ML20069B793

Forwards Responses to RAIs 260.1-260.8 Transmitted Via NRC Re Sbwr Design

ML20069B793
Person / Time
Site:	05200004
Issue date:	05/24/1994
From:	Marriott P GENERAL ELECTRIC CO.
To:	Borchardt R NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20069B795	List: ML20069B793 ML20069B811 ML20069B824
References
MFN-075-94, MFN-75-94, NUDOCS 9405310143
Download: ML20069B793 (11)

Text

m, -*

GENuclear Energy Genere!Dectuc Depany 115 Curtner Avenue, Se Jose. CA 95125 May 24,1994 MFN No. 075-94 Docket No. STN 52-004 Document Control Desk U. S. Nuclear Regulatory Commission

- Washington, D. C. 20555 Attention: Richard W. Borchardt, Director Standardization Project Directorate

Subject:

NRC Requests for Additional Information (RAls) on the Simplified Boiling Water Reactor (SBWR) Design

References:

Transmittal of Requests for Additional Information (RAI)s Requesting the SBWR Design, Letter from M. Malloy to P. W. Marriott dated February 22,1994 The Reference letter requested additional information regarding the SBWR

. Quality Assurance Program. In fulGilment of t' is request, GE is submitting

- Attachment 1 to this letter which transmits the responses to RA!s 260.1-260.8.

Sincerely,

. /7 Marriott, Manager Advanced Plant Technologies M/C 781, (408) 9254i948 Attachment 1, " Responses to NRC RAls" cc: M. Malloy, Project Manager (w/2 copics of Attachment 1)

F. W. Hasselberg, Project Manager (w/l copy of Attachment 1) n e: r r r "

p Ch. y m _ p_ b i

[ RAI Number: 260.1 Question:

E Describe what.is meant by the term "SBWR Team Members " which is used in several places in Section 17.1 of the standard safety analysis report (SSAR). In addition, identify the Team Members.

- GE Response:

SBWR Team members are those companies who agreed to support GF. during the design and NRC certification of the SBWR. GE-NE document, NEDG-31836, SBWR wim Organization and Procedures Manual, identifies those team members who are nuclear system suppliers, architectengineers, constructors,. ,

utilities and universities with extensive LWR experience and complementary experience. When the project began, the SBWR team included ~Bechtel, Burns and Roe, Foster Wheeler, Southern Company, MIT. UCB, Ansalso, ENEA, ENEL, Hitachi, KEMA, NUCON and Toshiba. Many havejoined the team since that time.

4

n, y

t RAI Number: 5260.2-Question:

'SSAR Section 17.1.2 states that GE Nuclear Energy (GE-NE) and each ofits -

Team Members have their own quality assurance program as described in Reference 17.1.4 ("SIMR Design and Certification Program Quality Assurance Plan," NEDG-31831). Provide a copy of NEDG-31831 and describe the method by which GE found the Team Member's QA programs to be acceptable.

Response

As described in the attached SBWR Design and Certification Program Quality.

Assurance Plan, NEDG-31831, which requires that audits of GENE suppliers of -

Safety-related engineering services are conducted by QA representatives at least every three years, or more frequently, based on the following: (1) importance,'

complexity and quality requirements of the item or senice; (2) the resuhs of the previous audits; (3) history of performance of purchased service; or (4) efTectiveness of the implementation of the suppliers QA Program. For those years when an audit is not planned, a formal evaluation of the supplier is performed to determine if a re-audit is requiied during the upcoming year.

The International Technical Associates (ITAs) quality plans were surveyed for concurrence with NQA-1-1983 or an International' equivalent but were not included in the GE-NE approved supplier list as were the domestic team members. The same frequency of evaluation and audit was conducted for ITAs.'

as was conducted for domestic team members.

2

n er 4 h ,

RAI Number: _ 260.3l i Question:

Describe the provisions that control the design interfaces between GE-NE and the SBWR Team Members.

GE Response:

Design interfaces between GE-NE and the SBWR Team members is described - A in the SBWR Team Organization and Procedures Manual, NEDG-31836. -

NEDG-31836 addresses interfaces through the following organizational '

activities: (1) The Management Review Committee, which is composed of the senior management of organizations participating in the Program; (2) SBWR Working Groups, where cach working group consists of GE participants as well as participants from other team member organizations, all of whom report to the. .

GE-NE I cad engineer in accomplishing the technical work.

a

+

1

.i s

l j

.i 1

-j

y & s.; " - '

^ ' ^ -

s ,

4 h!

• ' RAI Number: l 260.4

' Question:

SSAR Section 19G.221," Procedures for Feedback of Operating, Design and Construction Experience," regarding wmpliance with 10 CFR 50.34(f)(3)(i) states that this is a combined operating license (COL) license information 4 requirement. Describe provisions for the feedback ofimportant industry design experience into the SBWR design.

GE Response:

GE-NE Procedure EOP 42-6.00, " Design Verification", includes the following _ 1 requirements in Appendix A, design verification guidelines,' Item A5, which states "Have applicable construction and operating experience been

[L considered?" This is one of the documented requirements for considering construction and operating experience by GE-NE during its design activities. In addition employee communication documents are periodically made available to all engineering personnel which describe the benefits of reviewing and applying the recommendations of the GE-NE Senices Information letters (SIL) p which are issued to describe feedback from experiences with operating plants.

L L

L u

p'.

l .-

H 3.

4 4 - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _

p.

[s B

RAI Number:: 260.5 Question:

. Describe what QA provisions apply to design-phase test programs, including the software QA controls.

GE Response:

The SBWR Design and Certification Quality Assurance Plan, NEDG-31831,

' Section 4, NQA-1-1983 and addenda /GE implementing procedure matrix, NQA-1 criteria, Design Control, calls out GE-NE Procedure EOP 40-3.00, " Engineering Computer Programs" for implementation of the requirements to control software codes used during design activities.' NQA-1 criteria, Test Control, calls.

out GE-NE procedure EOP 35-3.00, " Engineering Tests" for implementation of the requirements to control design phase test programs.

F F

f f

t RAI Number: 260.6 ' a Question: l Describe the QA provisions that apply to the appropriate items of Se'ction 3.3.1.4 of ANSI /ANS-52.1-1983, " Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants," including the safety parameter display system or its equivalent. ,

a

, GE-Response:

The SBWR Design and Certification Quality Assurance Plan, NEDG-31831,- ,

NQA-1-1983 and addenda /GE-Implementation procedure index, criteria 4,.

Design Control, references the appropriate GE-NE Engineering Operating Procedures which were applied to implement the requirements for the safety' .'

parameter display system described in Section 3.3,1.4 of ANSI /ANS-52.1-1983,

" Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plan ts."

'i

.i e

,b t

I l

r P

I' s-p

. RAI Number: ; 260.7 -

p ,

Questioni

- Provide a statement in SSAR Section 17.2 that the QA responsibilities for the

? operations phase is a COL responsibility.

[7 GE Response:

See attached revision to the SBWR SSAR Section 17.2 that states the QA .

responsibilities for the operations phase is a COL responsibility.

O t

.t

> 25A5113 R:v, A -

^<<~ '

SBWR . suaatsannyAufysis Report 17.2 Quality' Assurance During the Operations Phase Onef-S&WR S:2ndard Plani cccpe, r O_A responsibilities durine the constmetion and coerations chases are a COL responsibility. .,

I

,t I

h

^$

r i

?

r 1

i 1

l 1

j i

I l

l

' Ouality Assurance During the Operations Phase - Amendment 1 17.2-12 tiV17M.

.i ~J

.n

C

,1 .

~

c~ >

RAI Number: - 260.8:

Question: -i Provide a statement that QA requirements for construction are a COL .

responsibility.

GE Response:

See attached revision to the SBWR SSAR Chapter 17.2 that states that the QA - .

requirements during the construction are a COL responsibility, P

n b

l h

i

.- .a

-]

'l 8-

~i i

[ . . ..

j _; 25AS113 lbv. A l

SBWR .

sandcatsavenyAnstysis acport^

s

.f

.17.2 Quality Assurance During the Operations Phase Ot:t of SE".S. Standard Plant eccpe. .

t OA resoonsibilitics durine the constniction and onerations chases are a COL

~

resoonsibility. j r

i 1

.. i 9

i

.k i

i s

f i

-I

_~

i L

9 t

i 1

Quality Assurance Dur:ng the Operations Phase - Amendment 1 17.2-172

. S/17N4 L

, . - 4 2, .. - . _ . _ , , . , . . . -