Sheet 12.

07/13/77

- D. Goodman-B. Street Meted Co. Documentation -

Meted Co.

B&W B&W Ref. 601-8027-06 w/ Attachments as follows:

(1) Simulator Training Summary Sheet 6/27-7/1/77 (2) Plant Operations Training Sheet (3) Simulator Training Summary Sheet 6/27-7/1/77 (4) Plant Operations Training Sheet (5)

Simulator Training Summary Sheet 6/27-7/1/77 1

13.

07/28/77 United.

TMI Document 2

Engineers No. TM-0836 Equipment Data Sheet Construction Mechanical Inc.

l 14.

07/28/77 TMI Document 2

I No. 0838 Equipment Erection Data Sheet j

Vibration Record r--e w -

e

,mm1 c--

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_... _. _... -. - _ ~. -... _.. - _. _. _ _ _.. -. _... _. _.. _

4 i

i FOIA-96-214 2

f Date

To

.From Subiect

1. Paces _,

15.

12/27/77 R. Toole J.

Furlong TMI, Unit 2, FCR 3

GPU Catalytic Completion Notice i

Constructors w/ attachment as follows:

{

06/23/77 W. Gunn G. Cavis TMI, Unit 2, FCR i

GPU United Completion Notice Engineers w/FCR Transmittal

{

Sheet dated 2/21/77 i

Constructors Inc.

16.

01/17/78 U. Lamay D. English W.O. 2555-02 5

Catalytic, Inc. Burns & Roe JCP& Light Co.

j Inc.

TMI Transmittal l

of Field Change

[

Request (FCR)

& Associated Documents w/ Attached (1) Field Change Request FCR No. 2329.1, Rev. 1 dated 1/16/78 l

(2) Description of Change (3) List of Attachments (4) Exhibit A, TMI-008 17.

03/02/78 R. Toole S. Kakarla TMI Doc. No. 0710 3

GPU Corp.

United.

TMI, Unit 2 TMI Engineers FCR Completion Notice 1

w/ Attached i

Constructors FCR Transmittal Inc.

dated'1/18/78 TMI Document 10 18.

12/11/78 No. 0861.

Radiological Ref. #90 This Radiological Reference changed to #45

~w/ associated documents including 07/28/78 P. De R. Gaspercic W.O. 2555-02 Burns & Roe JCP&L Co.

Problem Report #2699 w/ attachments i

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_. David DeKok-113 Conoy St.

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..Harrisburg, Pa.17104

' 'May 19,~ 1996

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,.Div:sion of Frevedont of:Information-i.. +

. ACT REQUEST

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).h r Sir or Madam:

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.h, ! Pursuant to the F.reedom of Information Ah,Tlihereby' request copihsf -

(of the folidwing; f

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6All Category Q (inspe..ction) reports for the Three Mile ~ Isla:nd"; Unit)2 b

ffeactor (Docketz50-320) that cannot be proveri to beiri bie Public

• Docume.nt Room:

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^

.N M Isear'ched for these documents in the PDR on M,ay 17-1996, and Y found that many.werel missing. Some inspection, reports in thefPR.I"

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Ecollection refererenced previous inspection reports that we.re not >

'there, I had the staff do a printout of in'spection reports that were l supposedly in the PDR, but was unable to find over half of those of a-

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sample I randomly picked from the list to pull.;The mere fact that an

-. inspection report is in the 60mputer evidently does not mean ~it is in ;

.the fiche file.

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.e,HAsy corresponderice between the Atomic Energy Commission'or the Nuclear Regillatory Commission and any'of.the following companies c

i whb had a role in.the construction of TMI-2: Burns & Roe, Gilbert Associates,-Babcock & Wilcor, and United Engineers & Constructors, a '

- subsidiary of Raytheon.

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i Pursuant 10 the Freedom of Information Act, I also request L

~ Representative of the News Media" status, which entitles me to a waiver of search fees and 100 pages of free copying. These documents are needed for a book I am writing on the. history of General Public l

Utilities Corp., owner of TMI-2. I am an established freelance writer, l

author of one previous book. Unseen Banger.4 Trsgedy#hge, 6orernment sadthe Centrshs # hee #g was published in 1986 by University of Pennsylvania Press. In addition. I have been a l

newspaper journalist for 20 years.

Thank you for your attention to this request.

Sincerely.

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David DeKot i

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o, Babcock & Wilcox go.., cen,,.1 ion oi i. ion -

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i P.O. Box 1260, tynchburg. Va. 24505 i

Telephone: 003) 384-5111 l

February 19,1973 I

l Mr. Paul Collins l

Chief, Operator Licensing Branch U. S. Atomic Energy Commission Washington, D. C.

20545

Dear Mr. Collins:

In an effort to update and make the Babcock & Wilcox training programs more effective, I have conducted a review of our programs and made a number of proposed revisions to our " cold" license training program. Enclosure I is a copy of our revised " cold" license program which is submitted for review with respect to meeting the requirements of Section 55.25(b) of 10 CFR, Part 55.

It is requested that you conduct a review of this material and forwcrd yo'ur ce==ents to me at the earliest possible time.

- Enclosure II is a su==ary of the experience levels of the B&W instructors who conduct instruction on our simulator. This information combined with the description of our simulator facility forwarded to you on January 15, 1973 should provide a comprehensive picture of our capsbilities to train nuclear power plant operators.

In addition, this information provides an up-to-date status of our meeting ti.e considerations specified in Mr. Frank L. Kelly's letter to Mr. James C. Deddens of December 20, 1968.

Very ur

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111ott Manager - Nuclear Training NSE/ea Enclosures (2)

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bec:

J. C. Deddens G. J. Stoll f[/

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ENCLOSURE I o

" LICENSE TRAINING PROGRAMo i

COLD PURPOSE

]

This program is intended to prepare a power plant operator to become a licensed reactor operator or senior reactor operator under the provision j

of Section 55.25(b) of 10 CFR,'Part 55.

APPLICABILITY

~

y The cold license training program is required for all candidates for reactor

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operator or senior reactor operator license for each new nuclear power plant.

i Depending upon the qualifications of individual candidates who have had previous nuclear power plant operating experience, portions of this program may be waived by the USAEC on a case by case bases for specific individuals.

1 PROGRAM q

}

The " cold" license training program consists of five (5) phases, and they are normally completed in order. The specific

• phases are:

Phase I Basic Nuclear Theory Phase II Nuclear Power Plant Operation, Observation Phase III PWR Technology Phase IV Nuclear Power Plant Simulator Operation Experience Phase V On The Job Experience Phase I A course of classroom study comprised of basic physics, mathematics, heat transfer, fluid flow, and plant operations.

Phase II & IV Operational experience gained in actually being involved with operation of a power plant and operating a nuclear power plant simulator. For those trainees who do not gain sufficient actual reactor operatinF experience during the Phase II portion of the program, an operational period on the B&W Training Reactor will be required in order to be eligibic for examination as a " cold" license candidate.

Phase 4I1 The presentation of the design details of how the specific nuclear steam supply is constructed and how operating systens accomplish their functions.

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Phase V On the job experience, gained while operating their own plant during the test programs and writing operating and test procedures.

i The specific details of each of these programs are contained in the following sections.

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(Program 0 - )

COL'RSE DURATION - 13 weeks, 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> / week classroom time.

TRAINING LOCATION - Customer's discretion.

l PURPOSE - To provide the prospective nuclear power plant operators with a basic foundation in nuclear engineering, reacEor theory, and nuclear physics so that he can successfully pursue later phases of instruction covering operations, construc-tion, technical specifications and operating and casualty procedures of a nuclear power plant.

APPLICABILITY - High school graduates, with demonstrated aptitude in mathematics, chemistry and physics.

COURSE CONTENT - Covers basic subjects in areas of mathematics, atomic physics, reactor physics, heat transfer, introductory nuclear instrumentation, shielding,

and health physics, as outlined below:

Estimated Subject Matter Time, Hr.

Arithectic Computations, exponentials, roots, logarithms, math tables, slide rule usage, curve plotting.

15 Algebra Notation, addition and subtraction, factoring, fractions, squares, cubes, solutien of equations, simultanecus equations.

30 Trir.cnome trv Definitions of functions, angles, plane triangles, trigo-nonetric tables.

15 Introduction to Calculus Derivatives and differentials, integration, series, tables of derivatives and integrals, approximate methods of in-tegration, ordinary differential equations, graphical rep-recentation of variables.

10 Atonie Physics Atomic nature of matter, nuclear characteristics of the elements, fundanental particles and rays, radioactivity j

and decay, induced nuclear reactions.

60 l

Penctor Physics l

Terminology, fission process and chain reactiens, properties i

of neut renn. nu!tiplication f actors, crf ticality, fi-nnd i wr, m W r cperatien and control, reactivity, r_activ't}

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Estimated Subject Matter Time, Hr.

Heat Transfer and Fluid Flow Thermal properties of bodies, gases, vapors, transmission i

of heat by conduction and convection, viscosity, pressure, liquids in motion, steam and compressed liquid tables, ex-Pansion of gases and vapors, application to. reactor design.

75 t

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r Introduction to Nuclear Instrumentation Radiation detectors, principles of operation, radiation detector types, pulse-type neutron detectors, integrating detectors, detector design factors, ion current measure-t ment, scales and counters, typical systems.

30 i

Shieldir2 Functional requirements,' sources of radiation, materials and shielding types of various radiations, shielding geom-etry, principles of shield design.

30 Health Physics and Radiation Safety i

Health physics practices, biological effects of radiation, radiation units and dosages, exposure levels, review of federal regulations.

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PHA II - PRACTICAL OPERATING EXPER CE (Program 0 - i 1

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' COURSE DURATION - Trainees / Class - 8 Weeks /40 Hours Per Week APPLICABILITY - Personnel without prev'ious nuclear control room experience PROGRAM - Preplanned program of system tracing and evolution observation of the operation of a commercial nuclear power plant under supervision of full time i

B&W coordinator.

TRAINING LOCATION - At ar. operating PWR utility power plant, preferably with B&W l

supplied NSS.

DESCRIPTION This program is a familiarization phase designed to satisfy U.S. Atomic 4

Energy Co= mission requirements concerning practical experie,nce and to provide the trainee with an insight into actual operations and procedures in an operating utility type nuclear power plant.

The full time B&W coordinator will schedule classes, designate instructors, validate and sign off preplanned program check-lists, generate necessary docu=enta-l tion and generally ensure that the trainees become familiar with operations within and outside of the control room.

It has been the policy of the USAEC to give credit for previous w.: lear experience.

If in their opinion the trainee's background meets the intent of th'is program, the requirement to complete this phase may be waived by the USAEC.

The choice of plant is at the customers discretion; however, we will assist the customer in making the necessary arrangements if desired.

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' PHASE III - Pk'R TECHNOLOGY (Program 0 - )

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COURSE DURATION :- 6 weeks, 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> / week, classroom time, 28 men / class.

TRAINING LOCATION - Nuclear Training Center 4

DESCRIPTION - This phase of operator tra ning is designed to provide an in-depth i

series of lectures covering design and operation of the particular B&W plant the J

trainees will operate. This program is normally presented at the Nuclear Training u.

j Center in Lynchburg, Virginia.

A Training Supervisor is assigned to your group of operators when they arrive f

at the training center in Lynchburg for the beginning of Phase III. The supervisor's duties include preparation of course material, arrangements for instructors and classes, setting up special tutoring sessions, and generally assisting the trainees, singly and i

1

.as a group.

j The heavy investment in and concentration of unique facilities and staff, such as_the PWR simulator, Lynchburg Pool Reactor, modern classrooms, and instructors I

with design,and service experience, make the training center at Lynchburg, Virginia, j

an ideal location for this phase of-their training. However, we can negotiate'to l

provide this program at any location desired by the customer.

The trainees will apply their experience as power station operators and begin to use the knowledge gained in earlier phases of the training program. They learn how reactor physics, heat transfer, and fluid flow principles are factored into the design of the nuclear plant. They e.re given an insight into the safety requirements for and descriptions of potential plant accidents and hazards. After studying applicable codes and regulations, they will better understand the need for the adminis-

trative and design limitatior.s on the operation of the plant. Generally, they learn the similarities and diffr.rences in nuclear and fossil-fired power stations.

Operating personnel are instructed in the detailed design and characteristics of the rajor componen'.s of the nucicar stec: supply systec. /.11 facett, of the inntre-l i

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- Q features of these systems.

Instruction is provided in water chemistry, radiochemistry,l and health physics, as applied to the operation and maintenance of a nuclear plant.

1 The refueling procedure and the, operator's role in this operation are discussed.

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Fundamentals of operating the plant are taught, and operators are informed of the normal and emergency operating characteristics, response, and capabilities and l

limitations of the nuclear system. Finally, the precritical and posteritical test programs are studied in detail.

Estimated 1

Subject Matter Time, Hr.

Reactor Physics f

Review of reactor physics as applied to the specific plant design.

15 i

Heat Trtr.sfer and Fluid Flow l

Review of the nuclear plant design, design objectives, re-actor design considerations and limitations.

15 Reactor Vessel and Internals j

1.

Reactor vessel design, materials, fabrication, in,

spection, NDTT.

2.

Reactor internals description, design, materials, purposes.

3.

Design and fabrication of fuel elements and control rods.

7 - 1/2 Primary Loop Components 1.

Simplified two-loop heat transport system.

2.

Description of piping, pumps, and pressurizer.

3.

Design considerations, analysis performed, materials.

15 Once-Through Steam Generators Description, peculiarities, heat transfer characteristics, mechanical design considerations, materials, chemistry necessities, maintenance.

15 1

4 Reactor Auxiliary Systems 1.

Functional requirements (normal and emergency).

2.

Design objectives and criteria.

3.

Design approach and analysis.

1 Estimated Subject Matter Time. Hr.

i 4.

System-by-system description, equipment descrip-tion, arrangement, parameters.

5.

Equipment access and maintenance 30 Control Rod Drives 1.

Description of drives.

c.

2.

Description of controls.

7 - 1/2 Instrumentation and Control 1.

Functional requirements and description.

2.

Integrated plant control system.

3.

Nuclear instrumentation and reactor protection system.

4.

Pri2 nary loop non-nuclear instrumentation.-

5.

Reactor auxillaries non-nuclear instrumentation.

6.

Incore monito::ing system description and, function.

7.

Automatic data logging and on-line computer re-quirements.

30 1

Nor1nal and Emergency Power Requirements j

1.

Description of functional needs.

2.

Procedures.

7 - 1/2 Chemistry i

1.

Water chemistry application to the nuclear plant.

2.

Radiochemistry measurements.

3.

Sampling and chemical analysis.

7 - 1/2 1

Health Physics l

1.

Radiation monitoring systems.

2.

Decontamination methods and precautions.

3.

Administrative proce dures and controls.

7 - 1/2 Safety Analysis 1.

Potential plant accidents and hazards.

2.

General public protection and acceptance.

3.

Administrative safeguards.'

4.

Accident analysis (MllA, MCA, reactivity accidents, equipment failures such as loss of coolant flow).

15 Examination and Review 7 - 1/2 Total 180

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l PHASE IV - PWR OPERATION l

(Program 0 - )

GENERAL DESCRIPTION:

1 This phase is an operational period in which classroom lectures and the e.

B&W PWR simulator are used to provide a coordinatad training effort in nuclear power station operation. This program when combined with Phase II training provides operational experience required to meet the requirements expressed in USAIC Regulations Title 10, Part 55, Paragraph 55.25b. This period of training is directed toward the understanding and actual completion of opera-tional procedures as.they would be accomplished at a nuclear power station.

The training consists of five weeks of instruction, split between classroom and operation of the PWR simulator and two weeks of shift operation, followed by an AEC type written and operational examination.

This program will thoroughly indoctrinate each man in the duties of his watch station. Af ter first learning the details of plant design and construc-tion and the theory of operation in Phases I - III, the trainee is now schooled in the practical conduct of plant operations. During the two week period of shift operations, the actual shift crews will operate the PWR simulator control room as if it were a unit in commercial operation. They will complete all shif t functions and make all decisions on plant operction, as they will be required to do in the actual plant. Operational responsibility will be greater than that experienced at any power reactor.

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-a-l Training in malfunction and emergency procedures is possible on the PWR

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i simulator to an extent impractical on an operating reactor. The instructor will carefully probe the level 6f knowledge of each operator by interjecting I

i various system and component failures into plant operation. Major malfunctions that cannot be conducted on an operating reactor will be possible on the PWR i

simulator in complete detail. Completion of this training program permits the operator to observe the responses of a PWR nuclear steam supply system to both a

normal and abnormal conditions. This program demands response of an operational nature from each operator, for it is the operator who must make the necessary 4

decisions and initiate the required actions under actual plant conditions.

i i

i DETAIL COURSE DESCRIPTION l

Course Duration: 8 Weeks Class Size:

6 Men Per Class 3

5 Training Location: Nuc1 car Training Center f

Simulator Operation: 100 Hours (Minimum)

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a During this portion of the program, the trainees will be broken 1nto groups i

i of three for duty in the control room where each trainee vill operate the simulator at each of the three operating positions. Approximately one third of the time will be spent as Shif t Supervisor, Control Operator and Assistant Control Operator.

I During the first five weeks the emphasis will be on operational orientation where the trainee will concentrate on learning the basic operations of the plant including casualty procedures.

The second part will consist of two weeks of shif t operation where the trainees will operate the plant with minimal instructor assistance.

They will perform.

assigned evolutions and handle imposed casualties to develop confidence in their 4

ability to handle a plant under all conditions. During this phase, day to day ptonress of each trainee vi.11 be documented and evaluated with group and individual

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CLASSROOM INSTRUCTION - 170 Hours l

An essential supplement to simulator operation is the related classroom instruction provided in this phase. Lectures will be given to review plant systems from.an operational and funct fonal view point rather than plant design.

Areas covered will include:

e Pluid Systems Control Rod Drives Nuclear Physics Review Plant lustrumentation and Controls Reactor Protective System Reactivity Balance Soluable Poison Calculations Plant Operating procedures will be presented in a planned sequence along l

with actual operations on the simulator. The following operations will be presented:

1 Start Up Reactivity Control l

Power Operations Transient Control Loss Of Load j

Reactor Trip Casualty Procedures As with simulctor operations, progress and study in this portion of the progra:

i will be documented and appropriate assistance and counseling will be provided to the trainees.

SIMULATED AEC TYPE EXAMINATION AND REVIEW - 40 Hours This portion of the program will consist of a conplete examination by an experienced audit team of B&W staff cembers who have not been previously involved with training of the group.

These examinations vill closely simulcte USAEC operater

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examinations and the~results of these examinations will constitute an audit of individual and group competence.

This audit will be reviewed with plant management to appraise them of strengths j

.and weaknesses in their operating staff.

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TOTAL COURSE:

Lectures, Observation, Study and Counseling 170 Hours Simulator Operation 100 Hours l

T Examination, Reviews and Examination Preparation 40 Bours Total 310 Bours l

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O PHASE IVA -PVR OPERATION (B&W NUCLEAR TRAINING REACTOR OPERATION)

(Program 0 -

Optional) l j

COURSE DURATION - 2 Weeks i

a CLASS SIZE - 6 Men Per Class l

TRAINING LOCATION - B&W Nuclear Training Recctor - Lynchburg Research Center PURPOSE' i

i 1

This program is intended to supplement the eight week Phase IV - Simulator Program 0 -

for those trainees without prior nuclear experience, and who have not had actual start up experience on a real reactor.

l Trainees will operate the B&W Nuclear Training Reactor in at least three different core configurations, and will get a minimum of tdn start ups each.

1 Areas covered will include:

Control Rod Calibration 1

Increase Multiplication With Rods Increase Multiplication With Fuel Power Distribution Measurements Detection Systems Basic 11ealth Physics i

Reactivity Effects It is recommended that this program be included in the simulator training program as it will serve as an excellent review of reactor theory in a laboratory i

environment. Experienced operators will find the course stimulating and very vorthwhile.

If the course is selected it will be integrated into the custo=ers l

Phase IV simulator program, making the entire program ten (10) weeks in duration.

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PHASE V - ON-THE-JOB TRAINING j

(Program 0 - )

l COURSE - Approximately ten months TRAINING LOCATION - Job Site DESCRIPTION I

A resident on-site B&W Training Coordinator knowledgeable in design and I

operation of the nuclear plant will assist the plant superintendent in establishing i

an effective program during this final phase of operating staff training.

i The B&W Training Coordinator will tailor our' complete preplanned package to

{

suit the requirements of your particular plant. His responsibilities will include:

1.

Scheduling 2.

Training Records I

3.

Evaluations 4.

Assistance in development of lesson plans 5.

Assistance in locating outside resources when required f

6.

Evaluation of instructor presentations 7.

Reports 8.

Reviews and preparation for USAEC " cold" license examinations 9.

Development of a plant training program-During this phase of the program as fuel loading iIs approached a " cock" AEC written examination and walk-through oral examination for each license, applicant by a team of B&W examiners will be conducted. The results of this examination will be used to advise the trainees and their management of possible areas of weakness that should be corrected before taking the USAEC " cold" license examinations.

1 ENCLOSURE II CALVIN E. GOS PROFESSIONAL EXPERIENCE l

1.

Operating Experience:

Senior Reactor Operator License,for H. B. Robinson, Unit #2.

(SOP 1360) l a.

l b.

Senior Reactor Operator License for CVTR.

(SOP 747) c.

Reactor's Operator License for CVTR.

(OP1791) d.

Carolinas / Virginia Nuclear Power Associates, Shift Supervisor - Charge of reactor operation, on shift, of a Prototype Power Reactor. Supervised the plant during periods of critical testing, power operation.

Carolinas / Virginia Nuclear Power Associates, Reactor / Health Physics Techni-e.

cian - Operated the controls of a Prototype Power Reactor. Responsible for radiation control on shift. Performed routine surveys, sampled radioactive waste for release, issued radiation work permits, and provided health physics

coverage, f.

Carolina Power 6 Light Company, Control Operator - Ope' ated the controls of r

a steam generating plant, maintained operating records and was responsible for the operation of the switchgear. Assisted in the start-up of a 650 Mwe generating unit.

g.

U.S. Navy, Boilerman. - Qualified nuclear plant operator, and Engineering Laboratory Technician at two Navy reactor facilities.

Served as a Boileman on a Destroyer.

2.

Support Exoerience.

Carolina Power 6 Light Company, Radiation Control and Test Foreman - Organized a.

and supervised the Radiation Control and Test Group at a large power reactor.

b.

Supervised the start-up test group. Directed construction follow-up, equip-ment check-out, and procedure writing.

c.

Served on the Plant Nuclear Safety Committee. Review all operating and test procedures, unusual occurrences, safety related incidents, and plant operation in general.

d.

Co-authored the Plant Radiation Protection Manual.

3.

Training Experience:

Supervisor Classroom Training, Babcock 6 Wilcox Company - Responsible for a.

supervision, scheduling, documentation, material preparation, and development of classroom training programs.

b.

Babcock 6 Wilcox Training Instructor - Conducted training on a PhR Simulator; l

including classroom Icctures, simulator operation, and test preparation for l

nuclear plant staff training.

~

l

. Q Radiation Control and Test Foreman, conducted the Padiation Control Traini..

c.

Program for plant personnel. Supervised in-plant, on-the-job training of l

plant operators during initial construction phases, d.

Shift Supervisor, responsible for on-shift training of plant operator in Reactor Operation, Health,Physich, and Industrial Safety.

4.

Related Experience:

Supervisor Classroom Training / Training Instmeter, audited Phase II, III, IV, a.

and V training programs for plant operators.

4 9

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o PHILLIP E. GRIFFI'IH'

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PROFESSIONAL EXPERIENCE i

1.

Power Plant Operating Experience:

i i

a.

USS Nautilus - Reactor Opsrator 148 months), Electric Plant Operator and Reactor Plant Mechanical Watchstander.

Including one major overhaul and one refueling.

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2.

Power Plant Support Experience.

l USS' Nautilus - Electronic technician - Responsible for maintenance and a.

upkeep of all Reactor Control Instrumentation and Control Equipment including two major overhauls.

b.

Babcock 6 Wilcox Company - Preparation of plant operating procedures for mechanical and Instrumentation and Control Systems for Oconee Unit One.

3.

Instructor Experience:

USS Nautilus - Responsible for instruction and qualification of Reactor Operato:

a.

and Technicians.

e i

b.

Babcock 6 Wilcox Company - Instructor classroom Phase III training for B6W i

customers in Instrumentation and Controls and Plant Operations.

1 c.

Babcock 6 Wilcox Company - Instructor 850 hke class nuclear simulator, including classroom and control room instructions.

l 4.

Other Related Experience:

a.

Bailey Meter Company - Processing Reactor Protection Systems, including preparation of system schematics, calibration data, And technical manuals.

Also preparation of technical manuals for Engineered Safeguards Systems.

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AREUR OXFURTH PROFESSIONAL EXPERIENCE 1.

Power Plant Operating Experience:

a.

U.S. Navy, Leading Petty Officer Reactor Control Division. Reactor Operator (44 months) - Supervisor of maintenance / operation of reactor control / reactor protection instrumentation.

2.

Power Plant Support Experience:

a.

Babcock 6 Wilcox Nuclear Service Engineer - Preparing plant operating proce-dures and test specifications for B5W customers.

b.

VEPCO, Surry Nuclear Power Station, Instrument Technician - Responsible for maintenance of Westinghouse nuclear instrumentation, Teleflex incore flux mapping system, Hagan process control instrumentation, and auxiliary systems.

Westinghouse P-50 conputer (W-251-AA Gas Turbine), electropneumatic instnt-ments and controls (W-191-G Gas Turbine).

U.S. Navy, Leading Reactor Control Petty Officer - Responsible for maintaining c.

reactor control and nuclear instnimentation equipment'(Submarine Prototype Nuclear Propulsion Plant).

3.

Instructor Experience:

a.

Babcock 4 Wilcox Company, Instructor for Nuclear Training Center.

b.

Training Coordinator Practical Operating Experience at H. B. Robinson, Unit

1. 2 for Arkansas Power G Light and Duke Power Company.

Training Coordinator PWR Technology Course at Toledo' Edison Company.

)

c.

d.

U.S. Navy, Instructor - Responsible for instructing reactor control and nuc1 car instrumentation equipment (Submarine Prototype Nuclear Propulsion Plant).

4.

Other Related Experience:

Conducted audits for Phase II, Practical Operating Experience Program for a.

Toledo Edison Company engineers and operators.

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80B D. Ra m s

' PROFESSIONAL EXPERIESCE 1.

Power Plant Operating Experience:

a.

Reactor Operator, SL-1 Nuclear Power Plant, Idaho Falls, Idaho b.

Shift Supenisor, PM-3A Nuclear Power Plant - Supervised a shift during plant construction and testing. This' included factory assembly and testing, ship-ment and reassembly of the plant at McMurdo Station, Antarctica.

Shift Supervisor, SM-1, Nuclear Power Plant - Progressed from initial assign-c.

ment as Training Equipment Operator through qualification as Equipment Operator Control Room Operator aniShift Supervisor. Responsible for all plant opera-tions and testing during my assigned shift as Shift Supervisor.

1 1

2.

Power Plant Support Experience:

hhintenance and Supply Supervisor, PM-3A Nuclear Power Plant - Supervised a.

instmment, electrical and mechanical maintenance technician in performance s

of preventive maintenance, plant modifications, repairs, and testing of all plant components and systems.

b.

Assistant Project Engineer, PM-3A Nuclear Power Plant - Assisted the Project -

1 Engineer in providing engineering support for Operation, maintenance and modification of the Navy's Nuclear Power Plant, McMurdo Station, Antarctica.

Drafted specification for engineering support contracts, reviewed reports and procedures submitted by various engineering branches and contractors and monitored contracts and in-house engineering studies from conception to completion.

Represented the Navy during test, modification and fabrication of plant components at civilian manufacturing fims.

Supervisor, Mechanical Maintenance at the SM-1 Nuclear Power Plant..

c.

d.

Senice Engineer, Nuclear Service - Responsible for preparing plant operating procedures and test specifications for Babcock 6 Wilcox customers.

3.

Instructor Exoerience:

Instructor and Supervisor, Replacement Crew Training for the PM-3A Nuclear a.

Power Plant, McMurdo Station, Antarctica - Responsible for development of initial training program and for teaching the Nuclear Steam System, Components, cnd NSS. Auxiliary Systems.

b.

Instructor, SM-1 Nuc1 car Power Plant - Instructed Nuclear Power Plant Operators Course trainees during the operations phase of their training.

Positions in-cluded Equipment Operator, Reactor Operator and Shift Supervisor.

Instructor and Supervisor at a 850 We Nuclear Power Plant Simulator Instruc-c.

tions at The Babcock 6 Wilcox Nuclear Training Center.

d.

Instructor for Pressurized Water Reactor Technology Course (Phase III) for customers, operators, and engineers.

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1 4.

Other Related Experience-Training Programmer and Coordinator, Naval Nuclear Shore Power Program -

a.

Responsible for postgraduate assignments of Naval personnel to operating plants in the Nuclear Power Program and for ultimately providing a well-balanced and well-trained, relief' Crew for the PM-3A Nuclear Power Plant, McMurdo Station, Antarctica on an annual basis.

Provide guidance for preparatory study programs and counsel students during the 52 week Nuclear Power Plant Operators Course (NPPOC). Voting member of Academic Review Board for the NPPOC.-

b.

Training Auditor - Prepared and administered typical AEC written examinations for potential Duke Power Company Reactor Operator and Senior Reactor Opera-tor candidates. Prepared and administered typical AEC oral examinations for potential Duke Power Company Reactor Operators and Senior Reactor Operators

" cold" license candidates.

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/g PROFESSIONAL EXPERIENCE 4

1.

Power Plant Operating Experience:

a.

SM-1 hbclear Power Plant, Fort Belvoir, Virginia - Served as Shift Supervisor (30 months), Reactor Operator (8 months) and Auxiliary Operator (4 months).

b.

PM-3A Nuclear Power Plant, McMurdo Sound, Antarctica - Served as Shift Supervisor (10 months) and Reactor Operator (2 months).

2.

Power Plant Support Experience:

a.

Served as Operations Supervisor at the PM-3A Nuclear Power Plant and Water Desalinization Plant.

b.

Served as Maintenance Supervisor at the PM-3A Nuclear Power Plant and Water Desalinization Plant. Directed electrical, instmmentation, and mechanical technicians in preventive and scheduled maintenance, overhaul and plant modifications.

3.

Instructor Excerience:

a.

Instructor, Babcock and Wilcox Nuclear Training Simuistor.

Instruct potential nuclear power plant operators on the operation of B5W's Pressurized Water Nuclear Steam System, b.

hhile serving at the SM-1 hbclear Power Plant, I was responsible for instructing officers and civilian personnel undergoing Nuclear Plant Engineer and Officer in Charge courses of instmetion. Substituted for the Operations Supervisor during his temporary absence.

4.

Other Related Experience:

a.

Served as Senior Enlisted Advisor and Training Programmer for the Navy's Shore Nuclear Power Drogram.

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'7, 1973 4

Mr. Paul Collins Chief, Operstor Licensing Branch U.S. Atomic Energy Coc=ission

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Vashington, D. C.

20545

Dear Mr. Collins:

Enclosed is a copy of Babcock & Wilcox's proposed rapiscement operator training program for hot licensing candidates.

I request that you 1

review this progrsm for its general content. This program appears to be highly desirable for Babcock & Wilcox customers, and we are interested in providing this type of service.

The classroom schedule is under review and development of outlines and slight modifications are expected to be made. You will be advised as to the final program that is developed.

Very t ly 1

/

N. S Elliott, Manager Nucle aining NSE/en Enclosure k

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• O REPLACEME!.*T OPERATOR TRAININO U

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CLASS DURATION 10 vecks (Part I - 4 vecks, Tart II - 6 veeks)

TRAINING LOCATION: BLW Nuclear Training Center, Lynchburg, Virginia DESCRIPTION: The purpose of this program is to supplement a utility training program with a concentrated classroom program of nucicar supply system instruc-tion and operational experience gained frem operating the D&W nucicar power plant simula tor.

This program vill provide instruction for nucicar plant auxiliary operators so that they vill be adequately prepared for the AEC Reactor Operator examination. The prcrcquisites for,this program include:

1.

Ccmpletien of a Comprehensive Basic Nuclear Theory Course (tak' Program 4 or the equivalent).

2.

Com;,1ction of a program to develop experience as a T:cactor Operator Under Instruction which will include a nu=ber of significant reactor ;,ower chan;;cs.

PROGRAM: The replacement operator program is divided into two part which are conducted separately but are mutually dependent. Part 1 is a classroom presenta-tion of the systems and components which mahcup the nucicar steam supply and its instrumentation and control equipment. Part 2 in the practical application of knowledge of the nucicar steam supply systems to operation of tne BLW nucicar steam supply simulator.

PAi.T I - Noelcar Steam _ Suppl $' Systems (4 vecks - maximum of 12 studenta per greur)

This part provides a series o l Icetures covering design and operation of the particular plant the trainees will operate.

Operating personnel study the detailed designs of the msjor components of the nucicar system and their various characteristics. All f acets of the instrumenta-tion and control systems arc studied to give each student an operational knoviQe of"these systems.

1.'ater chemistry, radiochem'istry, and health physics are stud!<.d in relatienship to their appli'catien to the operation cf a plant.

The subjects cevered during Part 1 are shown below:

Esti=ated S idect :'at ter tirc. h r. _ _,

l Evacter Vessel and Internals....

7 1.

Rea: tor vessel design, r.sterial:.. MDT!.

2.

T:caetor intern.ais descriptien, ass.e.bly, and rurretes.

3k 0 0440 0-08A91N '

3.

ss;cn, componcr.t pits, and centrcl reds.

8 Esticated

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Subject Mattar tiae. hr.

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Primary Loop Components.......................... 6 i

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1.

Simplified two-loop heat transport system.

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Description of piping, pu=ps, and pressurizer.

l Steam Cenerators.............................

4 I

Description, peculiaritics, heat transfer characteristics, mechanical design.

Reactor Auxiliary Systems.............. '....

28 1.

Functional requirements (normal and emergency).

2.

Design objectives and criterin.

3.

System-by-system description equip =cnt description, arrange =ent, parameters.

Control Red Drives.

6 1.

Description of drives.

2.

Description of controls.

Instrtmentation and Control............"...........

28 1.

Functional requirc=cnts and description.

2.

Integrated plant control system.

3.

Nuclear instrumentetion and reactor protection system.

4.

Primary loop non-nucicar instrumentation.

5.

Reactor auxiliaries non-nuclear instrc=cntation.

6.

Incore conitoring system description and function.

7.

Automatic data logging and on-line ce=puter.

l Che:12try.

4 1.

Liter chemistry expected pricary and secondary values.

2.

Changes in radiochemistry with life and malfunctions.

3.

Chemistry casualty conditiens and necessary actions.

Walth rhysics..............................

6 1.

P.adiation conitorin; syste:s.

2.

Decentaminatien eethods and precautions.

3.

Mni: istrative precedures and controls.

S t.i t t en 1 ; c e t r i c rew r..........................

4 1.

L'istritutien Systtr..

2.

Sy::ter Interie:*.s.

(

'O Esti: aged s

d ','

time, hr.

Subject Matter fvi 19 kN

S a f e ty Ana ly s i s.................

1.

Review of applicable reactor theory, heat transfer, and fluid flow.

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Potential plant accidents and ha:ards.

3.

Ad=inistrative safeguards.

4.

Accident analysis (MHA, MCA, reactivity accidents, equipment failures such as loss of coolant flow).

8 Examination and Reviev.........................

40 Supervised Study...

PAP.T II - PWR 0seration (6 vecks)

This part of the total progran provides the operational experience on the E6*'

simulator which vill allev the trainees to becc:e proficient reactor operators.

This part of the progran is dependent upon the trainees ce=pleting Part I of the progrc where the detailed knowledge of plant syste s is presented.

Instruc-tien vill be entirely involved with plant operation in nereal plant codes (manual, 5

partial auto =atic and full autocatic centrol), abnormal aquipment configuration operation, and casualty control. The students will be given an audit (cock),

written and perfornance exan to prepare them for their ifcense examination. The last week of the progres is set aside for preparation and conduct of Reactor Operator exa=inations which the purchaser should schedule with the USAEC Operater 1.icensing Branch.

Esticated Subject !atter tice. hr.

100 Simult. tor Operation.

The trr.incts are brchen into treups of three for duty in the control rect with cach trainee operating the sfeulator at the cach of the three crerating positiens. A;pec:<inntvly ene-third cf cach traince's ti=e vill be spent vorhine, as Shif t Supervi:;.*r, cr.e-third as Control Operator, ced the fint.1 third as Asti<ttnt Contrel C,wrr.tcr.

Ourin,: ti.cre sin vechs, the c.ph cis :s en epcrationni orientation with the trainte con:entratin; en lestnin; the be. sit operations of the plant, in:1udin'; car.ualt;. ;recedures..

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timt. hr.

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8 Subioet Hatter 86 k,:. -

Classroom Instruction.......................

Plant operating procedures are presented as a planned sequence 1

i Operations coinciding with actus1 operations on the simulator, I

included in this sequence include startup, reactivity control, t

l power operations, transient control. loss of load, reactor trip, and casualty procedures.

Study Time AEC-Exacination and Review.......******.

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P.O. Bc 1260.hree..gm pag $

feiepnoae::304) 234 $g 3 3 August 30, 1974 l

Mr. Paul F. Collins Chief Operator 1.icensing Brar..h U. S. Atomic Energy Consnission Washington, D. C.

20545 Dear Mr. Collinst In reference to our recent conversation with respect to the conduct of the reactor operator's certification examination on the Babcock &

Wilcox simulator, we will be conducting a training program for the Duke Power Company Oconee station during September,1974 which will include at least that amount of instruction as described in my letter 9 H (14) AEC 1-74 dated August 30, 1974.

It is my understanding that the Duke Power Conapny will submit to you a description of the total training program for these operators who 9111 be in our September class.

l The reactor startup examinations for the Duke operators will oe l

given on Friday, September 13 and September 27, 1974. Your attendance for observation or participation in these examinations would be veicomed.

The Duke Power Company plans to provide a management representativa to observe the conduct of examinations on both dates shown.

/

Very truly yours /. Ahd

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Nprman S.11110tt Hansger, Nuclear Training NSE/ph 2 oopo2 cost >

bP 0014000').o te em.. u.c. come-,. tu v.,s :m F/&

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,4 UNITED STATES M

ys NUCLEAR REGULATORY COMMisslON

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WASHINGTON, D. C. 20555

%, ",O December 15, 1976 NOTES FOR ATTENDEES AT THE NOVEMBER 30, 1976 MEETING OF THE INTEROFFICE QA TASK FORCE TO DISCUSS QUALITY ASSURANCE PROBLEMS.

Those in attendance at the November 30, 1976 meeting were W. M. Morrison, J. L. Milhoan, SD; J. H. Sniezek, Mr. Peranich, IE; J. G. Spraul, R. J.

Bosnak, R. Kirkwood, NRR.

Two problem areas were discussed during this meeting; the first being the fact that quality assurance requirements for Class 3 items now included in the ASME Boiler and Pressure Vessel Code,Section III, do not appear to comply with the requirements of Appendix B to 10 CFR Part 50 and second, a proposal submitted by the ASME Section III Division 1 and 2 Work Group on Quality Assurance and Stamping to make the provisions of the Code, NA 4000, conform to the provisions included in Criterion I of Appendix B was rejected at the Subgroup on General Requirements level. Action to resolve these two problems is as indicated below.

It was agreed that Bosnak as a member of the Subgroup on General Requirements would send a letter to Dobel, Chairman of this Subgroup, in which he would recomend specific changes that were required in the Code so that quality assurance requirements for Class 3 items would conform to Appendix B requirements. Target date for submittal of this letter is January 14, 1977. A proposed draft of this letter is included as an enclosure. Attendees are requested to send comments on this draft to Morrison by January 5,1977.

With regard to the proposed changes to reflect the Appendix B Criterion I provisions, it was agreed that Bosnak would contact Dobel to find out specifically what the problem was with the Subgroup on General Require-ments non-acceptance of the wording. Subsequent to conversations of (1) Bosnak and Dobel, and (2) Bosnak and Milhoan, it was decided that a letter would be sent to the Chaiman of the Work Group on QA and Stamping proposing a resolution of problems of the Subgroup on General Requirements. A proposed draft letter from Milhoan, a member of the

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Work Group on Quality Assurance and Stamping to Gibbons, Chairman of j

this Work Group, is attached. Comments on this draft should be pro-vided to Morrison by January 5, 1977.

j i

The next meeting of the QA Task Force will be held on January 13, 1977 at 9:40 a.m. in Room 6507 Maryland National Bank Building.

b' $ $ G1A 41 *1 W. M. Morrison, Chairman Interoffice Quality Assurance Task Force

Enclosures:

1.

Draft letter to H. Dobel with enclosure 2.

Draft letter to W. Gibbons with enclosure cc: w/ enclosures L. V. Gossick B. C. Rusche E. Volgenau K. Chapman S. Hanauer E. Case C. J. Heltemes D. Skovholt B. Grier (7)

R. B. liinogue G. A. Arlotto M. Kehnemuyi W. Morriso '~

K. Steyer J. Milhoan 3

W. E. Campbell, Jr.

J. H. Sniezek J. G. Spraul R. J. Bosnak R. Kirkwood M. Peranich A. T. Clark H. George 5

e_a a-,,A E

e COMMITTEE COMESPONDEiUCE

'~

SOCIETY / COMMITTEE:

ADDRESS CORRESPONDENCE TO:

ASME Boiler and Pressure Vessel Code R. J. Bosnak Section III Division 1 and 2 Mechanical Engineering Brarch Division of Systems Safety Subgroup General Requirements Office of Nuclear Reactor Regulation U.S. NUCLEAR REGULATORY COMMISSION

SUBJECT:

Consideration of Class 3 Quality WACHINGTON, D.C.

20555 Assurance Requirements i

AGENDAITEM:

GR 76-19 DATE:

FILE NO.:

N/A l

TO:

Mr. H. Dobel, Chairman ASME Boiler and Pressure Vessel Code Section III Division 1 and 2 Subgroup General Requirements Babcock and Wilcox Company P.O. Box 1260 1.ynchburg, Virginia 24505

Dear Mr. Dobel:

My letter to you of June 8,1976 indicated that merr.bers of the Regulatory Staff were concerned regarding the'quaN t'y assurance requirements included in the Code for Class 3 Items.

It may be helpful if I summarize this concern as a preclude to suggesting a method for resolution. Regulatory Guide 1.26 indicates that the Class 3 technical requirements of the ASME Code should be applied to certain components and systems. Regulatory Guide 1.29 indicates that many of these same components and systems should be designated as Seismic Category I.

Regulatory Guide 1.29 further states that the pertinent quality assurance requirements of Appendix B to 10 CFR Part 50 should be applied to all activities affecting the safety-related functions of these items. Our review of t'he quality assurance requirements presently included in the Code for Class 3 items indicates that not all of the pertinent requirements of er-90BNN NRC FORM 158

r:;

! l Appendix B to 10 CFR Part 50 are applied. Examples of deficiencies j

in this regard were included in my June 8,1976 letter to you.

Subgroup item GR 76-19 has been established to address this question of coverage of quality assurance requirements for Class 3 items.

During the discussion of this item during the meeting of our Subgroup on General Requirements, it appeared that part of the problem may be classification; namely, should any safety-related l

t item of a nuclear power plant be classified as Class 3.

The question was also raised as to whether or not a less than " full blown" quality assurance program, but one which is considered to be adequate for Class 3 items, could ever be accepted by NRC.

N NRC's problem with regard to Class 3 items may well be one of classification in that it may not be intended by the cognizant code enemittees that Class 3 requirements be applied to safety-related items of the plant.

If that is the case the appropriate action for NRC would be to reclassify safety-related Class 3 items I

as Class 2 items.

It appears to us, however, that the technical requirements (as opposed to quality assurance requirements) now included in the Code for Class 3 items are adequate. Reclassifying these items up to Class 2 in order to correct a quality assurance requirements deficient.y would appear to cause the application of more stringent technical requirements than is necessary. A more desirable approach is to attempt to reach agreement on the necessary quality i

assurance requirements for Class 3 items in the Code.

l t

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. The answer to the question - Will a less than " full blown" quality 1

assurance program for Class 3 items be accepted by NRC? - is yes, l

but it requires some amplification. We agree that differences L

l should exist with regard to the extent which the overall quality l

l assurance program requirements are implemented depending upon the l

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importance to safety of the covered activity. For maximum effectiveness and efficiency, a graded approach to QA program implementation should be provided. Appendix B to 10 CFR Part 50 recognizes this concept.

For example, Criterior. II states:

"The quality assurance program shall provide control over activities affecting the quality of identified structures, systems, and components, to an extent consistent with their importance to safety." Criterion IV also recognizes that selective application of quality assuranca requirements to contractors.

and sub-contractors is necessary by stating: "Tc the extent necessary, procurement documents shall require contractors or subcontractors to provide a quality assurance program consistent with the pertinent provisions of this Appendix." Therefore, a less than " full blown" quality assurance program can-be applied to a safety-related item q

for a nuclear power plant and still meet the overall quality assurance j

program requirements of Appendix B.

l l

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4 The quality assurance. provisions included in NCA 4L 0 are basically overall quality assurance program requirements which we consider to be generally consistent with the overall program requirements of Appendix B.

It appears logical to us, then, that within these overall quality assurance program requirements included in the Code, a graded 1

-approach to the application of the program requirements is not only

)

permissible but necessary and desirable. If some of the overall program requirements are omitted, as they are for Class 3 items, it appears to us that key quality assurance provisions would ba omitted entirely. For example, there are no quality assurance program requirements for design control for Class 3 items. As I have indicated earlier, many of these Class 3 items are required to be designed to withstand the Safe-Shutdown Earthquake. 'If there is no requirement for control over the design process, what assurance is there that a Class 3 item was properly designed to withstand the Safe Shutdown j

Earthquake?

We have compared the present coverage of the Code for quality assurance requirements for Class 1, 2, MC, CS, CB, and CC construction with the quality assurance requirements for Class 3 construction. A copy of this comparison is attached. We have underlined those requirements for Class 1, 2, etc. which we believe are also necessary for Class 3 construction for safety-related components. As can be seen in this comparison, we consider that the overall quality assurance program requirements should be essentially the same for all safety-related items in the plant. As indicated above however, this does not mean

.m-

-, -, - ~., -, -

m i

that detailed implementation of these program requirements cannot provide for less stringent measures for Class 3 than for the higher classes.

I hope the above discussion clarifies our concerns regarding Class 3 quality assurance requirements.

It is requested we consider this item with a degree of urgency.

Sincerely, l

R. J. Bosnak Member, Subgroup

)

General Requirements j

i

Enclosure:

As Stated I

cc w/ encl:

W. S. Gibbons R. E. Keever j

1

)

i SD:RSSB SD:RSSB SD:ADDES SD: DES NRR:QAB IE: RIP NRR:MEB JMilhoan WMorrison MKehnemuyi GAArlotto CHeltemes BGrier RJBosnak Task No.

bec w/ encl:

DISTRIBUTION W/ ENCL:

RBMinogue DSkovhol t Central Files RGSmith CHeltemes GAArlotto BGrier MKehnemuyi JSniezek WMorrison MPeranich JMilhoan RJBosnak GMillman 1

e C Lgss I A Mc., c $, c8, 4 c.c_

class-3 t

ceu coe.an n ses..;e. a. r a NA.4134 h%r w a vai.5t9-4 -c4&aM,blal& elf Ct.AS'i 3 AertCtt 6Ca-teco (gmypesArd./ Mpese quAttif A15URAMJE a

s

,g

~~.

\\

4+

WCA*43&S kfqulkintsTE e

I' bCA-4ta$

SCDFB AeD APPLICAtlLitt

.I

+

fa)

This Article eete forth the regeleemente for pleesteg.

i f

m.*.rlet. ee8 seeduca lop Quality Assurance Prepreme for coatselling the gustit y shie bestice and the omles 34*eseleg tite evaluatise of l

el wee k p a lveaw d me ts e

...k tiersan pe sar to 86 6ee.eue of Certificates of Aethesitaties ter tre y

f ebsitat ion. one.f ac tuse and f estallaties of Cless I. 2. C3, uc.

s ets.staen.

Cs esJ &( jaeos f or Class 3 see bsA-SIP 3 and 6CA-6000. yee states tel Mesafeaturere i

8#r all steeses of senese <tlee, ese DCA-3000. Certifieste e.d.Mateesel 5.rpl eret.o. ie sa

..id.e s.ra e.eind ie.eee.it et6.s r...ieueen for...iit, e.

es.reece e.g.isemente ge=erales utleittee tegend the esere of this suf fee.

lbl the detelled regelseerste to be semptied with te feltillleg these seep,melbiliales are etapeleted le this Article.

8 bt;A-4 8 6 Da t a blil0e2 kCA-4831 Q*elity Asevesese As need to this 8estles. quality esserence eseptiese all these pleased eed sysseestis actione esseeeery to provide edegute seelidense that all itece de-sipeed. constreated. febsitated, esesf ectored or testalled esa in escardesse with the =lse of this secties. Quality aes.sease testudse 9eelity Centeel

[

tendaation e d twelity Costlet Adelaistraties.

i bCA-4121 Quality Ceettet Esseleettee Quality Coetset Esselsettee semptlses the essefeettee of the physiset shersstes tetise of e estesial, teopeseet, part er opporteenste eed the accepteece etendasde essesisted with these seenleet(see.

i eCA-4133 lb.elisy Centrol Adelaistrettee I

quality Cestsel Adsdelettettes le the eseepament sed decomentattee

.btsh ses.se e te.et the spuitted 4.ality Centrol Rosaluties le servied out.

'i l.

f DCA-4114 leentifisettee and Verificettes 1

i i

The Idestifisettee and Verif tsaalen Protree shall seatste a eyesee get the positiv. identificesien et estorial desies eterate med wesitteetles el the isentity et setselal and the acreepaarist Certified Mosesial feet tepende er Certilis ates of Cseptises at the time et ehlpeast both inte sed evt of tLe t.

(

itetesial Seg pliers warehewee.

A WCA-4131 A. Jim r

An omdit le e documented estivity perfossed la es(ordasse with writtee skettilets te vestlye by enasteettee end avelvation of objettlee nse, ti.et esplisette elemeete of the twality protree have been develept.

(

, paesed.see os e.3de de e3dlt dettuoted, eend tortemented le e6sofdante With eyes l$ied Ef qWlfeneste.

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. m.

p 1

C L rss 1,-\\ bfl, C $ CO.o

• C C-C l.hss 3 i

m...

i.,i.A.

iii.u...

..,.oi

.,,.a -. n u,. ~..

WCA-4 3 26 5.e.ey

.)

4

, s. 4 e.4 u s s.s e r. i....

....re.s..e s..*e..,..

sie

.ise r,r.sr... s

.t thev.,.si

.. abs.snes.

essais... s es.es.:

NCA-4338 ESIAeLI5Intui att InflinthTATION mCA-gl31

• h.s es !.I h..e t.cs.r.s. B6,I.4.= I -

WCA-4531.8 (Se. DCA-3800) m A-44 32 m t.siet no fesses.r. (n.setti.), si,tes 3

hCA-4933.8 (See DCA-3000)

I su-4133

. H.ieel.1 s.,pttess. Divi.t. 1 mCA-4333.1 (see aca-3000)

WCA-4134 W. urT...e NA C.s ti fle.a. M.nd.r. f.e Ct.

8,2.34. Cs,Cs. 4 CC e

.truti..

l i

f I

i t

i e

I

C LA 6s I, 51, M C, c S, C B o C C..

C Los.s 3 e,re.i...

b sce.o..

a.....ce *... e.. 6.eiYi. 4 r.emiy ine r.c is..e s. em.,,e.r f.)

"' I

• 6 * **! *a tion 8

w...mu n u < iese n e e..mi n ihe d.t.4 dae..e t ed.

A

.,gs.i,,,i, cl.a rt sheerlag the relati.sl.1P

.>e o.uir r.,.... e. u r.. i.. i... ce r t..... :. n i e r e.... m e s.ac e s.c o on.i s 6..e Lelween managcasha anel ens;lacesing. perst.an6.ag.

1 snanufacterlag. field constructLoes. Inspection, ar.it sguality ca.utral, la resguliest to reacct al.a actual o.t ric a

..e et1*de ti.e4 ner==etbitier. eiineetts..ad ertuteet ten tenes*

organisatloa. The piirpose of this chart.Is to identisy i

• nd a88** late &* various organisational groug.s with (11 Ideat i f, e.aiier pan =a Patten s llee particular finnstlen for shish they are responsin.le, p

i._n ine-are i. aicl reate e in sei.slene:

~

.e si veri t, in e tenn,t i

.c..i.e ie.o n. theo u ve6te...

j I4) ceneret 1.rther erernet g. detiwer er f astalletlen of h)

• The authority enel responsibillsY of thase in char $a s/

Apo,p.ggef e_rsian lieu. fefit semer. er ***.t ie fect ory toedit ie. until

. t 8 Elwa@y Cosettel sysitem sl+all be clearly estas.lar kee!.

s gryer disteest see hae teeie e.de.

Paret fes perferrning ggual'ty contral fuggrions sl.all ej7mmarn of ik

. tra wrence Prorre= slill be deng eeed eh.)] L t

hau sv.iticient an.: wein.Rnne.: res;-anubstity, de la. neo-ead ae@07p ai.r.=!bt.e '- **Hain "* 8 r ="~e!=a ne *e=*u a

3 muthoritye and the organlan ts.aal freedom to Id :.tliT

~

gjg 3 m re.Jent tea the vreeserte of e.eduties. shall have direct eccese

{

,e t 3,gm.uist e e.ug e.= se e in e t whn e actr.iel.e e aes te. e.. Se re. nee.

'!"*IgIf * *"I ' *I Problerns an= e. Inlitate r e c ommer.d, e

.e* entlprovide seletions.

i. ;.r

{

sid:sA ass-es t 1ssuierit ti us.t1[rt.!iv_evn *MOnste.g rne ggandet n o i t i [}

f f

ar a bit j, e,_eJJ.e.e.gia n e selee r.Gil te

~ ~ ~ ~

~

e.t.t _ s.in s t r s tg s a. r dit.j a s I

eye e r.:

i bed.

A >i v eue et e silt? res ie c e.eaageocas seeenre e.t.ict gle..ly sosir e4 tire resynidfie r et is.epe<a ses, y Ese thee the si.dividual es rea,

eest irr, eheehier or eshessite ve r a f g.gie that en attivetY Den tete carreetit e

of e t.e a n niv a t..I er t re., di r as a l, rese+=.i s s e f ee pre f e.

e d, se sesarent r,t

p. t... u i n.,u i s 'i.

t i e s t r

"'a '"**

• • • t t "f*h*' tr re se. s he se e:

. e,Jegne y eTo-e F ret ra..

Ike eyes.d es teorensibia.sie. el the q..lity esses

• er.u er.eeises.on.i sne Caeallisase k.less ok.ht instmas the e.eiew of weitten

,.r

....e....

.,4.. i...e n oi s ei. ie..

u...

ia a.

.u i, as..r...

,,,,..e.e.....

6... e. i.ie.

i W 6c.e N15- &l, ElR 7H, Q A %-71 toa J,w m;sa CF G yEsred chaaf To nc.n - yI3 t., j Ts KcFL K Y CR eTct. noel.T o b App 6dds x, f To su c rg p g 7 go,

^

l I

o/

e e

W k

e t

1 i

C LASSf,& RC, C.S, CB u CC.

3 i

.mu n.

.is., as.... e r...r.e s c ra m e

ge) yes,.

Sue..or eseieer er e re.s e riesee er a es es.u toe,

- NA.4834.2 Quality Cor.t rol p pm The 1.5m&m* _N*M.*"

1. OMe the artisemat ab il *

• 8 eh l i e ta ' r a t ic J *: '8 ' t#

f e'.* t r a' ' i ".. f ebr ec at e en.

a i... 4. e. "A... 2 a e 6.4t it y a...r.m tv rr ee f ee e se a)

-" 7 shall have an l s.imi..?atn r.. e.,... e,

n.

g

,s.o a quality control systtrys uhish will estel.lish that all

...r et *ree s 'ie n'*= s eich he n rat o e e te ree s t r.ca. es.o.f ue.,e.

hplicablhrequitetnents of this $cction instwJin g re e,e e ce she,

.-hig e., p.ceerce ee_gII M. 1he Precre. shal t define the

c. e. e u ei s e.

e.g,. i n es s-- e n. i..< e a r e.. thin on.h the 0.e tite s e==geace trere n= s e s e t e leg-l e

anaterlab du% (Meh e h m*W w(;,g,4 erased 4ed ekstl Iceels eclineste elit reerce

• t ti l e t t e e. levele et autherie sse e

retaree skat t be deeneesed se desen t se e w'**.rN tad _ **b<*eJJ t<!st.t.

4e*

a I e enet. Da sysicin that the Wadenw,fou,,

age orp irasiea f.e ene vam e iedanfei t. I l

e a_b'~The b.h..h.he t s 6. e e,jer bas s e s er dee e.a s se ios of code e.iretieace. Th* S.t'i.t 's gases to meet the requ{rements of thi.-)Section sl ell

. Itt y as e.s er:e tee==s t slepend on the complealty of the we.V.c riern. cst ar.d on i

ip g gg e..<, tr e c.-= th.i t te a

~e. ed 6 r -r i u es pe t es * * *, s.r *< e

• re e.

s Ilie slae and ceniplexte et al.e n r..... r. w,,.i.., g. c g..,/.

d!f_ u. ** 6 "'d ** '**"hc.2.' !** !!

'6+

' e* ha '* ".L eL8.Te *PP II r e* t 's i

.. 81Mid orEantI4HM A WFitlett de st riptinen ed the,

.ed.4n11***ea$

~

• • ' mi fe

• • 'd e

EL!ce er easiell < iea e*tM 8 8 *8 es'***

• I

• • e k - h eg.EW'* '..d' i s sat system the Ma.uient;_ _ :. =

n.

e e.e.e e e6 e i.,

...e f ee

.e er e as *,s i e s er. e*ree*=e se t he e.g. ire-ret e r

gig.. g g,,..

un-er ein.. air su. h err. ree.ir.~ t e hardres sacered.

elece an licm under the Cettific slos of Authorlaatie.

.e..... e.victe..-

m rr..r..

.n.tt i.r.nie for si.e ecce. viish.no et estivisire ef f ervier o.asity h*11 b* ***11a1.1* I" ***I"*

.mr. 6.,i.i, e.ne rc.iies eeenitieu. ceu.eined coj., sis tems sui.<e en. ne.f G4/h.h#4&v enecuriere g.im r. e.it eMe cavi.e-cat et sonde s peGer acce.epiMGr the e,i...

, se s e....anc e s h u recees.imee see es% r he.e >=e= s eeis fie s.

(

,b).

The written descriptian of the qulity control system 1e s.,r a,.e.e e t i e. e i..e e.:ee et she e,cJ I;r op.eiet eeeevete eter e s.r e.

.shalt liscluele reference to gl.e Insgiector.

g. e.. w a s ons sa in t e se eie sia ei.e ree.ir ed..stii, seJ neen en i,.t

.e..

.h c) The8.lewfec4.'.Me ad

.a.i..eise

e. itis, 6,is > celan e a oest. Ike trorm ensit a re, ire in

.le;,talier shall snake avallat.le to reser

.eer s io= e f re

• • f deia e aet e'i*l end ser eisety =4 reettive rcerecif w e:ise.

'i the Inspector a currer.t copy of the written Jescripaion i

(g)

The trerre= Lef t reevise for ledes t rie se lee end resi f or of the quality control system.

, f u rinee t eer feresar un ivie nen e s fue io e.et it, e.ang.s e r v s e e s..r.

3 6ee

/ C, /

te ne i r e: e e s e r v t c..ttef, t.G.t w.n u i'.. reenee '*inez.

d)

"Il'8 I4* **T* *~**4 3 '****

G' e..... e 2. n. i.,,, i,

e.. i..e.e d s. e. e i en t

Eehe M

=.acs ie's wit hs terGjicei, Nt.ser te ogsa

• • • 8W L -- - '; epatity cosde on shteen e c.t e.

• o f. sere i. e.,1p.t.s,.4 t.114L21Lautea'ttl.

e seversal een e.JTT -

8 shall prowhle access for the le spector to all,l.a.s.rge,. M

, p.e n

jied es. rec ie s s is e he n seriq=

id e e s e i rimee t of e.anitica pereene.I ehell be calculat ions, specifigag grags,,,,,,,aa,,,, py,,,,,,,g,,,,,,

the f.gsiilar #Lt.htdtg'r ekstl be tespeesible

~

et e i. e si.cres.:n ei l M 8 C e d" W. F e e t.n els test s c oulas anel an

• ieT The ceitificate solde for advisteg

• ""'*** * * * * * * * * * * ** #* * * ** * '~ *

• e.. e. n. e y s a l.sw e

ice a shaised Supection ageesy of eny elasifisent abanges which age prop e s. dt.r'!-

to....e a e.i e siin, a se. nee.e m.a..l. eed i.a.ie,.ne, e-o en sie.e.ed Id=$aw'" =ces**v e< reeI,umist to reWdes DurM r

6eri.ed Isopectice agenay's lessection Specialiste befoes p.ttlet e.cli cheeres inte ef f.ct.

see cuu fi.ei. =eide,

..n be ue eesine f-pr. po, ea u,se, 46. sospesier

.I of sash a:ca peed shegee. Inst.eing evidense of esceptes.ce er the a.theris.4 tempeeg ge.

N 1.M Mme e.at4 in d.c aginality e trol sys t. nn ar I i

agency e.d ter sia la see sty reaeecilies reples of the 4.ality ase.seece ste==al.

ar)y detalled proreds*ree far fleelt asse sisant be I

(J)

Iba applicaat shall regn et the Swiety te eveltete thle j

&Yallable to ll.a InSprtier d'st review.

• g 344 wrattesa pruedese

.d Psess ee pre 6s to stie tem 4s.ce of a Cas tificate of a.t herteettee.

sla a i 48 8ha) 8 De c-8& {y **fe re nces le 1: e bu eety..e en e.g.utea se the eg.pree.eiste fero ( B l. stil errence for en sul.et ime e8 the applis aat 's 4 sal 6 ty asa.rseee Pserrea. The Pse vas t.ill be evaluted en l

"' I* N L SLe basis el ist c.ca tierre.ith*thie antiste and the oppropriate E=beastions.

It ot.all 6e edetweee la so. teel the esepe el teek it.t hbids the ePPlitant orplied.

The Certificate.hsch to iss.e4 etalt dressibe end on.erily the store end limite es w ek ler.bi s h the app le t s.t se e.elilieJ....SAelhcr tenpre igtyd. g@gigg( gg

.g (at li e euci f t e o f ell iteet

.I e i.e t..re60 ices t.lJer's f ec alirice er e t aiseJ s r n es. eue s i te enr+t ie r. s's' t be n

chorelles at.11 so. eve ee<etener to

• • • .re ceafeeeee:* with the ree ed rese:se I !

e( isie bes e s..g wi the #ertUigne I% Bder's Nat iu Agguraate Pul)1he Mosi l

shall ne accepted by she Society teler se tLe ise=ence of a Certitasete of A.6ert,

• g.

l a.usen. atory. iert. diet att aheasce emas are mede stelt be esJe evellette sa J,

./ The complexity of the work Is-cludes factora e'uch as the h. opes ces. naer*e shalt 8*e edele ted se the aethertsed leetusten a es:y c

design a J e. e..sjes to swir useptame. Le r.ameen eball be the taspeesee's seide

,j thelypes of matellats and "'idI"3 ProceJuss e e

i f e oe 6:ering tt.e t.-e s t fivete et a.s hortseties i.elJer's esetta e4 eseplasese insed, the thickness of malatials, ti.c types of nan.

iin ite useri.4 e at sar a:s.esees tre;ree. 1be Certifieste of a.thestaes t:c

'I'*Iruttlt e chamlnallons appljul, ahd Rhcllee r I.eAl t lJn sha:..te.aeallaa.le se ate seepestu euh dra* 8ese er piness eheate se

. trealments are applied.

i ere ncssar y to

..h.

the q. alit y assetence tregree latallisthta.

G.JLf,,4 g, g 1

- J! TI.e site and complexity s.f the * *' ',i.,,,,,'g;,',',,,

j

-t

.q 7

_k_R$<E O e C 44 et V l t,er

/i A Af tM L T

Ja=*ttetter's organlaation include, ta 3

rt' ' ; ~i "~e a ~ i e - i-o.+.,....

r e....d

,e f.r..t lee.

le. t r..t l...

m...

.t..... 6e,t eed.f..e e

e.,,,.e.

..ri.via,t a-k.e,..r..eE m..use. m a

, - a.. ed. e d..r.

. factor s de tintae th.e enm.a.,,:.

.,... d 6.i.ml..r the

.se.

5

- - =

e a

C S % C C-( kr}$ S b eD) bSC C S s

i

18. A-4 3 34. 3 Beenga Ceessel (e) go oge,e sheJt, he establiehed se ees.re gget appygg, g gggge g et ett E6 elen Sr.-e s t.e ar ian e ese o f t hI lec e len for it e.e er, reee ce t t y s een st sted de te er e t tit or sac e. de*=see s,yeredures.

d in se rw ;i..,

i.+.e r es i..-a s s e e se e e s hee e.f re-re ie:. e.ei i' u e : e'Je g g e., *, e e.....

i e i -e, i. i i-e, d... r..ec.

..e e. e e. e e n e.e i t e t.e e','e.t es.

mi r, i r..d

...d eet" i a e'd ' e' ie - '.-

• i'**ili<

i li %,

e-f s t.- v.n.'. een reac e s.e s. ' e ere r o ec.I,2.Letthiti *a e ' cu er :e : e.

s

.. i i. s eie e e me. 3, e m eiree-,ce.

t.:

i e e, er e.f.cesi

.. d... re

,r ceu,,s. end f.e.,

t g

.i.aii se cu sep se eet., the.g. aer.no ad o g n u.p. g ne she g aih. m g

'Te,.. i,.. sci-r eas < ~ri e ~ e -o h ae na it a s uir u u isse e d e sert e..

e gLTa..ir w s

.4,i e e r mW' e' < * ** t ho ttabn_ enfuetti'i< ethhd e,g g. o r ea s.terbiu e s ti se e.-e ru e4 n, or f a. the go. -.Th i. d,.ie

,ed o

d e s. -..

o,..se d

..e.is eh.is he eer eissed by e oef nned tiereni. et sesnur i

.. e....es 6,she. sess w.

(g)

[erorte of ie-ref gje end final desigeviews ehell it~

g ie weJ b y 6 5 ez..e e. e e l t he e terone thle de elre err eni e li *. t%eira tha ;ee ent i tid s at fself r e **r' *. Sh e l l be orte t*t ed Wbe erf enitalien thet per feemed the

.7;;l.i e,.i.. - ies e ne %c, ereci s ie st e, de.irne e.

e.. ear,eei.,.eiwie s eg ic a s.s t. sp.

Fre.eewree shell be est ableshed eeect res tic ipe;teg desi gn e? Jail-e s s iam o for the teott.r. appree s t. e elease, d e sc r ibut see. and seeisten o g de;e-eens. ineele tar da a re satee leces.

MA-40)4.4 Psecurement Dettaneet Centret t=eiacres ter e rec c eecat a f meteriale. (tees end hif"te"ed 8'f eIc e!.

e s. e i l in gose reem rerwnts to tte eetent eeces s er y to esente their cens liee e vita enie tec e na in e t c e.eens mer e s s tr y. eterwer= at de:= eat e shal t reenlee suntiere ti t"' id ' s C"

• 8 5 ' ' , et ' ** * ** ' i ' 8 * * * *ith the req.seenent e e t shie sess a e.

e c est e t ished to s u=. e the s eli pun c hend e sTit ie s. i s... e-:

re eswere e* alt gmge c on f o rn v. i t.e ee re eis i r ec e=t e. Then eteneree shet t sect ede Idees i ficet tee (a g_1g.Agggil ALLeeJ rrariginagan as-preeriete. f or e==te e test eetiene et ec tive 3

evidenc e of guelit y f *rme sted by the = rpf lef. eessinet ion es Et, tomrc e ord seenieem, Ten spos deliver y.

{

I se:a-4134. 3 aut r ea s seu Prund.ree and are 4ege e

/~ndlH. 5 - Inkf ru'ations N

ar e es t i se t erfgar eutb st.eil ne erence rted by duie.eated I esees-Processurce anddranir.g o

he _ e... d or. or aresge. et e avre espeerieve es ime cire..eece ees e:s eheit s

%u,6 7A,,

4 4Ig*

e i

se acc.e ptieses i. eccordan e e it the se seetractions. Precedces of drawi ee.

gg.g,gP,gyg, g,,Q.I WJ8'. i-f" Me.em%e5gs bu c e ie... r enci dw re er d re d at e **.< I t en ti.de encepriate caeris eslee e r e

Epeet.eecrieerie #er decersinia, eret I.rerie t ersioisiee here 6een ee :.e ee.

~~-

sT ue_ecccm iieu.a.The tunissesse asider snett essensie e writare duse:ase.

..., f ;. _ _

.c.sy pecmedores heed by his ergesteet tee for e..anet et g.entes e s easeisetien e ske sus in date s t the insiementesion of aL geelley ese=s ense setelresease af thle i

sces ion o f the C.Jo.

A es.py of these precederse shell be needily eveitable for use by seassses tien reseennet and for esse by the taspester.

m.

/

/

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i e

~K~

C 0 ** OC-C L A S.S L, Q 01 C, C S i C LAs s.3 l

a

(

HA.4114.6 - Document.Centrol hea-4 34.6 m

at c seet c,y og,, ge,gg, E'* E NT"***4'r*ttl% stuality centrol sFstein 8

(.I ti.e Ps.r e.=.h tt i f.e t.d.

.e...e e. i.ee..

the (....n o

• g Pg* Procesheres wlich will assure that al.e latest e a i e r. in i.,..e a

......< h.. -erh..e.e-< i t i r a t i.... i.. u.c i i.e.

cr,-

• lt C AI'le drawings, design calculallons. s;>ecifiestle...s, II

.a

.,,,i.,e inc t.s n chsere, twret e. airk arerrribe ese.etivis in e ga n..

.u n..cc we n i,.

Tw.e *,u.rgtp.i t eu <e em.: en..e.e.

6. cia..eet..re.

l and Instructlier.s. as well,as authorised chantes, ase s, sed

.,,.....-4 ree e s,

..c,. 4.erravee f ee r<i...e hv *.ei rived rer.

..t ad

• for construciton, ihe 1.<. u...hei e in. e,e.n.t.e 4 e n

c.,e s s ie.i e.4..+ 16. i h.i4...t i ii, 6. ee. t.r.ies,

}g

- - _ + -...

=

oi.,s...... a

..e.

's _

. w.iie r a........

(6 8.

.h.< h i n..... t h e r i h. n ee e..

.rci c.si.

r..g.....is pe..iac c, ced ec.

47..iar...recifie.'i.a.

...8 4..

t.e iaa. er i red b, t he be.ir. eev i s e. 1...

o i. u. _...

_..m.n...'.h '.in.

... m.

.r... a r., i. o,..i.

l

.. sue..i......i...i,... i.e..J i..u u.ei...

sca-4334.7 c

.e et F.nhued H. inlet. sie....a ser.seu MA-4114.7. Co.ritrol of 1%rcha sed Malertal and liems-

.h.i s t.. e.a..i t.hes t o....r e t hetA. su_t** the atir n e rial.

/. war,v p,,,g,,,e

, e#y ha M m...-.

...r... i..he u s._ue... n _.c.hi i s+ tuir r.usuas i......a. u. i t,.

e.,.... e..i oin..

6i,u

..i.e...e..u.,e.ro..ha.,. e..,uer.

4 m,,my %, 7

.y

.e.n.., t. o.. o<..

r i.. i i., u n e ai n i, a m. i. in......--re.....

_.... a i...c. h. u c..a....i... i.,.,

.e u.. r,. su.

..ree. 4e.:.

.c.il te..n i a t e. ime eeu u.cei...r i..t.nl.sia..it. beteo....,s..s l-9 i.ei...

e..h.. 4

.in i.i en

.a....

wc a-4 3 34. s taou e n.s te. end c tv.1 et mea n s.t. uJ ti...

1; NA-4111.S. Identiftsatica and Control of klaterial an 1 Its ms brfh 4.e shall incliado a system of L.)

ne...re eha t t,b. e t.y..k.4g idat i tl< sti

. 4 T1.e y

.gi e.

.e....rs.:..a e s me, h e t.d..t e n t i.i_ I r f.bn <.< ed.. *0 t i+ e.

Th..*

rcceiving control stilch mill assuie that al.a material re-ed. e eies.i.c 1 2.I.nti.eraattisr s.. ar e its. ar em i.e. imee.,h invie ti......t.es... er i...it.es...

celved is pincerly identtiled and lias documentation intimlin 4 c e....c.

.w i n n r e e i..e g, c.c n n.< e.h t e.. c h.

resguised mAterl41 certificatleine er anatorial test reports a..

s * *

• t I t e e-e i r. 4 e. pre.na t h e....r i.cn e4..

. e. ru t i.,

has u a.a si....

6tch h.

ntis

.<ee...T U. reg.ar.4

.......t

.,ie.e..

.c

.c8ht.I re d.

'The misatcrial control systeris stealt assure tlnat sien.

s ta= ' a -* ' t e".r.r

.d theaiU11*t iaa red..h.H be only the Intsaded material,le insed in construction.

i"r*"i*"tT-h otte. a8 et

.nt id.r._.n is._.r.cild a.nt.ru ss i.s t s_x.h.is t_ar t.h.e ti ed, h.re.t._dr!.!.i.r e.g.L.s. sh Iter i-e s ?tlie.yJ1.ht.t f._

1,1,.b _t i,h t.Qt. t~Gaer=

18 e_.i t h the f..qs..

t].gt t g. M){.{ ih. i t.a..

tir a d t.W.4, $,2 g y.t e-

.g

_ tEh_fLGl eTUug_.g[ts.!!.j.iU,3.t 11.l_tt._.t.at11mli*d..

a Ir h

(c )

({},e cters eu r eg. ige,LM e,eger ted by ihe e.e.r i.!

i

.gege.goet..Jb,tht. $cC E i b. rhill,,ge.c f r.. the r b {ht,)M.a 8 t he.;1[ ggfuh ar" 33, n.3.httlee e...i.e4 e r.stre.see m6re.

1 itehre tzenlit

.gt.ser6dd, ur acicdatus_laatsted.sa strallicLllattf.itt Ir.pL8citt!Ler_C r.lif.la.

P

.s itt e11eal.ttus_r.tt.Leatht dsti""* ia 'W **< 86 8. C5u%t..t h ti 8etsis; ad

~

t 4h4 *"*ruhie

r.nUnu.

_rmet. f et e inerf th.statiJ. r21!!.!!.L.!.st11r!.i Tut u t i...r'b es corn e :. h.n n e rec <

a. re - 4 a

ana.,

a; e......"*.'

6 r ' h* (

T;gh. &i it....u. c.,ir'an a' t'"d***

• aad=<r'iati..,"..s., nFls:-

in >UiT.1Va 4

ia ~.;ad.ut Mii.e. sh.i t ni.. <WrIg.'TUTH.[e'"el GT e..

The t P ec hie U~g

• f

...... i Fi in mii ini. ie.,.en I.. i.e i.iiWTr i.e_.e.e.e

.esu. 4 re.i. #.. e.

h i c h.. 38 -

g. n eg g m. g.n...ig.i.n. iris,i._t.,_or...

..q_L., orth.

l

/

i Lr...ces w.miercied t. et.e ce r th sc.t e roides. r n-ee t.t s ee

..t f.gakich p

er.t up

..s d t e f.c ih..e.et i vit s e.

.I te n ti d..t sira. tere, salaista.

e s v e.

e.

...____.__.s__.--

r

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t sca.4 i n. t c....t et r.I u s a sat. conim e i... ad tut.II si.e HA-413 8 3. Centrol et Etanufacta:Ing and lastallation h"'*"*

1*rocesses

.L g.)

ne (e.iiric.n nateer k.t t.r*e ne dn. c <reltd a) Tbn annality central system stiakt incle.le iirovistens

' ""' P"'*

• 2.*.."u'e'.*.*."."* * * *"'h.'i l be e m i t i.Le e"'1.".uw e t h e nu e u eM" '1.

)

ior inMeating that weldict confarme la sequirement a

[e J.

e...,v e s 6.

w h _L

.;D.f.g,J~; G T. Snei..

4 r

of Settlou IX smi Sutenection tin.

yeve.e t..egs.w e.ited ne.cceerai.*ed be ta h f.es,te..fu n du.<e won m,.c s o....e. s c.u r. e e m t..i : m aisted i..e,.n e

,,.e d, n.

re.un Feste..cbesntista. stme.ravsc4erse tr srista.a a) at b) The sguality ae.tsel oystem shall prowliin re.ntre le

. <.e.i i...han be r e r =r r a. Aul.J iat 3 9 a=

e.

_ g.ig.: m.6ich ie.e

..u..

gnj.g.. u p c n.. r. sa....,.a m. c.c.G&e dTTielrMi..;r>r s i.c.< su t s e

, to a s sure that b.at t re..senente as re.tmire.1 e'T it is no G Tu u 3*'ll'. a

• r * " 5ral. Alcans shall f.e initicated br.

.s c.. pica... 8 epc ii.. ern u i...

s.WE ine 8

E Eggt3n3...

.we n d.c.u.mi..>. n i.< 1.Je nu e. 8e es

..r..tne.

i.tei.te, whici the Inspetter can satisfy 0.Iniself th.se thesc l

_R u.nt.at s mu.e rre se.e.i....( e ne cer tif.c.ee 6.t der. 4 da te.. 4 for the Sept treat runt redrumnts art mL Wsmy

_. t e.. _.n..... 6 i..c.i e.

. e.w i...,n en a.... s.e pue = = i. iiie. a u. h i.e s u n a.n.

. be 1,y review.I furnace time.lems.oratore a ccords t. y-p g....rn m.i t r<..ia, for ite cc..rt i et=at e.f.c e l.-

• • yF of,te r methods.

j lativR t w. 13nli1LWii "4 ' **l 2 '~"*Hii_1?"!!!'am.12"11?Hi! 3*."'IN'

_itisa eutsli

.it 2. t rra n !!!r. tW r.=*alw a ab 8. ~ 4' *a.*a u t <**d i

• tta18.r.

8 l

h r"""""'"'"*8E" "Y

_ns,e.t.u. i ir.t M* ** *le!* ". r

• • d "* *'"" * **'

si.

tu ni..e d

n:4 4t35.is s.

i..s i... 1 ei...a tu pu 4.u one. 6.ity og

%. NA-413 l.10. Iha,minsti.on. Te st s. and lasportlen t.)

n.. r..u.. ae..i n i.....

yh, mo.g,,,, m.nrr tmmenev.. i.ualley c.= rch g

u.i.n i....

.e.

.ra.. ce wish m eh.ei... d r-Jrt17"" *"im. a r

_t.!!?.'U..ni.**e!il S.e!!t:111'. g.*L "l'.c"."".."e'1.* **.1.E! *1.t!!..E[e.f.i!!.!!!!!. ' l idI*

-3

..,,my, hhe eIsism shall list at:o constrursion oPerat.on.* In.

,te Je

. d as t.

e.t n EE et t

er g.i u,.s su bg7.t.c pee sZei r-eef.L ^.Wr7hTei.T.'J.sye s e474..

j d*Mng am.nnations..wilictently to pe r.i it it.e g ne cJ s wi e 6.

ggEe.c g e,

....r. 3AIGe in..f.IIGLn.njutuisTL ali I Jidisi.

,1 Inspector to dete rmine mbs. specific luspcstiens me.gy.46:e ter s he woe s 6-iq i l ?tia are to be pasformed.

In)

.t retria.ek'rt!. !!?t t!. ni S' '8 e*

• li's. t"t'LS. r'S.tf e?d_s e.Gy,se AQd,e

..pr.....

m.. e i

i.~i. t'e e.,.li. iii n.K' i b sM'G"i

• i+* ** *i* h ' * * ".i i e. Fe n..n e....

b). Tl.c <nuality control a / stem shall include $sovintons ini dias n e * ** * * * * * *h * *ad

• "******a"***

~

s i.e en TNI.g ee.

A *nti.__ lei dH '

_1*!!Liaill'L.it!".f" * *ict!!.! ti. sail.lalt aL.feielma.p for identifyint nori!.structive naamination piace.

ad d.te o f t he.C"'i!Mi.81,. 'e uld'r *

• rtt42're 3ne e4 dar the t. jweier*

.t.

dere s tlie ? '- A ' ; a :n.s.4,r will une se

. r -.h.t n. u -ti tine a m. i., u.<..c.

w. o

.u i..

.....i...e brWa fi EE!d M t!E! s' ! LL.51.lilitd]a7 IJT*41 '.ied 'b r 't'he~CeHIfis se '

'#""'.#'.N islyamsnte of tl61s $scthn.

<M H et blJri_3ta.n21na.1tLnristrialtidt sr tal ettte tm she ilta h ) _ ___ _tMatestist!! tele 1Lat

• ic h *I tati!!!a.t e...istl...

i

_ittsn.c.st e.: t*rAstuus.ta.M.idst's sstastnuinoni ti:e larresser.eksil it i

be i.d tad is she pr.ecaq kege (J C434 )b H,._ Eggh_ ehglLagL ggggggd he ngj tad 8t*f!_b'E8 Pf8*'.. p{hggLght ig.. rat g{_ggg,,.{guijng.gigjt,glfgr's rgfgg-

.n s.. o. nu nci.e.

s.;A 4834.tl te es Cc..tr.t

,T.t i.e he]) hais terse 4 6..cc.rJ.*ce wi th we lite. te.t t.1 1

!'en t**tte et it!s tter

<*e etnir**t. ead nuotaca li=Ts.

_r.ene=a ei< h e

e

_e it. i.e 4 e. *Ill it *b l * :8'*i a d** *"s et ek'9 t

'?

M

_ It ti. terat t

i

_rinsn.u at e ne..!>c alus_scattomace.t!_latl=d _rt r tt enJer.e!!.r tes enet-ia us LJet t ut stia tmatausta Inats m catssion.

g.

. s..na. t!.aLsere,er, e3ntierins,_b per fetard tt1111:4 611.p m.o u..n,y.e u.e.t.":.!!h t!iLie".noatttifE4 nt!f t1111r_InIm's u68.111*ef.

Inhoe..i'i It ag 11._1 u n c os,~ e.a e6e icone e.

m ir..-

t on. e.... ua cr..

4.1,... r.u e.u.< o i n...i. t en dal._

It ti.Ikktlli_!h,j({ i)g de:eenied.pd e..)

ted 3.

..e rg a t.. t ne.t se noiretentLigstian sati.figla

-.... _ - ~.., _... -

9-

1

_... ~

C Lass I, h M s CS C Bct C C-i L

is:a.s t as. t a coete.t es ns e.e sas sad feet tg.s r.eet

. 24A-4tM.12. conte.,1 et klen s, iring. a y.e

,Y',,,3 C e.e U./. s.y# petur

%e W Miw sl.all have a e.rstem for t.)

n.. r e..h.i t be e s s en t i sh.4.e4 d..c se,i ed t.....r.

the callt,rattaa of vaarninatten, eneaseriaE* and test eN-ihy e.,t e. r..re_e. ia er e.a y t e..p ciece n.7 e c. =.

e.e

., g.4 t e se i-,

g3,.n.nt..s.i. sce t_yy.Da pq v ie s e f fee s iac e st u r see r f t he.rtstry

,ne ng,

~

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• I i *** * *

• SE****

W M*L?. L l'tts *"* *" *. ' *L2['* ?!?$h e** '*** *" L!*le. n. ru., int t'sucn t e.'ert a reee rd ere shall be an e igt to nos re,%e tee tib ' * b~'b ** d t!'h&lEtiL." L.hasLAL l d tiLa t humeleilet in a et_latial-

,'8" 5

gag sc e s.is es s e t.tre t sag _3iglit t se e s et tbs e s sygd_ge. res t nesp..t eJ et e-e:l*

h 1Ef tfILit.tille-e i. s y f1 Lt.Lc.243%t t.-Lptifo sfry,11.f a f.*tdssv.i t t l e t i.g.4.t'L p sicJy e J s er

• a -

12Ltd.ui A11*d 'td *

• • i.'h h i

• *a t i L-se ad...t o. wer e s.".c h e s aw.s ar J e es i st.

erismai

• s e t.we n t i e gmia et

~~ h,1 (mit Gr..

<

• stal*het.de era,lelane for Id.asif. leg g

e Ivr Jet r' col et s etion st erne L v e nuin z. ant machi.e or mg

, e *t,,, e.. d,,r*ca lm e.u " Ae. ne 3,,'<..

+

e e enh... S..t.L.dtn rrrmi.!1e ma.moni. tise or tesilet.eq sip no Ljed ls) n.e cen.uc.

n.h.n.-. n..e.2 s e.. e. i.e

., e f. a et i G..',,.i' -unc ia ai r e wi d ( eine ti_e_rre e s:.s

.u ri w au.u. n, n e A.i o n.'"3.

1.e.e..

f c u... sea est rim i,e n.u en.u,ue.sie.eedt s unn.we.

.ith lu ta..e es,.e e.ud e i r

.n ye.a e.... a. t o t

....e

e. e..

..e 6. e t.

u., gnpire.per.e, n.im res epe o.* Se ~ et.se-;

this e.{ tree ten s e negaggiaed. ta gLg er e.J ie theitser se.see.

men t se deseres.#

c eeded se the re fer ehee n reev ised the di screp.-, (,

disc re g~as: ie s m. e4 e=@7I'*e h -

.e...u s..d.o se'..ad *e Tiinee meldn'. g.iie.2griedic e'ec esan.

L 'M

• • *e'h'd e e*d '""cae y e t d i sc o.. r eT 5 h

h

.i.4e3 se the en r aes.r. m enste..

t f

Sca-4134.11 ataedlies. Snessge. Shipping eed ra sservattee ne. re heit be est attlehed to contret handlies, statore, ship

• eg n

re cee r.et t an el ester is t end i t u. e isi ec c erleac e s t a i gggr. TWm.e s,ar Js a: as e:c4*ees. er e tmes. to n.en t d es*re. de t erie-sitataistes eness i

ytien er_t e s s. tYe e cce st er ?. etM iel rever ent e. erec ial equipeent. and e ge,ehet ec t ive en.trea tee t e e.c h es. iaet t eas eersiehere, speci fic coiegave Ie.en.

and tenper et.re leeele shall be speelised pre.ided and their r ec e e n t eIlese-se=crili.d.

a uta-alse.ta s...i.. ties e r hue e si.e.e N41CNWn'atten er Procese state,

.h.n te e.n6u.s.d ie i.e s....

y ne

.e o f..ru, are ei *

• www M* M*P'*O h.4=*ev54 = e A

k T

I ru s....

st._a.t ter s.E..a..M.e'I.k ?tH i*.E_stif t. et siks.t !tlit!h.IEtssti._l e st **E_1_

• e*## M* *** P== 4 Mf-v/.y./c(et) ne toines wies e.di.ne. t fitse he ne=rce shott :re,tde ire.as.ai_sc h se feri. gn.ei.u.e s see and s el e

io t i: n a se t

.br the 6eens i fis eie., es e e6een

."mte"u n e*d 'llit * **

• di "' <*a f2!! "4 *h*L I *ael ade raced *eeU_e <,.

>=teet tieigg.Liaijeel the e t her de r ler eret iestien sad re=ovel of tage, l

e se n sen s. t abeie.gr e, inc l e. diet a

s.- 3 end gepgga tea-al 34.13 heueafe teing F.aterial er itess NA-4RH.15$ enceseformlag klaterial er lleens H

r. u.. os.t i 6. e.i e i t et e t to e*a s eet. in t.1 er ise..h t h de

,j

.g "'" g

,ot e en f m e s r..i r e a e r ia sij.st.tL a r e=ta t. the 't_hsiverteei x e er im et al-l r**= r e-e=r e o f s'ile f retlap.

.g,,, gg g'e A sys' tem for.terrectica of noncomformanc r e* *"

lat e es n nec t ase i.accan ter w-vith the A tienconformance is any candillan wl.icIn 8 tate esce saanI.I thepos es s%glI, *c tweearne.ivgtt.fgi !.dasIii c ati.e, doganggalen. !!ggg.

Wtle the appiltable tules of this Secll f.e t....: s a n t a u s.an. 5 2-a ine m, a nm e st e te sn ee.ed for uc't'Efl.

uncties. eenie er re.n ua are cie tate *"h d= *.o r in ormern. m ru: e-l goes.t 3.* Corruttest er clin 5.Inalsal 1,cters lies stent..c., I.,

~ ^

. 64ut y ni. n.. ie y son the di. esialen es n.ecea s.

ies inces elieti to serised.

e.,

e..

... a Wi $.Td, '..' '

~ e -i...s

.-J e....w.e si e s sha i oc e e-c.anacs in sneidenc e. tin t he om enst.

1. ~ " " ~ " * ~ * *

• P vet;b s e.ie rat ha t %cr es..e es t e. - ci e eunun feroint ce d e fes*

t a

gg.,, fmgu r 2 a

g %-a.t e.i t a di e s s e e r ei si e A n w.it taan etitt be c e t =Dli.hed and e sit te led. =#

1

[

g is c i s co s

l 6t t se nt e de e r..s e s sa. o f ese.6..e fer.am;, 4 Leme shell t.e de.tamented.

e r

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P m

m m

. +. -

e C.LA SS is 0; PV.,C.5 c8 ot-CCo r-- e C Lass 3 u e.n cette,tive me.de.

,j we. re a ii

.e ee.shi s eu,.e,e..re. e_tm.p[elaite. deles 11st.

i, ;,_mp.e e,vo n i e s t =e co mt io e t aMhu cartt3 Jrr w isg_.ee

• 3!! tit! eM,!$1511:' tt.a.5*2 ".1hM ""."e'aai " **f *e *re.fE*d112_1JitdliEd F A giu eg.A t. tu.J eu of r e...ei t ie.. se ue_ge eustit e she mas e,.

em. 3.t tef.

of she e dieices eJoerse to petityJe detettined g

g,e [ {Qa t e d t o'Ye'*Ts.J e s t re t i 'l*a.

.ig ne e ssw e shie the e e id'et e tice@ o f ef raijEg,il reaf ilige,.p est r W

d.er oe la t*al t e r,J he c.se o g a 6 4 ee Jision med the terrec ties eeti g

on seses t

eh s t,yg e seseeeste en.4,grputte !*.ffff?ftleit l!.!!!LiteenstrseLalt_atthist-g 9

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--___..__.._._.....__._.__L COMMb IEE CORRESPONDENCE l

SOCIETY / COMMITTEE:

ADDRESS CORRESPONDENCE TO:

ASME Section III James L. Milhoan

'O Division 1 and 2 Reactor Systems Standards Branch Work Group on Quality Assurance Office of Standards Development SUBfE T:

U.S. NUCLEAR REGULATORY COMMISSION Revision of the Code to Reflect WASHINGTON, D.C.

20555 Criterion I of Appendix B to 10 CFR Part 50 AGEND A ITEM: QA 76-27 i

i jay 7 7g77 FILE NO.: N/A DATE:

l l

TO:

Mr. W. S. Gibbons, Jr.

. Co-Chairman ASME Section III Division 1 and 2 Work Group on Quality Assurance and Stamping Bechtel Corporation c's 50 Beale Street s'

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P.O. Box 3965 J

San Francisco, California 94119

Dear Mr. Gibbons:

Mr. Dobel in his letter to you of May 5,1976 stated the proposed revisions to NA-4133.1 (copy attached) did not passSection III as he was unable to provide a satisfactory answer to the question of: "How high a management level must I go before I find someone who is considered sufficiently independent from cost and schedule considerations to satisfy the revised Code wording for this j

i particular requirement?"

Mr. Dobel also stated someone on Section III provided the alternate below to the proposed wording (fifth sentence) of NA-4133.1.

"The persons and organizations performing quality assurance functions shall be provided this required authority and organizational freedom and independence frcm costs and schedules. They shall provide reports to responsible management at a level where required corrective action can be mandated."

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Mr. W. S. Gibbons, Jr.

• He asked that you see what you can do to 1)

Develop an answer to the question based on proposed text of NA-4133.1 2)

Revise text if answer indicates necessity 3)

Revise text per proposal

{

4)

Get NRC to agree that existing Code text is consistent.

with 10 CFR 50 Appendix B intent and leave the Code alone.

l Since the revision to NA-4133.1 is still being held up at the Subgroup General Requirements level even after Work Group j

reaffirmation of the proposed wording, I believe we should respond to Mr. Dobel in an attempt to get action moving on this item. I have attempted as a Work Group member to develop answers to these questions. My proposed answers are attached.

Sincerely.

I n

a

' James L. Mi hoan Member, Working Group on Quality Assurance and Stamping

Enclosures:

l As Stated i

cc w/encis:

R. E. Keever l

H. Dobel R. Bosnak l

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RESPONSE TO H. 00 BEL REQUESTS CONCFRNING REVISION TO NA-4133.1 (NOW DESIGilATED NCA-4134.1)

Request Number 1 - Develop an answer to the question ("How high a managemenc level must I go before I find someone who is considered sufficiently independent from cost and schedule considerations to satisfy the revised Ccda wording for this particular requirement?")

based on proposed text of NA-4133.1.

Response

The intent of the organizational requirements of proposed RA-4133.7 is to assure that those persons and organizations performing quality assurance functions have the required degree of freedom from other organizational responsibilities, such as cost and scheduling responsibilities, which could conflict with their quality assurance functions.

It should be recognized in establishing the organizational requirements that the degree of separation or independence of the persons and organizations performing quality assurance functions can affect their auility to carry out these functions. While it is desirable from one point of view to have persons and organizations performing quality assurance functions completely separated, arganizationally, from individuals who have significant responsibility for performance of the work (including but not limited to cost and schedule responsibility),

that same separation may in seme instances hinder the quality assurance persons and organizations in performing their functions. The greater the independence or separation, for example, the more difficult it may be in some instances to maintain lines of communication in identifying quality problems and initiating corrective action. A number of variables affect the establishment of a quality assurance organization that will be consistent with the proposed wording.

The variables include, but are not ifmited to, the size of the organization, its organizational structure, the type of activity being performed, and the location or locations where the work is being performed. Thus, the answer to the question "How high a management level must I go before I find scmeone who is considered sufficiently independent frem cost and schedule considerations to satisfy the revised Code wording?" - is decendent on the individual organizatien. The proposed Code wording recognizes this situation and provides the necessary flexibility.

It should be recognized that the proposed wording regarding "orgenizational freedom including sufficient independence from cost and schedule considerations" is not a drastic departure from the present Code wording which states "The person or organization i

responsible for defining and for measuring the overall effectiveness of the Quality Assurance Program shall be designated, shall be sufficiently indeoendent from the p. essures of production, shall have direct access to responsible management at a level wnere appropriate action can be required, and shall report regularly on the effectiveness of the Program **(emphasis added). If problems do not exist w'ith present Code wording concerning " sufficient independence from the pressures of production" then the proposed wording should not present a problem.

Request Number 2 - Revise text if answer to question indicates necessity.

Response - Answer to question indicates a revision to the proposed text is not necessary.

Request Number 3 - Revise text per proposal:

Raplace the sentence "Such persons and organizations performing quality assurance functions shall report to a management level i

such that this required authority and organizational freedom including sufficient independence from cost and schedule considerations are provided" with the following:

"The persons and organizations performing quality assurance functions shall be provided this required authority and organizational freedom and independence from costs and schedules. They shall provide reports to be responsible management at a level where required corrective action can be mandated."

Response

The proposed alternative does not address the reporting level of persons and organizations performing quality assurance functions; tnus the alternative does not satisfy Criterion I of Appendix B to 10 CFR Part 50. The proposed alternative would appear to be acceptable if the second sentence is changed to read "They shall [previde-repepts] report to responsible management at a l evel..... ".

1

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.3 Reouest Number 4 - Get NRC to agree that existing Code text (NA-4131) 1s consistant with 10 CFR 50 Appendix B intent and leave Code alone.

Response

J. L. Milhoan of Reactor Systems Standards Branch.of l

the Office of Standards Development has provided the following comments as a work group member.

"In comparing the existing Code text with Criterion I of Appendix B to-10 CFR 50 it appears many subtle differences exist. Areas where differences exist are as follows:

a.

Criterion I of' Appendix B requires that those persons and organizations performing _ quality assurance functions shall report to a management level such that this required authority and organizational freedom, including sufficient l

independence from cost and schedule when opposed to safety are provided. The reporting level of those performing quality assurance functions is not addressed in NA-4131. -(I am making the assumption the term

" quality assurance function" as used in the Code has l

the same meaning as used in Appendix B to 10 CFR Part 50, l:

however, this is not specifically stated in NA-4131.)

NA-4131 requires that the individual or group assigned the responsibility of. inspection,' testing, checking, or otherwise verifying that an activity has been correctly

' performed, be independent of the individual or group directly responsibile for performing the specific activity and that the person and organization responsible for defining and for measuring the overall effectiveness of the Quality Assurance Program shall be designated, shall be sufficiently independent frem the pressures of production, shall have direct access to respo -ible -

management at a level where appropriate action can be required, and shall report regularly on the effectiveness of the Program (reporting level not specified).

b.

Criterion I of Appendix B states that individuals assigned the responsibility for assuring effective execution of any portion of the quality assurance program at any location where activities subject to Appendix B are being performed shall have direct access to such levels of manage-ment as may be necessary to perform this function.

NA-4131 requires management access only for those responsible for defining and for measuring the overall effectiveness of the Quality Assurance Program.

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c.

Appadix 8 requires that the authority and duties of pers;ns and organizations performing activities affecting the safety-related functions of structures, systems, and components shall be clearly established and delineated in writing. NA-4131 requires that the authority and responsibility of persons performing activities affecting quality shall be clearly established (no requirements j

fordocumentation). Of course, NA-4131 also requires that the authority and responsibility of those in charge of the Quality Assurance Program be established and documented, but this is required only for those in charge of the QA Program.

NA-4131 also does not emphasize that the " activities affecting quality" include both the performing functions of attaining quality objectives and the quality assurance functions.

The wording of NA-4131 has provided varying differences in wording from that contained in Criterion I of Appendix B.

I see no incentive for the differences unless the intent is to allow the practice to be different. The difference in wording raises questions of different practices, different interpretations and different requirements."

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, pg -

g ys; y y 7,f 2/24/76 WM (CR75-4) (N72-21)

// /

PROPOSED RE'a*0RDI!;G OF NA-4133.1 7,

Y HA-4133.l' OrCanization NA !G:1 OMGANIZATION The authority and responsibility crf those NA.Il35 Aurlueritr :md unpennihiitt Persoon and orzanizations perfo'rming acti-

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. 'Ihe authority and revonsibditv of inose m charee vitics affecting quality shall be cicarly cf the Quah,ty A5 urance Proyram sha!! he elee.rly established and documented. These acti-vitics include both the performinn acci-estabbsaed as:d decumenied. Penon> and ot.

gana. mons perforsnm; qu:dity as nrance funea,ans.

vitics of attaininC quality objectives shall have suffsetent ar.J we!!. defined n pon.d di:y.

and the quality assurance functions.

auttuvity.and organi/ationaliree.fom to:

(a) !dentify qu;dity anuranee prohtems The quality assurance functions vii;hin the Quality Ascsurance Progra:n are those (bf initiateauien wnich ts.:sts m wicuans ofs Gassuring that an appropriato quality (ef venfy nep!cmer.:suun of wlations to than problents assurance progran is established cnd The perwn or organizanon revonf.i!de for defining effectively implenented. and'Z).vurifyin;.

such as checking. auditing, or inspectin::,

anJ for,rneasuriny the overall effeetner.en of it.e that activitics affer.cing quality have Quality A<>urar.ee Pr.qtam shall be designated. >h:d!

been correctly performed. Persons and l

he sufficiently mdependent from the prer.sures of organizations performing quality assurance proJuction. shat! h.ae direct accos to respo: sib!:

functions shall have sufficient authority t

management at a level where appiepnaie acuen can and organizational freedom to: 9 identify be required. and shat: report repu!.orly on the quality proble s,',C initiste, ree:mmend.

effectivenew of the Program. The.:utharity.md or provide soluttens/ d) verify impicmanca-i resprmphility of perwr.* performing activnio af.

tions of solutiens, and O li: tic or centrol Icetis:p quality :. hall be c!carly osabbshed. Anuran.:e further processing, delivery or inscalla-of quality requho management rueasures whieti tion of a nonconforcing ice:a or unsatie-provide that the indisidual or pre ip anigned the factory condition until proper dispositi:n-

- soponsibility of inyection. sonnp. checimg. er ing has occurred. Such persene and organi-otherwbc serifying trial an aetnity has been correctly zations performir.g quality assurarce fun:-

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pe formed. a... dependent of the indisidual or,cmup tions shall report to a manage = cut Icvel s in such that this recuired authority and direct!y respon>ible for performing the spenfic activi:y..'.lanarement sh:.!! regularly res iew the status organizational freedom includinc suffi:icnc independence frem cost and schc5ule3 :ea and adequacy of ti:1 Prteiram. The spee:fic re.

~ ~ensiderations, are pre-6 7 - - u -A m spon ihili::o of the qua!!ty amirance.irpr.: mien of vid' ed.

Docauce ef the cany'varisbics in-

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the.\\lanufacturer er ic tal cr sha !i wh:Je t e reuew of y ruten proqevyto and monnoring of a" aeuuun volved, such as the number of personr.el, cenectned with the Q::a!!;) Assurance Program as the type of activity being performed, and e.rectedin :hh a tie:e.

the location or locations where activit. ice are performed, the organizational structure for executing the quality assurance progrcm may take various form: provided that the M-YjM MNUMSEACM persons and organi:ations assi;:ned the pg apj 3 3. I ed MSN quality'assurvnce functions have this r:' quired authority and 'or:;anizational freedore.

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g.g spective of the organisationsi structure, the individual (s) aal ;ned the responsibility for assuring cifective execut. ion of any portien of the quality auurance pre uram c.t any location.chere activities subj et to t his Section of the Code are belag perforned.<:bal]

i have direct ac:: css to r:uch It'vels un' :r.anap-ment as inny be neceusary to pert'orni chiu function. Management r:h.til renularly tuview I

the St.atu: ;.nd adeqaacy o f the quJ11 t'/ a*"ur"

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l The applicant} shall be responuhte for the establish.

ment and creCutson of the riuahty esfuranC8! Drogram.

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may d<. leg 4te to others. sue:h as contractors, agents, or consultants, the work of i

establishing and executirg I%e qu4fity assurance program, or any part th;reof, but shall retain respon-3 sibility therefor. The auttiority and dutses of persons I

,and organizations performing actinties affectinst the safety related functioni of structuees, systems and.

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components shall thr cicarfy es!abisshed and define.

ated in writing. Thesa activit;es it.clude both the performing furwtions of atta;ning quality ohjac$ves and the cuality assurance functior:5. II.c aual.ty assuranca functions are those o' fal assuring that an i

• j appropriate 'rJality awrence program is esteblished and effectively executed 2nd fbt verifyir g. such as by i

checking, aup ting, and insccetion, that activities affecting the safety reistrd fu9ctions have been cor-rectly i

performed. Tne pctsons and organsrations o

performing cuality assurance functions shall have sufficient authority and orgenstational freedorn to identify cuality probicms; to mitiate, recommend.or provide solutions; and to vera'y emplementatsen of l _

- solutions. Such persons and organitations performing j

3 quality assurance functions Jhael *coort to a manage-enent level such that thip reouired authority cad organitational freedom, inclucting sufficient inca-j-

pendence from cost and schadule when oppGled to l

safety considerations Are provided. Because of the many variabl.:s involved, such as the numQer of 1

i personnel, the type of actuity being performed :nd the location or locations where activities are per.

i formed, the organizational structura for executirig the quality assurance program may take various forms provided that the persons and orgivnizations assigned 2

the quality assurance functiuns have this reoutred

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authority arid organization 4i freedom. Irrespective of the organizational structure, the indh-idual(s) ass;gned the responsib.lity for assuring rf factive esecuMn of any portion of the cuality assurance progrnrn et any location where activities subiect to this Appendix are being performed shall have direct access to such larvets e.

1-of management as may be necessary to perform this t

function.

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Whae the term' "aposscant** is usest in these criterie. the e

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ressurements are, of course, acus.csa.se af ter euca e person j

g stas receeved a t. cense to ennstruct and operare a %ctear posseepless. These sesseria.se asin t>e usess for <jusewe en evoivateng the aclenuacy of sm.niev a.ius.ince twegrJms an ene try honoers of sonsteveteon peremts ane opeedseng

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COMMDTTEE COMESPONDENCE I

SOCIETY / COMMITTEE:

ADDRESS CORRESPONDENCG TO:

I ASME Boiler and Pressure Vessel Code R. J. Bosnak u. cSF " =E Section III Division 1 and 2 Mechanical Engineering Branch l

Subgroup General Requirements Division of Systems Safety 1

Office of Nuclear Reactor Reculation 1

SUBJECT:

U.S. NUCLEAR REGULATORY COMMISSION Consideration of Class 3 Quality WASHINGTON, D.C.

20555 l

Assurance Requirements AGENDAITEM: GR 76-19 FILE NO.:

N/A DATE: Jgy 171977 To: Mr. H. Dobel, Chairman ASME Boiler and Pressure Vessel Code Section III Division 1 and 2 Subgroup General Requirements Babcock and Wilcox Company o

P. O. Box 1260 Lynchburg, Virginia 24505

Dear Mr. Dobel:

My letter to you of June 8,1976 indicated that members of the Regulatory Staff were concerned regarding the quality assurance requirements included in the Code for Class 3 items.

It may be helpful if I summarize this i

l concern as a prelude to suggesting a method for resolution. Regulatory Guide 1.26 indicates that the Class 3 technical requirements of the ASME Code should be applied to certain components and systems. Regulatory Guide 1.29 indicates that many of these same components and systems should be designated as Seismic Category I.

Regulatory Guide 1.29 further states that the pertinent quality assurance requirements of Appendix B to 10 CFR Part 50 should be applied to all activities affecting the safety-related functions of these items. Our review of the quality assurance i

requirements presently included in the Code for Class 3 f tems indicates that not all of the pertinent requirements of Appendix B to 10 CFR Part 50 are applied. Examples of deficiencies in this regard were included in my June 8, 1976 letter to you.

Subgroup item GR 76-19 has been established to address this question of coverage of quality assurance requirements for Class 3 items. During the discussion of this item during the meeting of the Subgroup on General Requirements, it appeared that part of the problem may be classification; namely, should any safety-related item of a nuclear power plant be clar,si-fied as Class 3.

The question was also raised as to whether or not a less than " full bicwn" quality assurance program, but one which.is con-sidered to be adequate for Class 3 items, could ever be accepted by NRC.

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.:..~..

H. Dobel '

l The problem with regard to Class 3 f tems may well ce one of classification in that it may not be intended by the cognizant code committees that i

Clas: 3 requirements be applied to safety-related items of the plant, l

If thct is the case tt;c appropriate action for NRC would be to reclassify 5

safety i alatad Class 3 items as Class 2 ftems. It appears to us, however, that the technical requirements (as opposed to quality assurance require-ments) not included in the Code for Class 3 items are adequate.

Reclassi-fying these items up to Class 2 in order to correct a quality assurance requirements deficiency would appear to cause the ap stringent technical requirements than is necessary. plication of more A more desirable approach is to attempt to reach agreement on the necessary quality assurance requirements for Class 3 items in the Code.

The answer to tis question - Will a less than " full blown" qualit assurance program for Class 3 items be accepted by NRC? - is yes,y but it requires some amplification. We agree that differences should i

exist with regard to the extent which the overall quality assurance program requirements are implemented depending upon the importance to safety of the covered activity. For maximum effectiveness and efficiency, a graded approach to QA program implementation should be provided.

Appendix B to 10 CFR Part 50 recognizes this concept. For example, Criterion Il states: "The quality assurance orogram shall provide control over activities affecting the quality of identified structures, systems, and components, to an extent consistent with their importance to safety."

3 l

Criterion IV also recognizes that selective application of quality assurance requirements to contractors and sub-contractors is necessary by stating: "To the extent necessary, procurement documents shall require contractors or subcontractors to provide a quality assurance program con-sistent with the pertinent provisions of-this Appendix."

Therefore, a less than " full blown" quality assurance program can be applied to a safety-related item for a nuclear power plant and still meet the overall quality assurance program requirements of Appendix B.

The quality assurance provisions included in NCA 4000 are basically overall quality assurance program requirements which we consider to be generally consistent with the overall program requirements of Appendix B.

It appears logical to us, then, that within these overall quality assurance program requirements included in the Code, a graded approach to the application of the program requirements is not only permissible but necessary and desirable. If some of the overall program requirements are omitted, as they are for Class 3 items, it aopears to us that key quality assurance provisions would be omitted entirely. For example, there are no quality assurance program requirements for design control for Class 3 items. As I have indicated earlier, many of these Class 3 items are required to be designed to withstand the Safe Shut-down Earthquake. If there is no requirement for control over the design process, what assurance is there that a Class 3 item was property designed to withstand the Safe Shutdown Earthquake?

I

i H. Dobel JAN 171977 We have compared the present coverage of the Code for quality assurance i

requirements for Class 1, 2 MC, CS, CB, and CC construction with the quality assurance requirements for Class 3 construction. A copy of this i

g comparison is attached. We have underlined those requirements for Class 1, i

2, etc. which we believe are also necessary for Class 3 construction for safety-related components.

As can be seen in this comparison, we consider that the overall quality assurance program requirements should be essentially the same for all safety-related items in the plant.

As indicated above however, this does not mean that detailed implementation of these program requirements cannot provide for less stringent measures for Class 3 than for the higher classes.

I hope the above discussion clarifies our concerns regarding Class 3 l

i quality assurance requirements. It is requested you consider this item with a degree of urgency.

Sincerely, l

W~

R. f. Bosnak Member, Subgroup General Requirements

Enclosure:

As stated cc w/ enc 1:

W. S. Gibbons R. E. Keever 9

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E segelsed by this Sest ien.

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a

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. 6,. roe s he e evie. erre ovei eeiease, diee r.h.s i.e. e.d s ee.e s.. e r de:.-

eens e tavoleiar desire setu legee.

sc a.4 3 )t. 4 rsecureseet Deseement Coetrol

+

beensent e fer erecareeeet of meteriale. Items and edcastr ac ted sessicce shall inglede rets.cenent e qe the ess ent eteeeeecy to ess.ge e seir tempt jes a tith E his 5es t se.e.

Ta t he es eems nec ese ss y. erec e.r.eest de:gge shall et eels e st2allana to previde_eJeal e t y I'vegree esmesteese enth the sequerement e el this Setti =,

ga gge shell tie ett eished se esser e that all twe c6Q aetet tal s titie'sT serv ete e te*forn se these seestrecent e dese pese=ces shell testude_jde,sificellee fet.18.a&&29111LIJed erasialena. at attitf.gjene _ for eenree eesleetleme7eTMI evidenc e of guagin g fi.emiehed he the s cplies. enseiose ee og the somece ord enemies =* eies.ree det ive, p. esa-4tn.s seece al. e. ruoud ee e.d see.inse

1. NI-4534. 5. Inssen'cllens Procesheres anddrawege at t i,ii tee of feet tae entit, es.eis be eene tted by due-eates seeseet.

e e 3(geAgegse s r es en.ieswiss a et a a vre enretow lete to the c iceemet enc eo e7eQt , pogreishm454,4r 7h, - - A g ~" be eteee.pli es.ed in ertwedes e t.seh thcee lastsettiene. seeeedg;3e. er dese.i as. denigr r g Q. Y,4 }~gO'.I. 4 M*ese%*t.8 e bas e.c e iem e. prec ed r es, or d r eeter e e%a t t ietelede e v iste esiset.ee er ~~' -p = 4 Gisetive re servie f o r de s een sn i=1 that lose s s ent eesse see Eeve 6een es:ae ree= s ee il s eeressi t e8'ea8 She Cevas tissee i. elder ebate seieseie e writtee desse4sies "eTshe preeedores eised by his erseminaties fee eentret el queltsy and eseelsettee, showie.g to deteit the lepteeentatise of the geelity esseeemse eegelreeense of thle 2 Secties of the CeJa. a teor of these precedwee shall be needian asettable for f use by seestemeties res sensen end 8ee mee b.y the Inspostere 7 i l i h 1 , t t i ,s' - 1 { t __...p-,.+.,-.a_,,._,__,.,,--->y-+- = m-wm ,%,,.,.,_.,__,..,,p.,gwm._, ,,,y-.n ,,,_sm..g##y ..,44 ,.cp e,. yu, ,_y p y. ,.-,.,,v ,.y,.i

'- % ' " '^- C Ld s.S L, Q IU Cj C Lss s.3 j i 14 A-4114. 6." Doe ument Cent rol e,t a.a n sa. a e.,e..e. c.e s,.a cpj ,y,, py g,, g T1.s m t.1 h Fe.r e...t. i t i.e t 4. me. ee. e. ...e..s e h, s...n e. sei v se6ve.twiler's atuality centrol aFstem

• g P'**id*' Precedures stilste mill assure that tie 8. test

. 4 4.or.. s e i, .e do.vce....en. ag_tae ch

• e * **e i f ie ' t i'*. - i***

.c***.= .e.. ine ldi

• ch*

hie.ets. h

• P10I'*kI* E'*'ig e, efesign calculatlons. specaiacatie.ns.

gg.... .a se..i.n. t we.. ...ta sh_' art e ' t <e t e -e n e r .c ts.u.4 e, e.,'i.,i,,e s m..g. and Instructis.e.s. as ocell.as authorised thonge s, se e weed _.ssee,i.e v.,ise,. -ee s.w e i n. e.., .y e e. i. e4 see.dc e.ne r. J e,ce...a f ee e. t ..e se..e h.r e ses ree.-e n ea4 'isr consit ustlen, .s icai.*es e s kg i cecei*ed c e e. eir d e pee r...,s.

w..

. I si et e.6 e4 e..a.s c e.: she tie.ee.e. h.es.r.ci m.84ee..N.iier (nl. p.e c.ee a...e...e g re.re...'..it ee..ide re <*d-s ee. hie..s i l..*.e e <*' e e s he t.e e. s e re i e.61. av. 6.r...reei f ie.w i. .4 4..e e.e e laa. er--s eed br o m. be.ie. 5:ee i fic.e1... .a 6. m._ mew. _. w i n.. ..a me,,,, ,6.m.... .....e. r., s ite s,.e i. e.e e.. s,. e...i. s i. e e.s i e 4 s ee s.o.i s... sca.4134.7 c...e t.sem. e m.s ee t t. s ee.e e ses.see. .6.it te e.e.6t t nee e.....e it.4_m!Lrresitetrims.tatist. p.A-4114.1. Co.neral et INrske med Materl.1 and leema' eso..,. 133.....a s e s,. c e. e r.. i. the e.g.i ee c.c o of t h -aams.as Sergemssta fMP & q%h , G 6* y M es.r# t e.eesti t t e r ..d.r..t. sec e len Ire ne [.~I'E ,.helt e.et.d. ode.s e f de.e so. fe ...e ori ee for. .eee..t.=ti .. oh ner s he e.i.e.e e.I g..t i e r f.e.S. d ghf g y

• e....i. i...e e n., e ec e..a e...i..e i...e+. de t i.ee e. Dec..c.e.e e e riae.: e

~ I'* i on-e t e ese..re t ier. .s..n s....eente.: ime e ee.ee i .e insv en t.e. sie be f.e,.e..e 6.si e n. "TU6... ,.eek..e4..e.e TIT 77'l e. aca-4:34.s see. sites.es ..a c tret et u.a.es.t. ne lie 14A-4118. S. Identillsation and Cont rol of Material an.1 lie nus 41 pe.. e e n.m.i n te e e.htiehee f.e (e.ne t tle.ii.. ..d .[1.e 54 Inek. ~l.e t.4i. a shall incl Je a egetem of ....eITIc oe ee. ret t e.I s r inte le.t ed ....c'ali.e. ...e,. ..e er ie n. 4 see... Thee. ,,geg,s.g sne.t rol abish mill a ssues that al.e material e r. ....e. .s.i t... e i;.e is e the sh e f.6eit.!st.e.arti..s.iskar_on.ats i.tse_st_ca s..* ee.. .f.ee.e ce i.e.nl.ed... selved is PemPcely IJennified and laas elocumentats.n intl.s*Iang gee,e d. e r ecette a. sh. 2 drii i ** *e e r* * ** IF.t..a n..tr.a tuti s s*. I L6 .h ic h n o.e.t * * *

• re t*** * ' h * * ** *'e e,c ei ved o ne e n e e.4 e......i1...Je !*c 'i'*

'"l'I ' ' d '* .e' 34I * * ' 'iII'

• II * 8 ' "' 'i
• 8 8 8 "l'* e ' * '

se ..e e s e.. . s e e e...* restwireel. TI metatarial control system et.all assure 43.24 i.*cee8i***- only* the Intended material le used 6a can.oructi.n. ~ s63 - Ist. =e.'

• e n e-ettas e
• ail _leati f'imi 8*. e-6
• hei t 6.

tre. lit.t..u.i=e ~a**ds.raLnstfista _61sh__stt legit!t eat eat ee!!Jee.] !! L.hg 9 sie i ig s en i eceef

• .tD*.lai*ted ea..!= t. that M H *** I e.e-Tee. 6in is.~T _g i

.g_33.tyt L*u.gtssi..t its se e.. I ty_ tie t ai s sea be.e1.a nn-J. t TiifTGe.t1 I egett_Elsmetrasm ehtlLttyettellte. T te l UI e*= =eseini uttsastd.t e. 6 e..t re.e .n eisig ei.e. ead 6e saa 5rtalta_at.21Lerttar_erststu!1's.tte l.Libt =_= e s e_1.a t .d e :n m meher- . l .e !!. ' P ! * ! ter!!i"fr*. .stittidd'.a!! 31.** *tt12.!titett8rasical.~1stajaL1 ht.sa Certi.lisd l'.t.!!_ t.is?iite *

• Me tr.*111s s 1 Iept e itt89.te. cit.tih t

r .!!!!! *!.!r_11* **e e Sefd **n beAllef t!d 6 ahe ee-ech ties e. cmsqli e..n s t .s t eei! f C rt s. se t..tri sf!L!h.it!!i!.!!! ?!!!!!*!.I.?.'L8Ef*! * *

• • d f ee.l.(_le e se e.

8 Its. t.f ts e bee. recci ed ee iewed.

• • 4 f. d ess ere.ble.

L'e te e U.iis.'ellie e.e.l..t i Or te.e ge.:.4..e s J.ce ed by eG~lert ific.s e el.ld.y 4] .e's.ee.i..ig 'iitfi TiG(I78 JiGWiiiri,piFif7 Gi~NT u GTa Tie ~.e1...e ee4 Fed.iii-t eF*l. i W li ie71eT.-^.UsieTiT i ... is.fih. a s ei = ~.T.7 IhiiT se.r.ce. F.e i.ci..T...I 4.R.e., ea,e,.4T.W.1..e. 6H G o.. y g e....ee..4...de.,. ir.i.re.salei.ne..e.e.=1.4t.ees.tsh. 1 .se e.et s o. ce e t.eee d he,1he Cer t i fie.t e Welder e e e.e te.t.t iv. ..t f or he. tin gr '..I e.s t.ge. Init i.t a..e et. end def e f.r t he.e e t i.it te e.hleh .I t e.e. se.. "I b 41-

\\ ( LA % $,p & l*l G C* % U * .} ( Q$3 } p k sca.4 n sa.s c..s..t.t me.f u e= 6.g. c .s e.eal... d a..s et t es se. 'e"""* '*

• NA.1134.3. Centrol of htanufatterleg anel testallatten Proce sse s 1-.

g.) _ne cnit rie. medee **II arnae =.d* . e te.Ile d a) The eguallty central systein eksil include presistems .d..,. e.c h.. p..ee.e dess e. hsr r* w ' 'w n. e 6*c h 3 h". '""G'3s *e e3.To. aanMetEr ) . g*F g,ag**tl"C ll*28 welail*C restforme to regwiremanet e l v e**t or e ci as tati ed og.s t!!?EL5_3. [ 'I E*'ll*" 1X **d Sat.se ctlen HD. l . E,p"U Ti eroeLe. tit =eese e?triji e4 se e g, ed n. ha.u n sa.13 te r en nea.eis **d 6r t..t e ens pen..is..es. e wuh .., te..a oi. see si ed i.g, Iri.d 5 V, enk i. o ai ee..e se. ... o u i s.. sw....u.e. e. i. e..i.a..d f sh.it *.geerwed, i.e t =J s.t t h. **e===<. 8 ..=6 ee s w The g.auir e. ..i.r.see...u,r e.iae,. i. er .,.ie.s ae 4. e.L.s ico i . to assure that liest tre.nersitette as resguireet Iy llais f,'" $ gf", ',*7* ',*d, mmh, N I., S* Ell *n are esse el. hitans shall 1.e indicatsd by EislaijiiIAT'~~ E***IIIUI' 8"l%u*g.lf3gn for eh..ia..s.n,_jju bt e. whicle the les; tester can satisfy himself al.at al.ers<, b

• t ne cen i t g_mg un

_sL.Lif 22 ti tht l.ite.s tI*!.!.* p*7th. e=d da u. e.d I 8== '** ** *c s !. 6 gr t he hymt tacatment racialremente att steet. Tids saar "g y w e, o s s i t e.: , be 1.y savi.w e,f furnace eirse..tereng.erature a ccords ei st t== ree ses *ad d e'. see.4. Lek _l.liea eiIstibC9?!!!!L6.det ait.11r eanel1tuudie ing3.dg.tM.dle[g e,s.e.R n.dMs $r " " - Sad - a,c.c .T... ....ue .e o.e - n.,u a.~.. .ois-e y4, the ere q!.#rper3:1 8 *=e ut ca __j.3.l?tj j!8'.!*t It!aille!!NE. e.,St.!.r***1t!?t!*tif_1*?.f'o ..ee ehet pr eee g es fee she glees.c~il,e= ,_f!1,...e 6.. n i d. .c a-413.. :. i. i.n s.. s.n o..d nu,ois... l "^-mi 2;;,g;alag Tai ad laere <ii - ~ ..) ....e

e. e..d n..

e. t..o ..a... o..n.. e..... ,t hngd an.g e e f.e.e e. wit h.ces E lie.e i.y @ TgT.~1 Ren.s{te.~e-*3.J - og 73,, 34,,,,g,,ngg.T7pT"1stTtrite=r*e truelley ee e ren [ .E M if.*,.! ? t,t*' '1 _ M*

• I" e** * ' h e

.. ergl ic.E*!.!!!* t e.desi g. dos e e. 4. "...'46.".."c s s e itie s s".t!!*"fy.f5,Et eYstem st.all li.t sl:o sonstasesion oPersteen.* 4. " * ' * * *d 'e 1 e, b ers ab guis a d g'.ilir~4ET ik ibit *. 7 studiaC th*8asaallent. **ifit388*tIY to permit ate M. pee.i&.n.g o if 3N"6aidVFi*isi 3ihd 5ITiiiii~si't*e 8*'*e43, . Q T m rene.. et.H set er r e dis ecan e ne nWIC&ie Inspector to dete rmine who specific inspecitans i e i s .k. n. n.go.e itt e ser the swa beleg_3,srtsefb i...e i.,. 6 )e 4.c_e., J..ree.rs e ph*etr. t.u?= lee t.e,r ce p i.e. aan g be prep.g.4, '. are to be performed. ( e ..e..a e e.. i.... u s. .e....... ..e.e. g g-pg

4. a. 6e r. seddiE.@i ri..iU fJiTei Jler ee.. lit.I'ia.l.'stsu b) TI.c sgu.ality control a stem sl.allInclude scevielene f

e n.da-e*!! !*19.3*3.Je s nu f.e a nec3nre. hiiielt st_stemp for identifying not.' structive ensniinaalen prece. I

• rJ *e st e.

s 1 i

.d dat.E redtes!!steit_atttt*Lttr"~a'intre ad 'a ne sangsta* Haw re.

a.,e. ine y m. i

x.m

%,.,in ieu se i ..leiii n es e castilie,J3i di.r e.d desg_ s g ihm utititir, Eh.ead <='rieted tr ihic~elieich be 1:enue,,,the e.uus contenn,widi th,e reguljemente of sl.se S.ction. tu=ts.9.91 18eet stell *eWil Jie.e. stgj Js t 68.a f atlita_ tar _.f titePIjeti_ fad!L12-4*l stoap RL1hs.J1tg. i (s)._..___ t%f eters beltasin1LaL2thh wit =*elen_ef ts.= fu t i nt l it.get.i s t r. tit.i,tz.silness Jklass'a ssestrialaints an.t.the.lattesse te Jbell i 69 indie pte d i s e. , cos sheese (Lca-404.p}m vest s'.etLeet trettiL6trand

==J.t e r.h*18e t..r**='. ?l!N'*t It't.it9?'#R eLibalerillasste fieldsr's repre. t u.s e s s., re s. eca..n.. n se e. c..u.i [ ? to $.cu rotete.a_shell._tt e!!!s's=8 ** ar ed a= * *lth__wr ist.a ette Jtti!. e es tens.es jbLjgg. ire.e.t e ud usggsuc'TlIdItp ,ne;gewee skleh i n... n.3( f uy regj u.b t. dengt_t=g wn, 3 _Isnt.terstf rea "dT lastade te.eleite! Jer.tet-reas that. L

• eens.intin_fer es. tina.ssss aue Acasamet thatmemata_iaetzunstetien.

j t o mit 46fteni mits artitat seur.nr11.maaiiaturittre fund. tr last ade sikk i te**

• a_ edte atd. ***1e'E s.a!*'_8aa. _ *tt.retef at e_st._i.s=e.atts.!;!!ss

s. sivi.ed t

g ... e e n e w s r. , e d ne.. v

s. icene.

.t e.w e e lr_... 1 f.e... e i,. d i s e u i c..J e e.u. ud etaiei. to du e w ei iii... ls.) iennens a haa kgen a.t da flad 1*sLittulli_shall te dumened anJ mt wud t..uw e f i ti s t Ar.1 re u,,,,, l 3 y

e e C Lass I., Q M, css C B <+ C C-class 3 e- ,e a.. n.. n ces. ei e ..or i., d re.e 1,..,.e.t m-m i. n. c...i e nie e,e,.,,,,, re e,,.,y,,,,,,, "n e a e r.v...r, xeu.F The h. o ,,,,g,, ses twee-n eh.sg e nt ekn eh-d e.d d.e.e.,s ed to.e.g e_ i"" ""a "e **~J

• t!

the calibrati .g e.eing..d.,',,,g,gg g,,,,, un net.is. eio= IiL '!I_'= *= '* " '**==< * *** =at =ad 'e.. e a ~~rne nt. - s.

n. spa.s?!s te r,e.' n-t L==J dge i

,,,,,,, g,8 *,,,,,,, '9 "; P ' "" S i*e ** I"tu t1h* titur p ht* * -

• d '* 9' Ga *=".

e.e e4' 'th *i."il l% 11".I *T.3_ U"u.s .r,p'a= * ** *** ** Tire s t seef u ne. intow.t.. e.z 4 ei t .n e l .eth.t_mq tst te:Etra tsu rs tsc e en d as.id tisatix._msast u s er ter_st uttal-i brui! !' tir e '" <" 'at tselitta ' * *' *"'" *** "-r"i r t.8J 8- ,P MeJ Es.I'd!_ ** **- 'a'qttle S t adia tati !fla!?tI_2J ih*LF*1rief W"'*d a m: elts. Lad'igtna ph st i t.' er.11.1ti.mnritarat ttee.f ut* ** irk legg_6 eve enttinahs, l g o nat ieceLet e=de Js. ***ere sawk e*

• J oede ee net.

an) Lt.{Q7.G Te^ 3 tit t isit ode erwiela.. for idensar laa t,.e

e..r.~ e.a. r d ei e.. e. 6.

ei em et t e., st a t.m s e e w..e..e u,. e r i _,uinut-sue i. ice n intt_. (s) I i j r, s e. c.i ne si s f+co _djpgin.ga.flg.L e ese.saallan er teoitat.eggejgiggit g . ihe cen e s se n e soiser es.e s on.co..e .. n.n i.e I f,, .uusa_n.tutetri. r><"iat e *11'm ea rrintir <Nttre inim the.inty e d i or.!!!.i.s a!.!*!!! ta9 *i u,n e a g e..ris* 6 e

• -t ei n.hus ths_t'stl_tr_ta-murdn errugate unit,.

t rittInt e, ist mgua mi p m.si n.. fir.se si.t.ts.atte ..ete hoy M.e ss. l e ti.n s eianom gamengu.rie.e n.y3 esse etec t o ee ,1** P-the cer t uersaygeg. ur e,Eit. st[eg.i. .e4 g e t..

i. deen Jiii;;t="sp~ T'd **!r be "G"E'"~b enhed e end f e e3."c"n ae f 7*.'T"T"*t,T'" 3 b uTs

,n FeiiTii' - d ' *

• r' s" "

I'd I di. re a ae esci, shall be 6EcI*JeJ es the fertIIIsete isolder's truelle, aseenrance Pe nge ne. stien + 6C A-4 8 84. 3 3 Beadling e St or ege Shipping end FTesereettee n { b 4 ftese.e s e ehell be est ablished to centret headt l a. steroge ehlprieg s glgeng. s or t e r atEs seid trescrwetion of ester is t end itsee le acc ord anc e sit) [ t g e t at t i ebed ins t r uc t iano. ee nc ed=rea. er de serseite. to s rs vent d essee detee le. I g gg et les s. them necessar v. esec ial covet ens e, eree sel egespeens. d oper eal teetec t ive enwisesweest e each es. ince t aa e steesehere. e pec i f ic.ei st e.e e en t e n t l evel e med tes*Per etore levet e shet t be ereti8ied, prooided e id their 8 e'aistence Ur e fied. I ~ aca-4 g )4. s. aseennettee en tenen staan 8m-43TUUTK3i'iin' allen er 3*reetso States j ~ee..... eheu se estanos a to is.d e. st e s,.se.ee.e.or n i.e ee, jg, " p4 " f** *.4 Td"O b 'hMm. 's,s w%. l es tie. tee ises. IMei'i~iMist tarWee sr.edst==IMe streate.ine_steisIH-e e N+ W %e(3=) afetseister>=t.inti_ud ~* m s tadhids!Lue=e. Net _mstist:.t thn11 rerlde . foe the Identlist enies of eksee itene we.iet seafc,r. to esaelseeises and test . tis =leMej e W iNif.d,s t =d *ta ***=='hu i'z f" *relin'i*a *ad **=** *l o f "te eUUtTW'tUELThii'l'Ia*bd* "*e'd**e* 8er esesvel t! t t3u 6 t s ee t is e.. 39 e< 3t:3..d H.rn e. a t e e laele. Sr -tt u.u Peace.fusa.: sistniet er stone i NA-4W 11 - tiencenterrna g gg g.,g g,, g,,,, re e..... e s..t se e.nsi t et#4 e e. tre s. i ee let e, s ee.e whic h de

• iUg g se gen t.trrrat.de s am e.fer==w e it h t he teruit e-e.e"e e L13i,2t er inut -

p'F8 8g,II l** A systent (er. gnyreegg** *I nentesiferenar.c r s ~~j* ""~ ga .si gegrese to reewi i= u ser to..rttraLatt r i"d Hat _s i sce v iae. D!ag eigee ge_gt3p fin t ies doc ument at ies,yg n e. l'esec en ettnance le any senseditlam wl.as t, egeg,,,,,,,,,,8,g# by tegen e: d dan *_115,33.ilydt gr gderNee ident

• Ith the applicable evlee of shie seggs b" += f *'w r $ 1 ' r e
• I h e ' * ** d I"_ *1*
• P' < *.
• I ter r enei_tg_acc ord ers.e with ee:=m t ee"cr eced.ne.4 e et 4.ef r=ias itees abelt be d@e.eaed.

i M' gtge n i..,2ern.ohent y t.: sment he correstcd er stina.lmated before the ts.tn.e ane nt 6_.s the 4:eaul: s is a t it y ,d e s.o.4 CerfMCTCd4 j ~ eg.s..t en ge. t" c a s. 6t a h a s.n o ro t dersher se.. l e _ f. son:cs fero ier.r d e(G i ro i s...e e-s e r..n. J i e.s enell te e e coes 6u e se e,reeJo.ec e sfit the en:itose t e } gese der.. rra s bie a deris sea a n s e e J s.ce f r ic a sta t t be est.al s ehed and e sit t e lsed. .tre s sent e da s P*s i s sam e d aaet.e tset.ing itene shel l be de. ented. e t - g-I m

e s E F g Lac.et ~ */ */ e s ' ~ ' i ,) us i n... c.ee.. ee.e.. i se. e ce. e.....e..,ug., e s e.e 2, u i.i.iese u,in,e m,1, .44 3*2!!il ttil. *! _8 112t!!a.2 *lI*"' 8 '"** a.$21,.e. t 1 11.129 LIE 1 Jf2lAtjrEE AtleEllit. eseee isj ej egysgge cad echee eserante =mece see rg,rmea l e ihaliljrd ar A gag r ed. != se.. e see mi eireI~f scses readit sens saweese en austit e the e gg. gag etL.2 es sue, eksi ik. e..s. er.i.e ee sie s. gree s e gijzje scienised i ggg gjtsgg p erlede seert e ien. We.Jemeilicat e.3 of eing11113t;L seedinians 31 gree to e.al es e. ahe come e the senJisine end the eeeeeesies wei en esse-l, sk*t !. he 88e*eeee eg _ g.f_3ypee tti ; ip(e_gfryggt!stg jerti t a f_asesstr.eeldinote nager, em g ehell es se esteed to the ses emenc e el s he subceseracter's secreesime :gigy t eeneeee. ,f 3Ca-4 8 M. f l Q lity Aseme eene tesorde c.) _

w. en 6 siesse et a shu tut te. tenen.ses s esseres*

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• d l T N AE4381.83.

t aste *of. f at t e thaniltux.astthtet.entttitt n It.*a._iJ.rstJ fitstletairher.ps estiesee anness. see _ inst sesene st e f ate shat t stee iset de eenesed deze mt r _ g. g.s t i te e 6..e e r ge sa ri, tee, e g en...tutt* cat as ecletela.rt=H.e. i ($1 m..c o.o s pet. s ies us-son.ine) emesie esi ie s..a s. e e-se es.4:n osal else. uten by is, i eresser ead she ha se 61s-3Jir e se

• Eglise ses =ee t e i.aieiace si.euli.Te' cevillicais et a,in.ilsemies te'4.e i

h_e!!, sah ea ide ai dure..!s.te.sion e.strr.t_s.! nasjs.Itettedgede -hine ?en bu e'ee.*k 8

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dns see e1L nue rece J. e. e6e.e ir i et ee e e rre.ar.e,4 a e en t.*ie ce 33_^e m.e e tiMen,t_t c e b. =iudii.rr-4 e.1u e e. ise ome*. et h s sessentiatrilluthts eedistifi.*6ett ustes.a.oresce etsreaistieg shet_str uitt iled ifLaJstiff,att!t. tmtirt.e f nin egen aar ass-seece tiegsee e see =e ec.f .stne =>t Nesta s.tstettet theti!t siuthis **=p*Insee u origiun i t !9a ?! tefilist aris sent <=pasii'2 es **e *eh *UI f e?. y!st tea id. 'h 8 g Jed a&!!!hd* fitut*e X J E t!t_If etedeLilealt!Et.AA.ir.de:lts t he_Sai!e ahEsJae t l e te erie esposeees fee demess F eevesegel, secesieg remnesse_ sed,seeytee see. P_g [ b der s Is!!$80ep b'ne se'il eree ames serig,gecrgr._p.elity Ass 4eme Peegeg eksi). eie pe iae e,epetee,f,:e essiigeog Ti mtetbl an see.n ee.idstid e ereeJ ac t a en. Ih we un es.it i.e e ceressible in = =at ta=** es ta ue. ee e geUJ. st {ggi o E _ M -4116. l }M~ise t he li f e e d s he el aa e o g t he er,eg . t i t.e J plane jse, the Caes siseeer fielder's eleal gr ethar locatlane desereimed bw eERJt) F 4e.. e..c a s. Jn) - _. Tht_h s rhell.Js.inte-ihlt !st_folauttaa ehe semes t se 6. es tateseed. s en scenes shotl egeL=de _Lhe felle*saa es e elete=eTI'W'- til__egl*.No posee=t racere e ttetHi*h ^ f stL2=.a sedance.se sei ince h2.sma waer 1.e his son t.ee.eeace inepres tee own stool _,heltje_,.s,a,sai*stien.atung !M4_le affilina. 8 !, a&e eieresite of theet reliastasha ter abe series etikstilitia i p ene. vs. _ ige ((GGl{"iE'l serly fee Clas n L aie.e in she. rb (

8. 2. ca. ac cc end ca.

fi rom mes 1 O.l,ue sseense f*'!tterha rtMig6} g.g e Gee.11_1221191'. pae sgrtgag. i we we ut intaded to fac14 ill_.Jhlgg {jg[,g?g att (aciedgj{ll31gf(g.Aggjed fet c le-seeg leg,le sMg* sien. e er nstee, we ownt ahtsid_itatide, thett atede when i, deelgees&og esseede for esteeties. ye [ 4 .w .m- ~~ b l' 9 t

O e o e C LA.s.s.3 f N cces i fied b e. . scec ific antese. Comee rw ales spee l t iestieto. (3) _og see..ege, med somete ee nee sepas s e (esca j}pg ~ (3L 12ta t(sultt. retFete esee eeddee e=6 ede.e<*rt**!T.Ali e _ fees s ete strie m'n!?*titm an

,e er.ra tt~ltsj eartif; sed Strese sepeste, steees g eltetet iume.

i e e r +. (4) t es seasse Seteet mitte teellintlee erseedios the applitetlisp et s 4 $sesse l'aposte. st rese e elcelet tene or Desige Repest to the se* een.seneted seedities thC4-3337. bt-3400. ka-31re. 34-3600 and a { f' bC-3 titia 4 [ t (1) h tegelved ee-eemetrotted evewiege seettiled se to settetteese s g (ar a 354)g 86) C=> tee et all Castilled tietesial Test Reporte (SS-tale, lit.Illt. e De-4120. CB 3830 end CC 3130): (J) As-bellt ehetch incloding lesettee of e.acrose pleseeeste e, sabe= native of e.sesiele (58-4131. C5-4882. CC-4133); and eesorde of 4 g pest-teselezieg togeesse, precedes e end leads. 4* (8) s.eedeste. sties eseeleot tee sepeete 4eeleddeg seeelte et f' shell else S ee the esee med $57-TC-la l enesiaatione. Tele seport easieg of the wbt pesosanel seterpret tes ste enemiset tee eseelse. linal vediegeophe skall be Geel.ded.hees eed6egeoghy hee 6ees i pes teseed the-Silelg ( (t) auwde es als kees tresseeste t as-320e eed as-4ase). mn su.ede es, be eith.e the best-seest smert e n a e eeney enasty. Liu et heet-enes time eed teeresetne **te nueitled by ame Ceenistaete estan. sua asesewat e res teemed 6, the p.es siel sies.tus.en se easiety segelseecote et the seensel op cifise-a tiene eer be nye sed e the Centisied ei.te,lel teet bepeet. (s)

• afsee seneu r.es tee, sejrec ge te,e, e.reeterLet intistleales.

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