ML17264A307: Difference between revisions
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{{#Wiki_filter:CATEGORY 1 REGUDRTOO~INFORMATION'DISTRIBUTION | {{#Wiki_filter:CATEGORY 1 REGUDRTOO~INFORMATION'DISTRIBUTION %STEM (RIDE) | ||
%STEM (RIDE)ACCESSION NBR:9601020057 DOC.DATE: 95/12/21 NOTARIZED: | ACCESSION NBR:9601020057 DOC.DATE: 95/12/21 NOTARIZED: NO 'OCKET I FACIL:50-244 Robert "Emmet,Ginna kQclear. Plant', Unit j., Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas '& Electric Corp. | ||
NO'OCKET I FACIL:50-244 Robert"Emmet,Ginna kQclear.Plant', Unit j., Rochester G 05000244 AUTH. | RECIP.NAME RECIPIENT=AFFILIATION | ||
Rochester Gas'&Electric Corp.RECIP.NAME RECIPIENT=AFFILIATION.JOHNSON,A.R. | .JOHNSON,A.R. | ||
==SUBJECT:== | ==SUBJECT:== | ||
Forwards Rev 22 to"QA Program'for Station Operation," incorporating organization related changes associated w/C>>'restructuring of corporation.' | Forwards Rev 22 to "QA Program 'for Station Operation," | ||
DISTRIBUTION CODE: Q004D COPIES RECEIVED:LTR | incorporating organization related changes associated w/ C | ||
05000244 E | >>'restructuring of corporation.' | ||
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT.415-2083)TO ELZMZNATE YOUR NAME FROM DZSTRZBUTZON LZSTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR,'.15 ENCL."15 I li A!;0>1 C f 4~~l~"p' 4ND I ROCHESTER GAS AND | DISTRIBUTION CODE: Q004D TITLE: | ||
~89 EASTAY&IUf, ROCHESlER, N.Y IrIiQ9-0001 AREA CODE716 546-27M ROBERT C.MECREDY Vice President Nuclear Operations December 21, 1995 U.S.Nuclear Regulatory Commission Document | COPIES RECEIVED:LTR Topical Report, Change, ENCL U Amendment, or Correspondence SIZE: | ||
ocket Utili QA ( | |||
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 E RECIPIENT COPIES. RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL JOHNSON,A 1 "1 INTERNAL: DRS/RGNl 1 1 DRS/RGN2 1 1 3 1 1 DRS/RGN4 1 1 ILE CE 2 2 NRR/DISP/IMS 1 1 NRR DRCH/HQMB 1 1 NUDOCS-ABSTRACT 1 1 OC/LFDCB 1 1 RGN1 FILE 1 1 EXT RNA DMB/OSS 1 1 ' | |||
IHS 1 .1 NRC PDR 1 D | |||
0 C | |||
U E | |||
NOTE TO ALL "RZDS" RECZPZENTS: | |||
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELZMZNATE YOUR NAME FROM DZSTRZBUTZON LZSTS FOR DOCUMENTS YOU DON'T NEED! | |||
TOTAL NUMBER OF COPIES REQUIRED: LTTR, '. | |||
15 ENCL. "15 I | |||
li A | |||
! | |||
;0 | |||
>1 C | |||
f 4 | |||
~ ~l~"p' | |||
4ND I | |||
ROCHESTER GAS AND EIECIIIICCORPORATION ~ 89 EASTAY&IUf,ROCHESlER, N. Y IrIiQ9-0001 AREA CODE716 546-27M ROBERT C. MECREDY Vice President Nuclear Operations December 21, 1995 U.S. Nuclear Regulatory Commission Document Attn: 'llen Control Project Desk R. Johnson Directorate I-1 Washington, D.C. 20555 | |||
==Subject:== | ==Subject:== | ||
Revised Submittal of Quality Assurance Program for Station Operation Rochester Gas 6 Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244 | Revised Submittal of Quality Assurance Program for Station Operation Rochester Gas 6 Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244 | ||
==Dear Mr. Johnson,== | |||
In accordance with 10CFR50.54(a)(3), enclosed is revision 22 to the Quality Assurance Program for Station Operation (QAPSO). Revision 22 incorporates organization related changes associated with the restructuring of the corporation. Our effectiveness review concluded that these changes do not impact commitments in the quality assurance program description previously approved by the Nuclear Regulatory Commission (NRC) and therefore do not require prior NRC approval. | |||
The changes are described in the attached Synopsis of Changes (Attachment 1) and in the enclosed program revision. Attachment 1 also provides the basis for concluding that the revised program continues to satisfy the 10CFR50, Appendix B criteria and does not reduce the scope of the quality assurance program. Changes made to revision 21 of the Quality Assurance Program for Station Operation are denoted by a single revision bar in the left margin. | |||
Attachment 2 is a copy of the QAPSO with changes denoted by highlighting or strike-out. | |||
These QA Program changes are considered effective immediately. | |||
Ver truly yours, Robert C. ecr dy GAH'It413 Attachments 1 and 2 Enclosure 1: QA Program for Station Operation Revision 22 | |||
'st601020057 951221 PDR ADOCK 05000244 P PDR OO( | |||
02003I | |||
xc: Mr. Allen R. Johnson (Mail Stop 14B2) | |||
PWR Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector | |||
ATTACHMENT 1 S no sis of Chan es Or anization and Position Title Chan es The following organization titles and position titles have been changed: | |||
"Senior Vice President, Customer Operations" to "Senior Vice President, Energy Operations" "Vice President, Nuclear Operations" to "Vice President, Nuclear Operations Group" "Division Manager, Support Services" to "Group Manager, Support Services" "Division Manager,'nergy Delivery" to "Group Manager, Energy Delivery" "Division Manager, Information Services" to "Group Manager, Information Services" "Nuclear Division Training" to "Nuclear Training" These changes are reflected throughout the revised document and are not identified at each occurrence in the following summary. | |||
17.1 MANAGEMENT 17.1.1 Methodolo Paragraph 3 Last sentence was revised to be consistent with the phrase used on the "RGRE Corporate Statement of QA Policy" Table 17.1.1-1. | |||
Paragraph 4 Reference to ANSI N18.2-1973 is removed as been superseded by ANSI/ANS 51.1-1983. | |||
it has Paragraph 5 - This paragraph has been rewritten to clarify | |||
,RGEE's method of applying a graded QA Program to items which are not classified as "Safety Related". | |||
ATTACHMENT 1 S no sis of Chan es 17.1 MANAGEMENT (Cont.) | |||
17.1.2 Or anization The following organization changes were made and are reflected throughout the text of the document and on the Figure 17.1.2-1 Organization Chart: | |||
The Senior Vice President, Energy Operations reports directly to the Chairman of the Board, President, and Chief Executive Officer. The Executive Vice President position no longer exists. | |||
~ Information Services now reports to the Energy Services vice Energy Operations. However, their functions in supporting the QA Program have remained the same. | |||
A new position, the Director, Operating Experience, has been assigned the responsibility of supporting root cause investigations and corrective action for significant conditions adverse to quality, and for evaluating and disseminating industry experience information. These responsibilities were previously assigned to the Manager, Nuclear Assurance. | |||
Plant Manager, "Procurement" was added to list of Ginna Station responsibilities for clarification. | |||
Department Manager, "Technical Support" for Ginna Operations Nuclear Engineering was revised for clarification. | |||
ATTACHMENT 1 S no sis of Chan es 17.1 MANAGEMENT (Cont.)17.1.2 Or anization The following organization changes were made and are reflected throughout the text of the document and on the Figure 17.1.2-1 Organization Chart: The Senior Vice President, Energy Operations reports directly to the Chairman of the Board, President, and Chief Executive Officer.The Executive Vice President position no longer exists.~Information Services now reports to the Energy Services vice Energy Operations. | Services Manager, Revised to eliminate redundancy in text. | ||
However, their functions in supporting the QA Program have remained the same.A new position, the Director, Operating Experience, has been assigned the responsibility of supporting root cause investigations and corrective action for significant conditions adverse to quality, and for evaluating and disseminating industry experience information. | Quality Assurance Manager, Revised to remove responsibilities now Nuclear Assurance assigned to the Director, Operating Experience and to add responsibility for trending and analysis of corrective action program data. | ||
These responsibilities were previously assigned to the Manager, Nuclear Assurance. | Group Manager, Revised to clarify responsibility for Support Services calibration of M6TE reference standards. | ||
Plant Manager, | Group Manager, Revised to clarify responsibility for Information Services calibration of installed electric meters. | ||
Department Manager, | Group Manager, Revised to eliminate redundancy in text. | ||
Manager, | Energy Delivery | ||
Group Manager, | |||
ATTACHMENT 1 S no sis of Chan es 17.1 MANAGEMENT 17.1.2 Or anization Cont.Review and Audit Organizations | ATTACHMENT 1 S no sis of Chan es 17.1 MANAGEMENT 17.1.2 Or anization Cont. | ||
~Nuclear Safety Audit and.Review Board Removed reference to the QA/QC Subcommittee of the NSARB.Plant Operations Review Committee Paragraph 2 | Review and Audit Organizations | ||
'I Removed requirement for PORC to provide written meeting minutes to the Vice President, Nuclear Operations Group and the Chairman, NSARB.These meeting minutes are retained as a record by Records Management. | ~ Nuclear Safety Audit and. Review Board Removed reference to the QA/QC Subcommittee of the NSARB. | ||
Dele ation of Work Paragraph was revised to provide clarification of QA Program requirements for external organizations. | Plant Operations Review Committee Paragraph 2 Removed last sentence. This sentence does not discuss the primary responsibilities of the PORC and is unnecessary. | ||
17.1.5 Personnel Trainin and uglification Paragraph was revised to provide clarification of requirements for training of personnel in QA policies and instructions. | 'I Paragraph 7 Removed requirement for PORC to provide written meeting minutes to the Vice President, Nuclear Operations Group and the Chairman, NSARB. These meeting minutes are retained as a record by Records Management. | ||
Dele ation of Work Paragraph was revised to provide clarification of QA Program requirements for external organizations. | |||
17.1.5 Personnel Trainin and uglification Paragraph was revised to provide clarification of requirements for training of personnel in QA policies and instructions. | |||
17.1.6 Corrective Action Paragraph was revised to provide clarification of requirements for identifying adverse trends in performance. | 17.1.6 Corrective Action Paragraph was revised to provide clarification of requirements for identifying adverse trends in performance. | ||
ATTACHMENT 1 S no sis of Chan es 17.1 MANAGEMENT (Cont.)Table 17.1.1-2 Su lementar Glossar Commitment | |||
Off the Shelf | ATTACHMENT 1 S no sis of Chan es 17.1 MANAGEMENT (Cont.) | ||
ANSI/ANS 3.1-1987, Section 4.7.Revised to clarify that qualification requirements apply to NSARB members only as addressed by this standard.17.2 PERFORMANCE/VERIFICATION 17.2.1 Methodolo Paragraph 1 | Table 17.1.1-2 Su lementar Glossar Commitment Revised to be consistent with definition used in the Nuclear Policy Manual. | ||
ATTACHMENT 1 S no sis of Chan es 17.2 PERFORMANCE/VERIFICATION (Cont.)17.2.4 Procurement Control Acceptance of Items and Services Revised for clarification and to allow for the use of methods such as sampling.17.2.5 Procurement Verification Paragraph 5-Revised for clarification and to allow for the use of post installation testing as a means of item acceptance. | Heavy Load Revised to include specific plant information. | ||
17.2.8 Test Control Paragraph 6-Revised for clarification. | Off the Shelf Deleted. Old term is no longer used. | ||
17.2.11 S ecial Process Control Paragraph 4-Revised for clarification of responsibility changed in previous submittal (Rev.21).17.2.14 Document Control Paragraph 1 | Safety Related Revised for clarification SSCs Safety Significant Revised for clarification SSCs Table 17.1.7-1 Conformance of Ginna Station Pro ram to ualit Assurance Standards Re uirements and Guides Regulatory Guide 1.26 Reference to ANSI N18.2-1973 is removed as superseded by ANSI/ANS 51.1-1983. | ||
Paragraph 3 Revised for clarification of method used to approve temporary procedure changes at Ginna Station.Temporary procedure changes receive the same level of review as permanent changes, and in addition receive approval by the Shift Supervisor. | it has been ANSI/ANS 3.1-1987, Section 4.7. | ||
Revised to clarify that qualification requirements apply to NSARB members only as addressed by this standard. | |||
17.2 PERFORMANCE/VERIFICATION 17.2.1 Methodolo Paragraph 1 Revised for clarification and consistency with 10CFR50 Appendix B. | |||
17.2.2 Desi n Control Paragraph 7 - Revised for clarification. | |||
ATTACHMENT 1 S no sis of Chan es 17.2 PERFORMANCE/VERIFICATION (Cont.) | |||
17.2.4 Procurement Control Acceptance of Items and Services Revised for clarification and to allow for the use of methods such as sampling. | |||
17.2.5 Procurement Verification Paragraph 5 - Revised for clarification and to allow for the use of post installation testing as a means of item acceptance. | |||
17.2.8 Test Control Paragraph 6 - Revised for clarification. | |||
17.2.11 S ecial Process Control Paragraph 4 - Revised for clarification of responsibility changed in previous submittal (Rev. 21). | |||
17.2.14 Document Control Paragraph 1 Revised for clarification. | |||
Paragraph 3 Revised for clarification of method used to approve temporary procedure changes at Ginna Station. Temporary procedure changes receive the same level of review as permanent changes, and in addition receive approval by the Shift Supervisor. | |||
Temporary procedure changes are approved by the Plant Manager or designee prior to implementation. | Temporary procedure changes are approved by the Plant Manager or designee prior to implementation. | ||
17.2.15 Records Paragraph 1 | 17.2.15 Records Paragraph 1 Revised for clarification. | ||
ATTACHMENT 1 S no sis of Chan es 17.3 ASSESSMENT 17.3.1 Methodolo Paragraph 3 Revised to remove reference to the QA/QC Subcommittee. | |||
Provides clarification of"Operational Assessment" as an assessment type and"Operating Experience" as an organization which performs this assessment. | ATTACHMENT 1 S no sis of Chan es 17.3 ASSESSMENT 17.3.1 Methodolo Paragraph 3 Revised to remove reference to the QA/QC Subcommittee. Provides clarification of "Operational Assessment" as an assessment type and "Operating Experience" as an organization which performs this assessment. | ||
17.3.2 Assessment Operational Assessment The responsibility for reviewing NRC Information Notices has been reassigned to Nuclear Safety and Licensing. | 17.3.2 Assessment Operational Assessment The responsibility for reviewing NRC Information Notices has been reassigned to Nuclear Safety and Licensing. | ||
The revised program, as described above, continues to satisfy the 10CFR50 criteria and does not reduce the scope of the quality assurance program.These changes do not require NRC approval prior to implementation.}} | The revised program, as described above, continues to satisfy the 10CFR50 criteria and does not reduce the scope of the quality assurance program. These changes do not require NRC approval prior to implementation.}} |
Revision as of 18:09, 29 October 2019
ML17264A307 | |
Person / Time | |
---|---|
Site: | Ginna ![]() |
Issue date: | 12/21/1995 |
From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
To: | Andrea Johnson NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
Shared Package | |
ML17264A308 | List: |
References | |
NUDOCS 9601020057 | |
Download: ML17264A307 (10) | |
Text
CATEGORY 1 REGUDRTOO~INFORMATION'DISTRIBUTION %STEM (RIDE)
ACCESSION NBR:9601020057 DOC.DATE: 95/12/21 NOTARIZED: NO 'OCKET I FACIL:50-244 Robert "Emmet,Ginna kQclear. Plant', Unit j., Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas '& Electric Corp.
RECIP.NAME RECIPIENT=AFFILIATION
.JOHNSON,A.R.
SUBJECT:
Forwards Rev 22 to "QA Program 'for Station Operation,"
incorporating organization related changes associated w/ C
>>'restructuring of corporation.'
DISTRIBUTION CODE: Q004D TITLE:
COPIES RECEIVED:LTR Topical Report, Change, ENCL U Amendment, or Correspondence SIZE:
ocket Utili QA (
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 E RECIPIENT COPIES. RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL JOHNSON,A 1 "1 INTERNAL: DRS/RGNl 1 1 DRS/RGN2 1 1 3 1 1 DRS/RGN4 1 1 ILE CE 2 2 NRR/DISP/IMS 1 1 NRR DRCH/HQMB 1 1 NUDOCS-ABSTRACT 1 1 OC/LFDCB 1 1 RGN1 FILE 1 1 EXT RNA DMB/OSS 1 1 '
0 C
U E
NOTE TO ALL "RZDS" RECZPZENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELZMZNATE YOUR NAME FROM DZSTRZBUTZON LZSTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR, '.
15 ENCL. "15 I
li A
!
- 0
>1 C
f 4
~ ~l~"p'
4ND I
ROCHESTER GAS AND EIECIIIICCORPORATION ~ 89 EASTAY&IUf,ROCHESlER, N. Y IrIiQ9-0001 AREA CODE716 546-27M ROBERT C. MECREDY Vice President Nuclear Operations December 21, 1995 U.S. Nuclear Regulatory Commission Document Attn: 'llen Control Project Desk R. Johnson Directorate I-1 Washington, D.C. 20555
Subject:
Revised Submittal of Quality Assurance Program for Station Operation Rochester Gas 6 Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson,
In accordance with 10CFR50.54(a)(3), enclosed is revision 22 to the Quality Assurance Program for Station Operation (QAPSO). Revision 22 incorporates organization related changes associated with the restructuring of the corporation. Our effectiveness review concluded that these changes do not impact commitments in the quality assurance program description previously approved by the Nuclear Regulatory Commission (NRC) and therefore do not require prior NRC approval.
The changes are described in the attached Synopsis of Changes (Attachment 1) and in the enclosed program revision. Attachment 1 also provides the basis for concluding that the revised program continues to satisfy the 10CFR50, Appendix B criteria and does not reduce the scope of the quality assurance program. Changes made to revision 21 of the Quality Assurance Program for Station Operation are denoted by a single revision bar in the left margin.
Attachment 2 is a copy of the QAPSO with changes denoted by highlighting or strike-out.
These QA Program changes are considered effective immediately.
Ver truly yours, Robert C. ecr dy GAH'It413 Attachments 1 and 2 Enclosure 1: QA Program for Station Operation Revision 22
'st601020057 951221 PDR ADOCK 05000244 P PDR OO(
02003I
xc: Mr. Allen R. Johnson (Mail Stop 14B2)
PWR Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector
ATTACHMENT 1 S no sis of Chan es Or anization and Position Title Chan es The following organization titles and position titles have been changed:
"Senior Vice President, Customer Operations" to "Senior Vice President, Energy Operations" "Vice President, Nuclear Operations" to "Vice President, Nuclear Operations Group" "Division Manager, Support Services" to "Group Manager, Support Services" "Division Manager,'nergy Delivery" to "Group Manager, Energy Delivery" "Division Manager, Information Services" to "Group Manager, Information Services" "Nuclear Division Training" to "Nuclear Training" These changes are reflected throughout the revised document and are not identified at each occurrence in the following summary.
17.1 MANAGEMENT 17.1.1 Methodolo Paragraph 3 Last sentence was revised to be consistent with the phrase used on the "RGRE Corporate Statement of QA Policy" Table 17.1.1-1.
Paragraph 4 Reference to ANSI N18.2-1973 is removed as been superseded by ANSI/ANS 51.1-1983.
it has Paragraph 5 - This paragraph has been rewritten to clarify
,RGEE's method of applying a graded QA Program to items which are not classified as "Safety Related".
ATTACHMENT 1 S no sis of Chan es 17.1 MANAGEMENT (Cont.)
17.1.2 Or anization The following organization changes were made and are reflected throughout the text of the document and on the Figure 17.1.2-1 Organization Chart:
The Senior Vice President, Energy Operations reports directly to the Chairman of the Board, President, and Chief Executive Officer. The Executive Vice President position no longer exists.
~ Information Services now reports to the Energy Services vice Energy Operations. However, their functions in supporting the QA Program have remained the same.
A new position, the Director, Operating Experience, has been assigned the responsibility of supporting root cause investigations and corrective action for significant conditions adverse to quality, and for evaluating and disseminating industry experience information. These responsibilities were previously assigned to the Manager, Nuclear Assurance.
Plant Manager, "Procurement" was added to list of Ginna Station responsibilities for clarification.
Department Manager, "Technical Support" for Ginna Operations Nuclear Engineering was revised for clarification.
Services Manager, Revised to eliminate redundancy in text.
Quality Assurance Manager, Revised to remove responsibilities now Nuclear Assurance assigned to the Director, Operating Experience and to add responsibility for trending and analysis of corrective action program data.
Group Manager, Revised to clarify responsibility for Support Services calibration of M6TE reference standards.
Group Manager, Revised to clarify responsibility for Information Services calibration of installed electric meters.
Group Manager, Revised to eliminate redundancy in text.
Energy Delivery
ATTACHMENT 1 S no sis of Chan es 17.1 MANAGEMENT 17.1.2 Or anization Cont.
Review and Audit Organizations
~ Nuclear Safety Audit and. Review Board Removed reference to the QA/QC Subcommittee of the NSARB.
Plant Operations Review Committee Paragraph 2 Removed last sentence. This sentence does not discuss the primary responsibilities of the PORC and is unnecessary.
'I Paragraph 7 Removed requirement for PORC to provide written meeting minutes to the Vice President, Nuclear Operations Group and the Chairman, NSARB. These meeting minutes are retained as a record by Records Management.
Dele ation of Work Paragraph was revised to provide clarification of QA Program requirements for external organizations.
17.1.5 Personnel Trainin and uglification Paragraph was revised to provide clarification of requirements for training of personnel in QA policies and instructions.
17.1.6 Corrective Action Paragraph was revised to provide clarification of requirements for identifying adverse trends in performance.
ATTACHMENT 1 S no sis of Chan es 17.1 MANAGEMENT (Cont.)
Table 17.1.1-2 Su lementar Glossar Commitment Revised to be consistent with definition used in the Nuclear Policy Manual.
Heavy Load Revised to include specific plant information.
Off the Shelf Deleted. Old term is no longer used.
Safety Related Revised for clarification SSCs Safety Significant Revised for clarification SSCs Table 17.1.7-1 Conformance of Ginna Station Pro ram to ualit Assurance Standards Re uirements and Guides Regulatory Guide 1.26 Reference to ANSI N18.2-1973 is removed as superseded by ANSI/ANS 51.1-1983.
it has been ANSI/ANS 3.1-1987, Section 4.7.
Revised to clarify that qualification requirements apply to NSARB members only as addressed by this standard.
17.2 PERFORMANCE/VERIFICATION 17.2.1 Methodolo Paragraph 1 Revised for clarification and consistency with 10CFR50 Appendix B.
17.2.2 Desi n Control Paragraph 7 - Revised for clarification.
ATTACHMENT 1 S no sis of Chan es 17.2 PERFORMANCE/VERIFICATION (Cont.)
17.2.4 Procurement Control Acceptance of Items and Services Revised for clarification and to allow for the use of methods such as sampling.
17.2.5 Procurement Verification Paragraph 5 - Revised for clarification and to allow for the use of post installation testing as a means of item acceptance.
17.2.8 Test Control Paragraph 6 - Revised for clarification.
17.2.11 S ecial Process Control Paragraph 4 - Revised for clarification of responsibility changed in previous submittal (Rev. 21).
17.2.14 Document Control Paragraph 1 Revised for clarification.
Paragraph 3 Revised for clarification of method used to approve temporary procedure changes at Ginna Station. Temporary procedure changes receive the same level of review as permanent changes, and in addition receive approval by the Shift Supervisor.
Temporary procedure changes are approved by the Plant Manager or designee prior to implementation.
17.2.15 Records Paragraph 1 Revised for clarification.
ATTACHMENT 1 S no sis of Chan es 17.3 ASSESSMENT 17.3.1 Methodolo Paragraph 3 Revised to remove reference to the QA/QC Subcommittee. Provides clarification of "Operational Assessment" as an assessment type and "Operating Experience" as an organization which performs this assessment.
17.3.2 Assessment Operational Assessment The responsibility for reviewing NRC Information Notices has been reassigned to Nuclear Safety and Licensing.
The revised program, as described above, continues to satisfy the 10CFR50 criteria and does not reduce the scope of the quality assurance program. These changes do not require NRC approval prior to implementation.