ML20113C665
| ML20113C665 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 06/27/1996 |
| From: | Boulette E BOSTON EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BECO-LTR#96-061, BECO-LTR#96-61, NUDOCS 9607020043 | |
| Download: ML20113C665 (4) | |
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l 10CFR50.54(a)(3) a.
l Boston Edison Pilgnm Nuclear Power Station Rocky Hdi Roac' l
Plymouth, Massac%setts 02360 l
E. T. Boulette, PhD Senior Vice President - Nuclear June 27, 1996 Beco Ltr #96- 061 l
U.S. Nuclear Regulator / Commission Document Control Desk j
Washington, DC 20555 1
l License DPR-35 l
Docket 50-293
Subject:
Annual Report of Changes to the Boston Edison Quality Assurance Program Description As required by 10CFP50.54(a)(3), Boston Edison submits the annual summary of changes made to the Boston Edison quality assurance program description as listed in the Boston Edison Quality Assurance Manual (BEQAM), Volume ll. This report covers the period from July 1995 throug'a June 1996.
None of the changes summarized in Enclosure (A) reduce the commitments in the QA program description previously accepted by the NRC. The revised program continues to satisfy the criteria of 10CFR50, Appendix B.
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,,n E.T. Boulette RLC/dmc/beqam96 Encio are: (A)
Summary of the Boston Edison QA Program Description Changes (1996-1996) cc:
See next page 030006 9607020043 960627 Q u"O[
PDR ADOCK 05000293 P
PDR ii i
U. S. Nuclear Rsgulatory Cornmission June 27, 1996
- . Page '2 cc:
Mr. A. Wang, Project Manager Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation Mail Stop: 14D1 U.S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville, MD 02852 Chief of Materials Section l
Division of Reactor Safety i
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road i
King of Prussia, PA 19406 Senior NRC Resident inspector Pilgrim Nuclear Power Station l
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SUMMARY
OF THE BOSTON EDISON COMPANY QA PROGRAM DESCRIPTION CHANGES (1995-1996) l QA PROGRAM CHANGE #II-296 i
This change modifies scetion 15 of BEQAM ll as follows:
The discussion of the use of supplier finding reports was revised to separately identify supplier nonconfoiming items and other supplier
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conditions adverse to quality and more clearly address the section 7 requirements. The revision also clarifies the interface with section 7 and 4
4 provides consistency with the section 7 revisions.
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Organizational name changes were made to reflect the current Nuclear Business Unit organization chart.
The revised program incorporating this change continues to satisfy the criteria of 10CFR50, Appendix B, and the Safety Analysis Report quality assurance program
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description commitments previously accepted by the NRC.
4 QA PROGRAM CHANGE #II-297 This change modifies section 7 of BEQAM 11 as follows:
i The supplier finding report in paragraph 7.2, " General Requirements," was 1
replaced with a broader requirement addressing all conditions adverse to quality id3ntified during supplier oversight activities. The documentation requirements for the corrective action system that ensures proper resolution by BECo were expanded.
j Paragraph 7.8 was revised to restate the dispositioning of conditions adverse to quality using the corrective action system requirements as described in section 16 and consistent with the general statement of paragraph 7.2.
The sentence in paragraph 7.7 conceming audits of on-site suppliers' procurement and use of items was confusing and redundant to requirements of the overall control of suppliers delineated in this section and the audit program in section 18. The statement was deleted.
The term " item" was added in paragraph 7.3.1.c to clarify the scope of controls for uniquely qualified suppliers and the word " approved" was included to more clearly indicate the applicable status of that supplier's QA program.
In paragraph 7.3.'i.a, the term "non-approval" was changed to " conditional approval" to clarify when it is appropriate to use supplementary quality assurance requirements.
Page 1 of 2
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't in paragraph 7.5.1, the term " supplier's approval status" was added to the considerations for determining source inspection requirements.
l Several organizational name changes were made throughout the section to reflect the current Nuclear Business Unit organization chart.
The revised program incorporating this change continues to satisfy the criteria of 10CFR50, Appendix B, and the Safety Analysis Report quality assurance program i
description commitments previously accepted by the NRC.
QA PROGRAM CHANGE #ll 298 This change modifies section 1 of BEQAM 11 as follows:
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Organizational name changes were made to reflect recent organization realignment and renaming. Reference to the MOP manual was deleted and j
" Group" was added to the list of procedures to more clearly identify the j
methods of establishing the quality assurance program. The term " annual oral report" was deleted to eliminate the implication that the Quality Assurance Department Manager's access to the Executive Office is limited.
Also, the generic term " nuclear power plant" was replaced with Pilgrim t
Nuclear Power Station.
The revised program incorporating this change continues to satisfy the criteria of 10CFR50, Appendix B, and the Safety Analysis Report quality assurance program description commitments previously accepted by the NRC.
QA PROGRAM CHANGE #ll-299 This change modifies section 2 of BEQAM ll as follows:
1 Organizational name changes were made to reflect the current Nuclear Business Unit organization chart. Also, the generic term " nuclear power plant" was replaced with Pilgrim Nuclear Power Station.
The revised program incorporating this change continues to satisfy the criteria of l
10CFR50, Appendix B, and the Safety Analysis Report quality assurance program description commitments previously accepted by the NRC.
QA PROGRAM CHANGE #II-300 l
This change modifies section 3 of BEQAM ll as follows:
Organizational name changes were made to reflect the current Nuclear Business Unit organization chart.
The revised program incorporating this change continues to satisfy the criteria of l
10CFR50, Appendix B, and the Safety Analysis Report quality assurance program i
description commitments previously accepted by the NRC.
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