ML17257A467
| ML17257A467 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/22/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17257A466 | List: |
| References | |
| NUDOCS 8107150385 | |
| Download: ML17257A467 (14) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 4
"g SAFETY'VALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION UALITY ASSURANCE PROGRAM FOR FULL-TERN OPERATING LICENSE ROCHESTER GAS AHD ELECTRIC CORPORATION DOCYET NO. 50-244 1.0 Introducti on The quality assurance program for the full-tenn licensed operation phase. of.
Rochester Gas and Electric Corporation's (the licensee)
R.
E.
Ginna Nuclear Power Plant (Ginna) is described in Revision 7 to Supplement IV to the Tech-nical Supplement Accompanying Application for a Full-Term Operating
- License, "equality Assurance Program for Station Operation," July 1979.
Our review of
'the ouality assurance program Tor Ginna is based on the-prior acceptance of
'evision 6 to SI.pplement IV, discussions with representatives.
from the Rochester Gas and Electric Corporation (RGEE),
and our evaluation of Revision 7 and the RGKE letter of Apri*l 23, 19Bl which responded to our request for addi-tional information. It is the licensee's intention that the quality assur.-
ance program for the operation phase comply,with requirements of 10 CFR 50, Appendix 8, "equality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants" and with'pplicable quality assurance related Regulatory Gdides and ANSI Standards. shown in Table l.
2.0 Discussion
~0 The structure of the organization responsible for the operation of Ginna and for the establishment and execution of the operation phase quality assurance pro-gram is shown in the attached Figure 1.
The RGSE Vice President, Electric and Steam Production, has corpo'rate responsibility for operating Ginna in accordance with applicable adulatory requirements.
He is-responsible for establishing the policies and requirements necessary to assure safe and reliable operations af 07f $038/ 8f)+fj>>> ~~~i~n.
He has overall responsibi 1 ity for and authority to P
.direct quality affecting activities.-
He has delegated the responsibility
.for. the detailed-development and overall coordination of the quality assurance program to'he'Manager, 'gua1ity Assurance, who.reports through the'ngineering organization.'
)
The Manager, guality Assurance, located offsite, is responsible for establish-ing and executing the overall quality assurance program.
He is responsible for assuring that the program satisfies the requirements of 10 CFR 50, Appen-dix B, and for keeping'he total program updated.
He is responsible for assur-ing that all the planned and systematic actions necessary to provide adequate confidence that the Ginna Station will operate safely and reliably are estab-
.lished and folio&ed.
He provides management with cerning quality, i.ndependent of the individual or objective information con--
group directly responsible for performing'he specific a'ctivity.
He has the authority and organizational freedom to assure all necessary quality affecting
.for establishing and implementing a comprehensive activities are performed and audit program.
'he Manage>", guality Assurance and his staff are responsible for supervising both the onsite and offsite quality ass'urance program.
This includes writing quality assurance policies and procedures and reviewing the procedures of th' organizations participating in the quality assurance program.
They audit all aspects of the quality assurance program and ensure the correction of signifi-cant conditions adverse to quality.
They assure that proper codes, standards, and quality requirements are specified in design, procurement, and installa-tion documents.
They are responsible for assuring that the suppliers of safety-related
- material, equipment, and services are properly qualified, and they conduct audits and perform surveillance at suppliers'acilities.
\\ The responsibility for proper implementation of the quality assurance program requirements at Ginna has been assigned to the Ginna Station Superintendent, who is responsible to the Superintendent, Nuclear Production, for safe opera-tion of Ginna.
- Moreover, he is responsible for maintenance, repair, refueling, inservice inspection, modification, test, and inspection of quality-affecting activities in accordance with the requirements of the quality assurance pro-P gram.
The Ginna Station equality Control Engineer is responsible to the Station Superintendent, through the Assistant Superintendent, for supervising the station equality Control Organization which is responsible for assuring that activities affecting quality are prescribed and carried out in accordance with approved drawings, specifications, ar d procedures.
He is also responsi-N ble for coordinating inspection activities, for assuring that inspection requirements are included in approved procedures, for receipt inspection of incoming items, for processing nonconformance reports, for coordinating cor-rective. action reports, and for assuring that corrective action is taken.
The General Maintenance equality Control Coordinator is responsible to the Superintendent, General Maintenance, for verification acti vities for whi ch General Maintenance equality Control is responsible.
In addition, he is res-'onsible for assuring that maintenance activities affecting quality are car-ried out in accordance with approved drawings, specifications, and procedures; for the preparation of equality Maintenance procedures; for coordinating receipt inspection of incoming items; for routine surveillance of General Maintenance activities; and for coordinating nonconformance
- reports, corrective action
- reports, and the replies to audit reports.
3.0 Evaluation valet Assurance Pro ram The quality assurance organization is responsible for assuring that procedures and instructions provide for complete and adequate quality assurance require-t ments.
In addition, quality assurance personnel provide sufficient reviews, inspections, and audits to verify the effective implementation of the entire quality assurance program.
The licensee has s tructured i ts qual ity assurance program for the operation phase to be in accordance with Appendix B to 10 CFR Part 50, and compliance with the regulatory positions given in quality assurance-related Regulatory Guides and with the requirements of ANSI H45.2.12.
The quality assurance pro-gram is implemented by means of written policies, procedures, and instructions.
These documents result in control of quality-related activities involving safety-related items in accordance with the requirements of Appendix B to
' 0 ~
10 CFR Part 50 and with applicable regulations,
- codes, and standards.
The licensee' quality assurance program requires that implementing documen-tation encompasses detailed controls for (1) personnel indoctrination and
'training; (2) translating
- codes, standards, regulatory requirements, technical specifications, engineering requirements, and process requirements into draw-ings, specifications, procedures, and instructions; (3) developing, reviewing, and approving procurement documents, including changes; (4) prescribing all quality-related -activities by documented instructions, procedures,
- drawings, and specifications; (5) issuing and distributing approved documents;.
(6) purchasing item~nd servi ces; (7) i den tifying materi al s, parts, and compo=
nents.;
(8) performing special processes; (9) inspecting and/or testing mater-ials, equipment, processes, or services; (10) calibrating and maintaining
measuring equipment;= (11)-handling, 'storing, and shipping items; (12) identi-fang the inspection,'"test; and operating status of items; (13) identifying and disposing of nonconforming items; (14) correcting conditions adverse to quality; (15) preparing and maintaining quality assurance records; and (16) 4 4
auditing activities which affect quality.
equality is verified through checking, review, surveillance, inspection, test-ing, and audit of quality-related activities.
The quality assurance program requires that quality verification be performed by individuals who are,not directly responsible for perfo'rming the quality-related activities.
Inspec-tions are performed by qualified personnel in acc'ordance with. procedures, instructions, and checklists approved by the quality assurance organization.
The quality assurance organization is responsible for the establishment and implementation of the audit program.
Audits are performed. in accordance with pre-established written checklists by qualified"personnel not having direct responsibilities in the areas being audited.
Audits are performed to evaluate all aspects of the quality assurance program including the effective-ness of the quality assurance program implementation.
The quality assurance program requires the review of audit results by the per-son having responsibility in the area audited and corrective'action where necessary.
Continued deficiencies, or failure to implement corrective action, will be reported in writing by the quality assurance organization to the appro-priate management within the Rochester Gas and Electric Corporation.
Follow-up audits are performed to determine, that nonconformance and deficienci es are effectively corrected and that the corrective action precludes repetitive occurrences.
Audit reports, which indicate performance trends and the effective-
ness of the quality assurance
- program, are prepared and issued to responsible management for review and assessment.
Conclusion Based on our review and evaluation of the quality assurance program described in Revision 7 to Supplement IV to the Technical Supplement Accompanying the Application for a Full-Tenn Operating License for the R.
E.
Ginna Nuclear Power Plant as supplemented by the licensee's letter of April 23,
- 1981, we conclude that:
1.
The organizations and individuals perform>ng quality assurance func-tions have the required independence and authority to effectively carry out the quality assurance program without undue influence from those directly responsible for cost and schedules.
r 2.
The quality assurance program describes requirements, procedures, and controls that, when properly implemented, comply with the'equire-ments of Appendix B to 10 CFR Part 50 and with applicable quality assurance-related Regulatory Guides and ANSI Standards.
3.
The quality assurance program covers activities affecting structe.es, I
- systems, and components identified in the Final Facility Description and Safety Analysis Report.
Items designated as Seismic Class I on the list given in the SAR are subject to the pertinent provisions of the quality assurance program.
An evaluation of the acceptability of the list of structures,
- systems, and components is included in the scope of review of the Systematic Evaluation Program, Topic III-1, "Classification of Systems and Equipment."
4.
Updating Regulatory Guide commitments to include Regulatory Guide 1.146 and Revision 1 of Regulatory Guide 1.58 will be addressed separately in response to NRC's Generic Letter 81-01.
Accordingly, we conclude that the licensee's description of the quality assur-ance program is in compliance with applicable NRC regulations.
Attachment:
Figure 1
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TABLE 1
2.
3.
I NRC Regulatory Guide 1.8, Revision 1, "Personnel'Selection and Training."
NRC Regulatory Guide 1.28, Revision 2, "Quality Assurance Program Requirements (Desigo and Construction)."
AEC Regulatory Guide 1.30, Revision 0, "Quality Assurance Requirements for the installation, Inspection, and Testing of Instrumentation and Electric Equipment."
AEC Regulatory Guide 1.33, Revision 0, "Quality Assurance Program Requirements (Operation),"
and regulatory staff co+vents and supplementary guidance contained in the document entitled "Guidance on Quality Assurance Requirements During the Operations Phase of Nuclear Power Plants,"
Revision 0 dated October 1973 (Orange Book Revision 0).
5.
6.
AEC Regulatory Guide 1.37, Revision 0, "Quality Assurance Requirements for Clean-ing of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants."
AEC Regulatory Guide 1.38, Revision 2, "Quality Assurance Requirements for Pack-aging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants."
7.
AEC Regulatory Guide 1.39, Revision 2, "Housekeeping Requirements for Water-Cooled Nuclear Power Plants."
8.
9.
10.
AEC Regulatory Guide 1.58, Revision 0, "Qualification of Nuclear Power Plant in-
- spection, Examination, and Testing Personnel."
AEC Regulatory Guide 1.64, Revision 1, "Quality Assurance Requirements
.for the Design of Nuclear Power Plants."
AEC Regulatory Guide 1.74, Revision 0, "Quality Assurance Terms and Definitions."
AEC Regulatory Guide 1.88, Revision 2, "Collections, Storage, and Maintenance of Nuclear Power Plant Records."
13.
NRC Regulatory Guide 1.116, Revision O-R, "Quality Assurance Requirements for Installation, inspection, and Testing of Yiechanical Equipment and Systems."
NRC Regulatory Guide 1.123, Revision 1, "Quality Assurance Requirements for Con-trol of Procurement of Items and Services for Nuclear Power Plants."
14.
ANSI N45.2.12, D3, R4, 2/74, "Requirements for Auditing of Quality Assurance Pro-grams for Nuclear Power Plants."
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