ML19325D850

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Rev 11 to Section 3, Design Control, & Rev 77 to Page VII Re List of Effective Pages to Plant QA Manual
ML19325D850
Person / Time
Site: Pilgrim
Issue date: 10/10/1989
From:
BOSTON EDISON CO.
To:
References
NUDOCS 8910270031
Download: ML19325D850 (5)


Text

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  • * *' Boston Edison Company l Controlled Document RTYPE A2.21  :

TRANSMITTAL NOTICE IEAnlRltiALNumbfI CoatIslied Copy Numbtr DAtt_luutd j 89-396 20 10/16/89

+................................. ................+

NRC/ Office of Nuclear Reactor Regulation Assigned to < Instructions & Licensing Department l 1 White Flint North-ll555 Rockv{lle Pike  :

y Rockville, MD 20555 i

+..................................................,  !

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i Document (s): BEQAM, VOL.VME II; Page vii, Rev. 77; Section 3. Rev. 11  !

r l The attached Controlled Document (s) are transmitted for your use. Please insert / remove as indicated on the attached Change Instructions Notice. Then l check the appropriate block below, sign this form, and return it upon receipt f to: }

i Boston Edison Company i Controlled Document Clerk 25 Braintree Hill Office Park .

Braintree, Massachusetts 02184  ;

.COM HOLDER G EM QNE t

i [ ] I hereby certify that I have personally received from the sender the 1 material and attachments as indicated above, and I agree to comply with i the requirements set forth therein.  ;

L  ;

[ ] I am not currently in possession of the above documents. Please issue me  ;

another set.  !

l [ ] I am returning the documents listed above. l l

1 l Signed: _/ /89 i NRC/ Office of Nuclear Reactor Regulation Date b

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!. PDR ADOCK 09X,029 3 i P FDC 8 g

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Change instructions Notice (CIN)

Transmittal No.

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, - - Date: /0 /A, dh Please update your copy of - 3 EG AM, trith the attachments to this transmittal 45 instructed below.

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p BEQAM VOLLME II j LIST or EFFECTIVE Pacts SECTION PAGE NOS. SECTION REV. NO. M l 1

' 1 Title Page 07/20/83 l 11 3 07/16/87  :

111 5 07/20/83 i iv 5 07/20/83 i y 10 10/26/84 i vi 7 12/30/83 l vii 64 03/14/88  !

1 1-8 24 06/10/88 l 1 Figure II-1-1 24 06/10!88 ,

1 Figure 11-1-2 24 06/10/88 '

1 Figure 11-1-3 DELETED  ;

2 1-7 27 07/31/89  !

2 Exhibit II-2-1 27 07/31/89  :

3 1-2 11 10/10/89 4 1-4 20 09/25/89 .

4 Exhibit 11-4-1 20 09/25/89 l 5 1 and 2 13 07/24/87 6 1-2 10 02/12/88  ;

7 1-5 15 02/17/89  !

8 1 and 2 6 02/17/89 ,

9 1 and 2 5 07/20/83 l f

10 1 and 2 11 05/05/89 j 11 1 and 2 9 02/12/88  !

t 12 1-3 7 02/12/88 l 13 1 7 09/14/88 l

14 1 6 02/12/88 i 15 1-5 14 02/12/88 i 16 1-3 24 06/21/89 17 1-4 9 02/12/88 i 18 1-6 25 07/31/89 vii Rev. 77 Date: 10/10/89

i I

DESIGN CONIRQL l

1 3.1 PURPOSE This section establishes the requirements for the control of design I activities to assure that appropriate quality standards are specified i and design reviews are accomplished in a planned and orderly manner.

3.2 GENERAL j 3.2.1 Engineering and design activities associated with plant design '

changes and modifications of nuclear safety related structures,  ;

systems, and components are accomplished according to ANSI N45.2.11-1974 as amended by Regulatory Guide 1.64, Rev. 1.

3.2.2 Before implementation, plant design changes and modifications t are reviewed by responsible NED, QAD (quality category 0 changes I  !

and modifications only), ORC, and station personnel, and safety  !

evaluations are performed for design changes to assure l compliance with 10CFR50.59. If the Operations Review Committee (ORC) determines that an unreviewed safety item is involved, the Nuclear Safety Review and Audit Committee (NSRAC) reviews, and Nuclear Regulatory Cownission (NRC) approval is required through NED prior.to performing the change. Approved design changes and l modifications are implemented by the the Station Organization 1 -

O 3.2.3 with technice.1 guidance provided by NED.

When services designated quality category Q are purchased by the I

NED for performance of work associated with plant design changes ,

and modifications. 0AD reviews and approves the preliminary I ,

procurement documents to assure that appropriate quality assurance program requirements are included.

l ,

3.3 DESIGN CHANGE PROCESS  ;

3.3.1 A Plant Design Change (PDC) is used by BECo personnel to obtain I authorization for and to implement plant design changes and modifications to systems, structures, and components at the station. Subsequent changes to an approved PDC package are made using Field Revision Notices (FRNs).  ;

3.3.2 The cognizant personnel within the BECo Nuclear Organization, or approved supplier of engineering services, who are responsible for the engineering design inputs and design verifications  !

perform their functions according to written procedures to assure the following: .

3.3.2.1 Design documents are identified and controlled, and '

revisions thereto are reviewed, approved, collected, stored, and controlled in a systematic manner. l

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11-3-1 Rev. 11 l Page 1 of 2 Date: 10/10/89

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3.3.2.2 The individuals or groups responsible for design

.(\ reviews and other design verification activities and  :

their authority and responsibilities are identified i and design interfaces are controlled.  !

t 3.3.2.3 Plant design changes and modifications are reviewed, l approved, and controlled to assure compliance with >

10CFR50.59.

l 3.3.2.4 Applicable regulatory requirements and design bases i are correctly translated into specifications. l

. drawings, written procedures, and instructions. ,

3.3.2.5 Appropriate standards for quality are specified in i design documents and deviations and changes from such standards are controlled. ,

3.3.2.6 Sultable design controls are used in applying l principles of reactor physics and in making seismic,  !

stress, thermal, hydraulic, radiation, and accident l analyses.  ;

3.3.2.7 Design changes and revisions to design documents are ,

appropriately controlled to assure compatibility of materials; accessibility for in-service inspection,  !

maintenance, and repair; and delineation of acceptance  ;

criteria for inspections and tests.

3.3.2.8 Methods for' verifying design changes, such as design reviews, alternative calculations, and qualification i i testing are properly chosen and followed; the most  !

adverse design conditions are specified for test  :

programs used to verify the adequacy of designs. l 3.3.2.9 Individuals or groups responsible for design [

verification meet the requirements for independence j prescribed in Regulatory Guide 1.64 Rev. 1.  !

r 3.3.2.10 Design documents, including drawings and I specifications and approved revisions thereto, are l controlled and distributed to responsible individuals in the user organization in a timely manner, to preclude inadvertent use of superseded material, i 3.3.2.11 Errors and deficiencies that adversely affect safety related structures, systems, and components in the design process are documented and appropriate corrective action is taken.

3.3.2.12 Standard, off-the-shelf commercial or previously approved materials, parts, and equipment essential to the safety functions of structures, systems and

( components are reviewed for suitability of application.l i

11-3-2 Rev. 11 Page 2 of 2 Date: 10/10/89

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