ML20059H682
| ML20059H682 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/17/1994 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20059H676 | List: |
| References | |
| NUDOCS 9401310105 | |
| Download: ML20059H682 (168) | |
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RANCHO SECO i
QUALITY MANUAL i
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4 CONTROL DATE:
01/17/94 NUCLEAR OPERATING RECORDS MANAGEMENT SYSTEM PROGRAM NAME: VPO506GP CONTROL TIME:
11:29 OPERATING RECORDS TABLE OF CONTENTS PAGE:
1 FOR: LSTURGE - STURGEON. LOR 1 i
DOCUMENT TYPE: RSOM
- RANCHO SECO QUALITV MANUAL DOCUMENT ID REV STAT CHANGE NO EFF DATE EXp DATE SUBJECT RSOM-0AP 5
A 10/23/91 QUALITY ASSURANCE POLICV RSOM-I 7
A 8/03/92 ORGANIZATION R50#-11 6
A 8/03/92
-QUALITY ASSURANCE PROGRAM RSOM-Ill 6
A 12/16/93
. DESIGN CONTROL RSOM-IV 6
A 10/26/93 PROCUREMENT DOCUMENT CONTROL RSOM-V 6
A 1/11/94 INSTRUCTION
S. PROCEDURE
S AND DRAWING 5 RSOM-VI 6
A 10/26/93 DOCUMENT CONTROL RSOM-VII 6
A 1/11/94 CONTROL OF PURCHASED MATERIAL. EQUIPMENT AND SERVICES RSOM-Vill 6
A 1/11/94 IDENTIFICATION AND CONTROL OF MATERIALS. PARTS AND COMPONENTS RSDM-!X 7
A 1/11/94 CONTROL OF SPECIAL PROCESSES RSQM-X 7
A 1/11/94 INSPECTION RSOM-X1 6
A 1/11/94 TEST CONTROL RSQM-XII 6
A 1/11/94 CONTROL OF MEASURING AND TEST EQUIPMENT RSQM-XIII 6
A 1/11/94 HANDLING. STORAGE AND SHIPPING RSOM-XIV 6
A 1/11/94 INSPECTION. TEST AND OPERATING STATUS RSOM-MV 6
A 10/26/93 NONCONFORMING MATERIALS. PARTS OR COMPONENT 5 RSOM-XVI 6
4 10/26/93 CORRECTIVE ACTION R50M-XVII 6
A 10/26/93' OUALITY ASSURANCE RECORDS R$0M-XVIII 6
A 10/26/93-AUDITS T0iAL NUMBER OF RECORD 5:
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RSQM - POLICY 4
RANCHO SEC0 QUALITY MANUAL REVISION:
5 m
PAGE 10F 2 LEAD DEPARTMENT:
gTgEDATE i
NUCLEAR OUALITY ASSURANCE j
REVISION
SUMMARY
1.
Updated to reflect current organizational titles, responsibilities and requirements.
2.
Clarified Policy Statements II and III to be consistent with statements made in Section II of RSQM regarding the applicability of and responsibility for the Quality Assurance Program.
3.
Added " Revision Summary" page to this and all other sections of this Manual.
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THis PROCEDIWE IS ISSUED POR INFORf1ATl0N ORLY AND 9ffALL ft0T DE USED FOR WORK OR DESIGN.
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RSQM - POLICY
)
RANCHO SECO QUALITY MANUAL REVISION:
5 PAGE 2 0F 2 QUALITY ASSURANCE POLICY j
5-~
The Sacramento Municipal Utility District's (SMUD) policy regarding Nuclear Quality Assurance is as follows I.
Organizations involved in safety related activities shall be structured, managed, and operated to provide compliance with this manual.
Procedures and instructions shall be prepared to implement the activities required to provide direct support of the operation of Rancho l
Seco Nuclear Generating Station to achieve the following objectives:-
i a.
To comply with government regulations and established SMUD management policies and procedures, applying a systematic, t
disciplined and uniform approach to Quality Assurance, b.
To perform assigned work correctly the first time.
t c.
To provide facilities which are designed, modified, constructed, l
tested and operated in accordance with specified requirements, with assurance against failure or malfunctions, and without undue risks to the health and safety of the public, d.
To ensure prompt identification and resolution of actual and l
O potential problem areas in design, procurement, construction, testing, operations, maintenance and modification of safety related systems, structures and components.
5-II. The Rancho Seco Quality Assurance Program applies to activities, plans and programs affecting the operation and the quality of structures, systems, components, and services. This Program will be implemented by organizations responsible for achieving and verifying quality.
III. The Deputy Assistant General Manager, Nuclear has-delegated the responsibility and authority for development and execution of the Rancho Seco Quality Assurance Program to Manager, Quality Assurance. Any conflicts or questions involving interpretation of the requirements or resulting from the implementation of the Quality Assurance Program must be referred to the Manager, Nuclear Quality Assurance for resolution.
Paul BenTer Jf Shetler
- Manager, Deputy Nuclear Quality Assurance Assistant General Manager, Nuclear 1
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NUMBER:
RSQM - TOC RANCHO SECO QUALITY MANUAL REVISION:
6 O
e^ce i or 2 LEAD DEPARTMENT:
f5F{CTIVEDATE J-98 NUCLEAR 00ALITY ASSURANCE REVISION
SUMMARY
1.
Deleted columns for " Latest Revision" and "Date of Revision." This control is provided through Nuclear Operating Records Management System via the Procedures Control group in Administrative Services who maintain this status information.
2.
Added " Revision Summary" page to this and all other sections of tais Manual.
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j E'i PROCEDURE IS ISSUED POR INFORi1ATION ONLY AilD k
i AfALL tt0T DE USED FOR WORK OR DESIGN.
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i NUMBER:
RSQM - TOC RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 2 0F 2 RANCHO SECO QUALITY MANUAL TABLE OF CONTENTS SECTION NO.
TITLE 6-Quality Assurance Policy I
Organization
)
II Quality Assurance Program III Design Control l
[
IV Procurement Document Control i
V Instructions, Procedures and Drawings e
VI Document Control i
VII ControlofPurchasedMaterial,Equipmentand5ervices f
i VIII Identification and Control of Materials, Parts and Components i
IX Control of Special Processes X
Inspection j
XI Test Control I
XII Control of Measuring and Test Equipment XIII Handling, Storage and Shipping XIV Inspection, Test and Operating Status XV Nonconforming Materials, Parts or Components XVI Corrective Action XVII Quality Assurance Records XVIII Audits O
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NUMBER:
RSQM - SECTION I RANCHO SECO QUALITY MANUAL REVISION:
7 Os PAGE 10F 5 LEAD DEPARTMENT:
EFFECTIVE DATE:
NUCLEAR OUALITY ASSURANCE 08-03-92 REVISION
SUMMARY
The following revisions were made to make-the RSQM-Section I consistent with the Defueled Technical Specifications (License Amendment No. 119).
1.
Added General Manager responsibility statement.
(Para 4.1) 3.
Revised MSRC and PRC reporting chain.
(Paras 4.5 and 4.6) 4.
Revised MSRC review and audit activities.
(Para 4.6) r O
-. -- nay THIS PROCEDUEE IS ISSUED POR INFORl1ATl0N ONLY SD
<j M*ALL NOT BE USED. FOR WORK OR DESIGN.
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RSQM-SECTION I RANCHO SECO QUALITY MANUAL REVISION:
7 4
PAGE 2 0F 5 I.
ORGANIZATION i
i 1.0 PURPOSE This section describes the Sacramento Municipal Utility District (SMUD) organizations and personnel responsible for establishing, implementing, and verifying the Quality Assurance Program at Rancho Seco Nuclear Generating Station.
2.0 REFEREEE DOCUMEHIS 2.1 10CFR50, Appendix B, Criterion I, Organization 2.2 ANSI N45.2-1971, Section 2, Organization 2.3 Safety Guide 33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants 2.4 Rancho Seco Technical Specifications, Section 6.0 O
3.0 POLICY 3.1 The establishment and implementation of the Rancho Seco Quality Assurance Program shall be the responsibility of SMUD. Portions of the Quality Assurance Program functions may be delegated to other SMUD approved external organizations, but overall responsibility for the i
1 program is retained and exercised by SHUD.
3.2 Definitive lines of authority, responsibility and communication shall be established for those organizations involved in the Rancho Seco Quality Assurance Program.
3.3 Quality Assurance personnel assigned to Rancho Seco have defined responsibilities and organizational freedom to identify problems that affect quality; to initiate, recommend, or provide solutions; and to verify implementation of solutions.
They have the authority to initiate action to stop unsatisfactory work pending implementation of necessary corrective action to bring the unsatisfactory conditions into conformance.
3.4 The organizational structure and functional responsibility assignments shall be such that attainment of program objectives is accomplished by individuals or groups who inspect, examine, audit or otherwise verify conformance to established requirements, and who are independent of the individuals or groups who performed the original activity.
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RSQM-SECTION I
, O RANCHO SECO QUALITY MANUAL REVISION:
7 PAGE 3 0F 5 4.0 ORGANIZATION AND RESPONSIBILITIES 7+
4.1 The General Manager (GM) through the Assistant General Manager (AGM) and Chief Operations Officer.shall have corporate i
responsibility for overall. safe operation of the facility and shall take any measures needed to ensure acceptable performance of'the staff in operating, maintaining, and providing technical 2
support to the facility to ensure NUCLEAR SAFETY.
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4.2 The Deputy Assistant General Manager, Nuclear reports directly to the Assistant General Manager (AGM) and Chief Operations Officer of the Sacramento Municipal Utility-District.
The Deputy AGM, Nuclear assures that Rancho Seco is properly staffed and adequately budgeted to safely carry out its responsibilities.
He assures the staff responds to the recommendations of the i
Management Safety Review Committee (MSRC) and coordinates concerns relating to nuclear safety with the Manager, Nuclear Quality Assurance.
The Deputy Assistant General Manager, Nuclear is responsible for the safe and reliable decommissioning of Rancho Seco and reports to the AGM and Chief Operations Officer. The Deputy AGM has the O
resp nsibility and authority for development-and execution of the Rancho Seco Quality Assurance Program and ensures optimum quality performance of Rancho Seco.
In fulfilling this commitment, the 1
Deputy AGM shall conduct a final review of Rancho Seco Quality
.j Manual revisions and shall provide signature approval upon concurrence.
The Deputy AGM has delegated authority and responsibility for development and execution of the Quality Assurance Program to the Manager, Nuclear Quality Assurance.
The Deputy AGM, Nuclear is responsible for the administrative actions necessary to assure that the Rancho Seco Quality Assurance Program is implemented by-the organizations under his direction.
To this extent, the Deputy AGM shall maintain a continuing involvement in quality matters and shall assess the scope, status, implementation and effectiveness of the Quality Assurance Program through Quality Status Reports, Trend Analyses, Quality Audits or Surve111ances and Management Safety Review Committee (MSRC) meeting minutes.
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RSQM-SECTION I RANCHO SECO QUALITY MANUAL REVISION:
7 PAGE 4 0F 5 4.3 The Manager, Nuclear Quality Assurance reports directly to_the Deputy AGM, Nuclear, is independent from the pressures of other lines of authority, and ensures that an active Quality Assurance Program is implemented at Rancho S6:r in accordance with regulatory requirements.
The Manager, Nuclear Quality Assurance shall have sufficient authority and organizational freedom to identify problems that affect quality, recommend solutions, and verify implementation of solutions as appropriate. Commensurate with this responsibility is the authority to initiate action to stop unsatisfactory work and control further processing, delivery, installation, i
construction or modification or nonconforming items, or continuation of nonconforming services / operations, pending correction of the unsatisfactory condition.
l 4.4 Corporate and on-site organizational responsibilities are described in greater detail in Rancho Seco Administrative-Procedures. Specific duties and responsibilities for i
organizations whose activities affect quality are described in Sections II through XVIII of this manual, 7++
4.5 The Plant Review Committee (PRC) advises.the Deputy AGM, Nuclear and the Management Safety Review Committee (MSRC) on all matters i
related to nuclear safety.
The Committee composition.
responsibility and authority, subjects to be reviewed, and f
reporting requirements are addressed in'Section 6.0 of the Rancho Seco Technical Specifications and the PRC Procedure.
l 7+
4.6 The Management Safety Review Committee (MSRC) advises the AGM and Chief Operations Officer on facility operations. Composition,.
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responsibility and authority of.the HSRC as well as the subjects to be reviewed, administrative controls, and reporting requirements are addressed in Section 6 of the Rancho Seco Technical Specifications and the MSRC Procedure.
The MSRC also functions to provide for an independent review and audit of designated activities in areas of:
7+
a.
Facility Operation b.
Engineering and Nuclear Engineering c.
Chemistry and Radiochemistry d.
Radiological Safety
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e.
Quality Assurance Practices O'
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RSQM-SECTION I RANCHO SEC0 QUALITY MANUAL REVISION:
7 PAGE 5 0F 5 4.7 The Commitment Management Review Group (CMRG) is the senior management group responsible for reviewing all Potential i
Deviations from Quality (PDQ) to determine if a condition requires determination of the cause, extent, remedial corrective action and action to prevent recurrence.
The CMRG reviews and approves Deviation from Quality (DQ) dispositions and assigns 1
action for implementation.
The CMRG also determines whether a PDQ is potentially reportable under 10 CFR 21.
5.0 GENERAL RESPONSIBILITIES
)
Each organization involved in the design, operation, maintenance and modification of Rancho Seco is responsible for describing and clearly defining the duties and authority of individuals whose work affects quality.
Each organization has the responsibility to ensure that their procedures implement the Rancho Seco Quality Assurance Program requirements.
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q NUMBER:
RSOM - SECTION II C/
RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 10F 15 LEAD DEPARTMENT:
EFFECTIVE DATE:
@ CLEAR OUALITY ASSURANCE 08-03-92 REVISION
SUMMARY
1.
Updated References cited on Attachment II-l to agree with Defueled Technical Specifications.
(License Amendment No. 119)
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This PROCEDUEE IS ISSUED POR INF0bATION ONLY c dD f,
n, MALL NOT BE USED FOR WORK OR DESIGft.
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RSQM-SECTION II RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 2 0F 15 II.
QUALITY ASSURANCE PROGRAM 1.0 EUBf0SE The purpose of this section is to describe the Quality Assurance Program which shall'be implemented at Rancho Seco Nuclear-Generating Station.
2.0 REEERENCES 2.1 10 CFR 50, Appendix B, Criterion II, Quality Assurance Program i
2.2 ANSI N45.2-1971, Section 3, Quality Assurance Program 2.3 Safety Guide 33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants 2.4 10 CFR 71, Subpart H, Quality Assurance Requirements for Packaging and Transportation of Radioactive Material 3.0 E011Q The Quality Prog' ram described herein is designed to assure compliance with the requirements'of 10 CFR 50, Appendix B,
" Quality Assurance Criteria for Nuclear Power Plants and fuel Reprocessing Plants," including the requirements of_ applicable NRC Regulatory Guides, and ANSI Standards.
4.0 GEHEB8L_RE0VIREMERIS 4.1 This Quality Manual is organized to present the Rancho Seco Quality Assurance Program in the order of the 18 criteria of 10 CFR 50 Appendix B.
The manual states the Rancho'Seco policy for each of the criteria and describes how the controls pertinent to each are to be carried out. Any changes made to this manual that do not reduce the commitments previously accepted by the Nuclear Regulatory Commission (NRC) shall be submitted to the NRC 1
at least annually. Any changes made to this manual that reduce the commitments previously accepted by the NRC will be submitted i
to the NRC and shall. receive NRC approval prior to implementation.
The submittal'of the_ changes described above will be made in accordance with the requirements of 10 CFR 50.54(a).
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RSQM-SECTION II hm RANCHO SEC0 QUALITY MANUAL REVISION:
6 PAGE 3 0F 15 4.2 The Rancho Seco Quality Assurance Program is implemented by organizations responsible for achieving quality and by organizations respon",1ble for verifying quality.
j The Manager, Nuclear Technical Services is responsible to develop a Master Equipment List (MEL).
The MEL is a list of equipment that have been hssigned an equipment ID.
The MEL provides a ready reference for design and procurement information for each listed equipment. Q-List is a subset of the MEL, that includes i
all equipment that have been assigned QA Class 1 or identified as requiring Environmental Qualification.
The MEL is revised as a i
result of design changes.
4.3 The Quality Assurance Program applies to activities affecting the operation and the quality of safety related structures, systems, components, and services during plant operation, maintenance, testing and modifications.
]
Appropriate elements of this manual apply to emergency plans, radiation protection procedures, radioactive waste shipment programs, fire protection, effluent control and environmental j
g3 monitoring as indicated in Attachment II-1.
i 4.3.1 Attachment II-1 illustrates minimal regulatory and licensing requirements; implementing procedures shall meet or exceed these requirements.
4.4 The programmatic Regulatory Guides and ANSI Standards, and the applicable revisions, to which SMUD commits with regard to quality assurance matters and an appropriate explanation of interpretations and exceptions are tabulated in Attachment II-2 and II-3 of this section.
4.5 The extent to which the Quality Assurance Program and its controls are applied are established as follows:
a.
SMUD uses the criteria specified in Technical Services Procedures for identifying structures, systems and components to which the Quality Assurance Program applies; b.
This identification process results in a MEL which identifies safety-related items.
The MEL is a controlled document.
Safety-related items are determined by engineering analysis of the function (s) of plant structures, systems and components in relation to safe operation and shutdown; c.
The controls specified in the Quality Assurance Program
,d described in this manual are applied to safety..related items.
i NUMBER:
RSQM-SECTION II RANC 0 SECO QUALITY MANUAL REVISION:
6 i
PAGE 4 0F 15 4.6 Safety-related activities are accomplished under controlled l
conditions. Preparations for such activities include confirmation that prerequisites have been met.
4.7 Development, control, and use of computer programs affecting nuclear power plant safety-related design and operation are 1
subject to appropriate controls.
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4.8 Training and indoctrination programs shall be established to assure that personnel responsible for performing and verifying activities that affect quality have the required proficiency and qualifications to perform the assigned tasks.
4.9 Quality Assurance Program: ' Policy / Procedures / Instructions a.
The Quality Assurance Program is. documented by written Rancho Seco policies, procedures, and instructi.ons..The overall policies and general requirements are outlined in the Rancho Seco Quality Manual (RSQM).
Specific details related to implementation of the established quality l
policies are contained in the Rancho Seco Administrative j
Procedures (RSAP).
Additional implementing. procedures shall be prepared as required by the organizations responsible for l
performing the function.
The quality organization reviews i
such procedures to assure that quality-related functions are I
accomplished in a controlled manner, with specified I
equipment, under suitable environmental conditions,-and that prerequisites have been satisfied prior to inspection or testing.
b.
The Manager, Nuticar Quality Assurance is responsible fo the preparation, issuance, and control of the Rancho Sec..
Quality Manual.
c.
Proposed changes to the Quality Manual-shall be reviewed and approved by the Manager, Nuclear Quality Assurance and the AGM, Nuclear.
Requests to revise any portion of this manual shall be submitted in writing to the Manager, Nuclear Quality Assurance.
l d.
The Rancho Seco Quality Manual, including any changes, I
supplements, or attachmerts, is issued and maintained as a control!ad document.
e.
Rancho Seco Quality Manuals are assigned by the Manager, Nuclear Quality Assurance to managers of departments.
All changes will be distributed to the assignees and they will
,O be responsible f r inserting the revisions in their manuals.
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NUMBER:
RSQM-SECTION II O
RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 5 0F 15 4.10 Resolution of Differences The provisions delineated in the Rancho Seco Quality Manual shall take precedence over differing quality requirements specified in other departmental procedures until.the Manager, Nuclear Quality Assurance has evaluated the issue and determined which i
requirement (s) are to be modified.
Questions on disputes involving interpretation of the i
requirements or implementation of this manual must be referred to the Manager, Nuclear Quality Assurance for resolution and/or initiating changes to commitments or procedures as necessary to l
resolve the differences.
i i
4 4.11 Packaging and Transportation of Radioactive Material.
This Quality Assurance Program shall be applied to packaging and l
l transportation of radioactive material as specified in Ref. 2.4.
l 5.0 RESPONSIBILITIES General organizational responsibilities are described in i
Section I, ORGANIZATION.
l 6.0 AIJAQiMEllIS II-1, Application of Rancho Seco Quality Program Criteria II-2, Regulatory Commitments I
II-3, Exceptions i
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NUMBER:
RSQM-SECTION II O
RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 6 0F 15 ATTACHMENT II-l 9
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RSQM-SECTION II d
RANCHO SECO QUALITY MANUAL REVISION:
6
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PAGE 7 0F 15 l
l ATTACHMENT II-2 REGULATORY COMMITMENTS SMUD commits to the requirements of the regulations and industry standards listed below with any exceptions identified in Attachment II-3.
DOCUMENT REVISION /DATE TITLE
- 1. Reg. Guide 1.8 Personnel Selection and Training
- As referenced in the Tech. Spec.
- 2. Safety Guide 28 6/7/72 Quality Assurance Requirements ANSI N45.2 71 for Nuclear Power Plants
- 3. Reg. Guide 1.28 8/85 Supplementary Requirements for ANSI /ASME NQA-1 83 Quality Assurance Records (See Supplement 175-1 exception No. 1 in Attachment II-3)
- 4. Safety Guide 30 8/11/72 Quality Assurance Requirements t'%
ANSI N45.2.4 72 for the Installation, Inspection, and Testing of Instrumentation and Electrical Equipment (See exception No. 2 in Attachment II-3)
- 5. Safety Guide 33 Administrative Controls for Nuclear Power Plants
- As referenced in the Tech. Spec.
- 6. Reg. Guide 1.37 3/16/73 Quality Assurance Requirements for ANSI N45.2.1 73 Cleaning Fluid Systems and Associated Components of Hater-Cooled Nuclear Power Plants (See exception No. 3 in Attachment II-3)
- 7. Reg. Guide 1.38 3/16/73 Quality Assurance Requirements for j
ANSI N45.2.2 72 Packaging, Shipping, Receiving, Storage and Handling of Items for Water-Cooled Nuclear Power Plants (See exception No. 8 in Attachment II-3)
- 8. Reg. Guide 1.39 3/16/73 Housekeeping Requirements for Hater-ANSI N45.2.3 73 Cooled Nuclear Power Plants (See exception No. 4 in Attachment II-3)
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NUMBER:
RSQM-SECTION II l
O RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 8 0F 15 8
ATTACHMENT II-2 (Continued)
REGULATORY COMMITMENTS DOCUMENT REVISION /DATE TITLE-
- 9. Reg. Guide 1.54 6/73 Quality Assurance Requirements for ANSI N101.4 72 Protective Coatings Applied to Nuclear Facilities
- 10. Reg. Guide 1.58 9/80 Qualification of Nuclear Power Plant ANSI N45.2.6 78 Inspection, Examination, and Testing i
Personnel (See exception No. 5 in 1
Attachment II-3) i
- 11. Reg. Guide 1.64 10/73 Quality Assurance Requirements for the ANSI N45.2.11 74 Design of Nuclear Power Plants (See exception No. 6 in Attachment II-3) i
- 12. Reg. Guide 1.74 2/74 Quality Assurance Terms and Definitions j
ANSI N45.2.10 73 (See exception No. 7 in Attachment II-3)
- 13. Reg. Guide 1.94 2
Quality Assurance Requirements-for ANSI N45.2.5 78 Installation, Inspection, and Testing _of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants
- 14. Reg. Guide 1.116 6/76 Quality Assurance Requirements for ANSI N45.2.8 75 Installation, Inspection, and Testing of Mechanical Equipment and Systems
- 15. Reg. Guide 1.120 11/77 Fire Protection Guidelines for Nuclear Power Plants
- 16. Reg. Guide 1.123 7/77 Quality Assurance Requirements for ANSI N45.2.13 76 Control of Procurement Items and Services for Nuclear Power Plants 17, Reg. Guide 1.144 1/79 Auditing of Quality Assurance Programs ANSI N45.2.12 77 for Nuclear Power Plants
- 18. Reg. Guide 1.146 8/80 Qualification of Quality Assurance Program ANSI N45.2.23 78 Audit Personnel for~ Nuclear Power Plants
- 19. Reg. Guide 4.15 2/79 Quality Assurance for Radiological Monitoring Programs
h NUMBER:
RSOM-SECTION II RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 9 0F 15 i
4 ATTACHMENT II-3 EXCEPTIONS l
4 EXCEPTION NO. 1:
Reg. Guide 1.28/NQA-1, Supplement 17S-1 j
SMUD complies with the recommendations of this regulatory guide with the l
following clarifications:
l With regard to Section 2.4 of Supplement 175-1 titled.Index:
The phrase i
"an index" is clarified to mean a collection of documents or indices which, when taken together, supply the information attributed'to "an index" in.the standard.
The specific location of a record "within a storage area" may not be delineated (e.g. The specific location within a computer record file may i
not be constant.
Further, SMUD may utilize a computer assisted. random access filing system where such location could not be readily' l
" documented," or would such a location be " relevant.") The storage i
location will be delineated, but where file locations change with time, the specific location of a record within that file may not always be O-documented.
With regard to Section 4.3, Supplement 175-1 titled Safekeeoina:
l Routine general office and nuclear site security systems and access l
controls are provided:
No special security systems are required to be established for record storage areas.
With regard to Section 4.4, Supplement 175-1, titled Facility:
This Section provides no distinction between temporary and permanent facilities.
To cover temporary storage, the foljowing clarification is added:
" Records completed but not yet transferred for permanent storage i
may be temporarily stored in one-hour fire rated file cabinets.
In general, records shall not be maintained in such temporary storage for more than four months after completion without being microfilmed or placed in permanent storage. Open-ended documents revised or updated on a more-or-less continuing basis over an extended period of time (e.g.
personnel qualification and training documents, equipment history cards) which are cumulative in nature (e.g. nonconforming item logs and control room log books) shall become QA records when they are issued as a specific revision (e.g. the master audit schedule); when they are filled-up or discontinued (e.g log books or equipment history cards); on a predefined periodic basis when the completed portion of the on-going i
document shall be transferred to-records control as a " record" (e.g.
training and qualification records).
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RSQM-SECTION II 1
RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 10 0F 15 I
ATTACHMENT II-3 (Continued)
EXCEPTIONS i
EXCEPTION N0. 2: REG. GUIDE 1.30/ ANSI N45.2.4-72 Specific clarifications for ANSI N45.2.4 - 1972 are indicated below by sections.
Section 1.4 Definitions in this standard which are not included in ANSI N45.2.10 shall be used; all definitions which are included in ANSI N45.2.10 shall be used as clarified in SMUD commitment to Regulatory Guide 1.74.
Section 2.1 Plannina requirements, as determined by engineering, shall be incorporated into modification procedures.
Section 2.3 Procedures and' Instructions shall be implemented as set forth in Sections II, III, V, X and XI of this. program and by compliance with the Rancho Seco Plant Technical
. Specifications and Regulatory Guide 1.33 (ANSI N18.7).
Section 2.4 Results will be implemented as set forth in Sections X, XI, and XVII of this program and by compliance with ANSI N18.7 in lieu of the requirements set forth here.
S6ction 2.5.2 Calibration and Control covers three classes of instrumentation used by SMUD:
(1) M&TE (portable measuring instruments, test equipment,-tools, gages, and non-destructive test equipment used in measuring and inspecting safety-related structures, systems, and components); (2) reference standards (primary, secondary, transfer, and working); and (3) permanently installed process instrumentation (PI).
With respect to the first sentence, M&TE and. reference standards shall be included in calibration program and shall either be calibrated at prescribed intervals or shall be calibrated prior to use. With respect to the last sentence, personnel shall be trained and procedures shall require that the calibration sticker shall be reviewed to determine calibration status prior to use:
This label shall be considered to clearly identify i
equipment which is out of calibration.
Lack of a sticker shall require record review and affixing a new sticker based on calibration data.
M&TE and reference standards shall comply with sentences 2, 3 and 4.
()
NUMBER:
RSQM-SECTION II U
RANCHO SEC0 QUALITY MANUAL REVISION:
6 PAGE 11 0F 15 ATTACHMENT II-3 (Continued)
EXCEPTIONS EXCEPTION NO. 2:
REG. GUIDE 1.30/ ANSI N45.2.4-73 (Continued)
With respect to the third sentence, SMUD uniquely identifies each safety-related component of permanently installed process instrumentation.
This identification provides traceability to calibration data.
These actions are SMUD's alternative to the tagging or labeling of items to indicate the calibration date and the identity of the person who performed the calibration.
Permanently installed process instrumentation shall comply with sentences 1, 2, and 5.
Section 3 Preconstruction Verification will be implemented as follows:
(1) is required only for modifications, (2) no special checks are required to be made by the person
{
withdrawing a replacement part from the warehouse -
p/
equivalent controls are assured by compliance with
(
Regulatory Guide 1.38 (ANSI N45.2.2) as set forth in this table, and, (3) shall be complied with as determined by engineering, by individual technicians as part of the l
modification process.
t Section 5.1 Insoections, including subsections 5.1.1, 5.1.2, and 5.1.3, will be implemented as set forth in Section X of this program.
The inspection program will incorporate, as determined by engineering and Quality those items listed in these subsections.
Section 5.2 Tests, including subsections 5.2.1 through 5.2.3, will be implemented as set forth-in Sections III and XI of this program.
In some cases Surveillance testing may be used to meet the appropriate requirements of this section.
Section 6 Post-Construction Verification is not generally considered applicable at operating facilities because of the scope of the work and the relatively short interval l
between installation and operation.
Where considered necessary by engineering and Quality, the elements described in this Section will be used in the development and implementation of inspection and testing programs as describe in Sections III, X, and XI of this program.
O sectio" 7 o1 ^" ivs's
- 8 ev 'e *' "
iii 6 i P e e=ted s i
stated herein after adding the clarifying phrase "Where used" at the beginning of that paragraph.
i
N NUMBER:
RSQM-SECTION II
{s_ '/
RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 12 0F 15 ATTACHMENT II-3 (Continued)
EXCEPTIONS EXCEPTION NO. 3:
REG. GUIDE 1.37/ ANSI N45.2.1 73 Specific clarifications for this Regulatory Guide and ANSI N45.2.1 -
1973Property "ANSI code" (as page type) with input value "ANSI N45.2.1 -</br></br>1973" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process. are indicated below:
With regard to Paragraph C.3 of Regulatory Guide 1.37:
The water quality for final flushing of field systems and associated components shall be at least equivalent to rise quality of the operating system water, except for the oxygen and nitrogen content; but this does not infer that chromates or other additives, normally in the system water, will be added to the flush water.
With regard to Paragraph C.4 of Regulatory Guide 1.37:
Expendable materials, such as inks and related products; temperature indicating sticks; tapes; gummed labels; wrapping materials (other than polyethylene); water soluble dam materials; lubricants; NDT penetrant
{T materials and couplants, desiccants, which contact stainless steel or sJ nickel alloy surfaces shall not contain lead, zinc, copper,iaercury, cadmium and other low melting points metals, their alloys or compounds as basic and essential chemical constituents, no more than 0.1 percent (1,000 ppm) halogens will be allowed where such elements are leachable or where they could be released by breakdown of the compounds under expected environmental conditions.
1 With regard to Section 5 of ANSI N45.2.1 - 1973 titled Installation i
Cleaning:
The recommendation that local rusting on corrosion resistant alloys be removed by mechanical methods is interpreted to mean that local rusting may be removed mechanically, but the use of other removal means is not precluded, as determined by engineering or Chemistry.
i EXCEPTION NO. 4: REG. GUIDE 1.39/ ANSI N45.2.3-73 Specific classifications for ANSI N45.2.3 - 73 are indicated for specific sections below:
Section 1.4 Definitions:
Definitions in this Standard which are not included in Regulatory Guide 1.74 (ANSI N45.2.10) will be used:
all definitions which are included in ANSI N45.2.10 will be used as clarified in SMUD's commitment to Regulatory Guide 1.74.
,O
\\_/
NUMBER:
RSQM-SECTION II i
RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 13 0F 15 i
ATTACHMENT II-3 (Continued)
EXCEPTIONS EXCEPTION NO. 4:
REG. GUIDE 1.39/ ANSI N45.2.3-73 (Continued)
Section 2.1 Planpino:
SMUD may choose not to utilize the five-level
^
zone designation system, but will utilize standard janitorial and work practices to maintain a level of cleanliness commensurate with program requirements in the 3
areas of housekeeping, plant and personnel safety, and fire protection.
i Cleanliness will be maintained, consistent with the work being performed, so as to prevent the entry of foreign material into safety-related systems.
This will include, as a minimum, documented cleanliness inspections which
]
will be performed prior to system closure. As necessary, i
(e.g. the opening is_ larger than the tools being used) l control of personnel, tools, equipment,.and supplies will be established when the reactor system is opened for O
inspection, maintenance, modification or repair.
Additional housekeeping requirements will be implemented as required for control of radioactive contamination.
Section 2.2 Procedures and Instructioni: Appropriate procedures will be written and implemented.
Section 3.2 Control of Facilities:
SMUD may choose not to utilize the five-level zone designation system, but will utilize j
standard janitorial and work practices to maintain a i
level of cleanliness commensurate with program requirements in the areas of housekeeping, plant and personnel safety, and fire protection.
Cleanliness will be maintained, consistent with the work being performed, so as to prevent the entry of foreign material into safety-related systems. _This will include, as a minimum, documented cleanliness inspections which will be performed prior to system closure. As necessary, (e.g. the opening is_ larger than the tools being used) control of personnel, tools, equipment, and supplies will be established when the reactor system is opened for.
inspection, maintenance, modification or repair.
O Additional housekeeping requirements will be implemented as required for control of radioactive contamination.
i NUMBER:
RSQM-SECTION II O
RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 14 0F 15 l
ATTACHMENT II-3 (Continued)
EXCEPTIONS EXCEPTION NO. 5: REG. GUIDE 1.58/ ANSI N45.2.6 i
SMUD complies with the recommendation of the regulatory guide with the following clarification.
With regard to Paragraph C.5:
The Level III function of inspection planning, reviewing and concurring with inspection, examination and testing procedures is performed by designated individuals from the r
Quality & Industrial Safety Department.
EXCEPTION NO. 6:
REG. GUIDE 1.64/ ANSI N45.2.11 l
SMUD complies with the recommendation of the regulatory guide with the following clarification:
With regard to Paragraph C.2:
In exceptional circumstances, the designer's immediate supervisor can perform design verification, O
arovidee:
1.
The supervisor is the only technically qualified individual available.
2.
The need is individually documented and approved in advance by the supervisor's management.
3.
QA audits cover frequency and effectiveness of use of supervisors as design verifiers to guard against abuse.,
EXCEPTION NO. 7:
REG. GUIDE 1.74/ ANSI N45.2.10-73 SMUD complies with the recommendations of this regulatory guide with the following clarifications.
i SMUD reserves the right to define additional words or phrases which are not included in this Standard.
Such additional-definitions will be documented in appropriate procedures.
In addition to the Standard's definition of " Inspection,"~SMUD will use the following:
" Inspection (when used to. refer to activities-that are NOT performed by QC personnel) - Examining, viewing closely, scrutinizing, looking over or otherwise checking activities.
Personnel performing these functions are not necessarily certified to Regulatory Guide 1.58 (ANSI N45.2.6)."
I l
l l
l NUMBER:
RSQM-SECTION II
! O a^"cao seco ou^'tTv "^"ua' acvtsio":
6 PAGE 15 0F 15 ATTACHMENT II-3 (Continued)
EXCEPTIONS I
EXCEPTION NO. 7 (Continued)
When SMUD intends for Inspection to be performed in accordance with the OA Program by personnel certified as required by that program and for activities defined by " inspection" in ANSI N45.2.10, appropriate references to the plant QC organization or the procedures to be'used for performing the activity will be made.
If such references are NOT made, inspections are to be considered under the additional definition given above.
-l
" Independent Verification": - Verification by an' individual other'than the person who performed the operation or~ activity being veri.fied_that required actions have been completed.. Such verification may not necessarily require confirmation of the action at the. physical location j
if adequate remote indication of completion of action is available.
In 1
determining the acceptability of remote verification, the consequences of the action not being 1007. completed and the validity of the remote O
indication for confirming the completion-of the desired action will be considered.
Examples include, but are not limited to:. Verification of L
a breaker opening by observed remote. breaker indication-lights; l
verification of a set point (made with a voltmeter or ammeter for J
example) by observing the actuation of status or indicating lights at j
l the required panel-meter indicated value; verification that a valve has l
been positioned by observing the starting or. stopping of. flow on meter indications or by remote valve positions indicating lights.
" Hill" - (Not defined in any ANSI Standard) - Means the same as "shall" l
except when used to denote simple futurity.
When used to denote j
futurity, "will" is normally followed by "be".
EXCEPTION NO. 8:
REG. GUIDE 1.38/ ANSI N45.2 2 Section 2.7 Classification of Items - SMUD may choose not to. utilize I
the four level classification of items, but will address i
packaging and storage requirements for. Items based on the l
needs of individual items and manufacturers recommendation.
H
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION III REVISION:
6 TITLE:
DESIGN CONTROL PAGE 1 OF 5 LEAD DEPARTMENT:
FIF M VE DATE:
NUCLEAR OUALITY ASSURANCE 12-16-93 REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
2.
Removed references to the training simulator, technical support for the training simulator and environmental qualification.
O
=
THIS PROCEDURE IS ISSUED
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SffALL NOT DE USED FOR WORK OR DESIGN ON Om
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION III REVISION:
6
()
TITLE:
DESIGN CONTROL PAGE 2 OF 5 III.
DESIGN CONTROL 1.0 PURPOSE 6**
This section describes the Quality Assurance Program measures established for control of design activities affecting structures, systems and components at the Rancho Seco Nuclear Generating Station.
In addition, this section also defines the requirements for the development and implementation of control measures to assure that design functions affecting performance of operational, construction and modification activities are carried out in a planned, controlled, and orderly manner and are in compliance with applicable regulatory commitments.
2.0 REFERENCES
2.1 10 CFR 50, Appendix B, Section III, " Design Control" w6**
)
2.2 10 CFR 50.59, " Changes, Tests and Experiments" 2.3 Reg Guide 1.64/ ANSI N45.2.11, 1974, " Quality Assurance Requirements for the Design of Nuclear Power Plants", with exceptions noted in Section II of this manual.
2.4 ANSI N45.2, Section 4,
" Design Control" 3.0 POLICY The requirements specified in this section apply to all organizations performing design functions for modifications, changes, replacement or addition of structures, systems or components at Rancho Seco.
4.0 GENERAL REOUIREMENTS Procedures shall be established and executed to control design activities.
Procedures covering design control activities shall include the following requirements:
4.1 Applicable design inputs such as design bases, regulatory requirements, codes and standards, methodology and all
/~')
assumptions with appropriate justifications are Y-identified, documented and correctly translated into design output documents such as specifications, drawings, procedures or instructions.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION III REVISION:
6 O-TITLE:
DESIGN CONTROL PAGE 3 OF 5 4.2 Exceptions, waivers to or deviations from engineering requirements are documented and controlled.
4.3 Methods are specified for the selection and classification of suitable materials, parts, equipment, and processes used in-meeting applicable requirements for structures, systems and components.
Materials, parts, components and equipment which are 6-~
standard, commercial (off-the-shelf), or which have been previously approved for other similar applications are i
reviewed for suitability and appropriately classified.
4.4 Systematic methods are established for communicating and controlling the flow of related design information across the external and internal design interfaces, including any changes to the design information as the work progresses.
6-*
4.5 Interfaces between Technical Services and other participating design organizations (either internal or external to SMUD) are identified and documented.
This identification includes those organizations providing design inputs, design analyses, design specifications, and O
design verification for operational, construction and i
modification design activities.
4.6 Participating design organizations establish and describe the controlled methods for preparation, review, approval, i
release, distribution, and revision of documents (such as l
design analyses, specifications, drawings, reports) l involving design interfaces.
4.7 Verifying or checking the adequacy of design for modifications or changes performed.
Acceptable verification methods include, but are not limited to design reviews, alternate calculations or qualification testing.
If a test program is used to verify the adequacy of a design, it must include qualification testing of a prototype unit under the most adverse-design conditions.
4.8 Computer program codes used for design calculations are certified for use and their use is specified.
4.9 Design verification is performed by competent individuals or groups other than those who performed the original design but who may be from_the same organization.
This verification may be performed by the originator's supervisor provided the supervisor is the only technically O
qualified individual available and meets the appropriate clarification provisions of Ref.
2.4.
The results of the design verification efforts must be documented with the 1
identification of the verifier clearly provided.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION III REVISION:
6 O
TITLE:
DESIGN CONTROL PAGE 4 OF 5 4.10 Provisions are specified for the control of design analyses such as reactor physics,-stress, thermal, hydraulic, and accident; compatibility of materials; accessibility for inservice inspection, maintenance, and repair; and delineation of acceptance criteria for inspections and tests.
4.11 Design problems which are identified during field installation or testing activities shall be documented and 6**
forwarded to Technical Services for evaluation and resolution.
4.12 Design and specification changes, including field changes, receive the same degree of control and approval as the original design unless another qualified, responsible organization is specifically designated.
4.13 Errors and deficiencies in the design process, including computer programs, that could adversely affect structures, systems or components are documented and corrective action is taken to preclude repetition.
O Proposed modifications or design changes which involve an 4.14 unreviewed safety question or a change to the Rancho Seco Technical Specifications are handled in accordance with the requirements of 10 CFR 50.59.
I 4.15 Modifications are reviewed by plant personnel for effect
~
on plant operation prior to making the modification operational.
4.16 Design documents are reviewed for accessibility of equipment and components for inservice. inspection, tests, maintenance or modifications.
l 4.17 Design and/or test documentation must be obtained from all suppliers on procurements of ASME code components used for l
replacement or modification to Rancho Seco.
5.0 RESPONSIBILITIES i
General organizational responsibilities are described in Section I, ORGANIZATION.
64*
5.1 Technical Services is responsible for implementing a design control process per this section and to:
(f Provide and control design change packages.
a.
b.
Optimize nuclear fuel value and reactor safety by managing fuels management and core analysis.
~...
7-MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
-RSQM-SECTION III' REVISION:
6 TITLE:
DESIGN CONTROL PAGE 5 OF S i
c.
Ensure integrity and regulatory conformance of configuration control.
d.
Provide plant configuration control including establishing and maintaining baseline documents.
e.
Provide computer engineering support for plant 6**
computers, IDADs, etc.
f.
Perform probabilistic analysis in support of plant design.
6-g.
Provide engineering support to the Rancho Seco nuclear organization.
h.
Provide and maintain engineering procedures, standards and specifications and drawings.
6-*
i.
Prepare and maintain the Master Equipment List described in Section II.
6-*
5.2 Nuclear Quality is responsible for:
{
Review and concurrence of design control procedures.
a.
b.
Monitoring implementation of the Design Control Program.
I Auditing the Design Control Program per-Section XVIII c.
of this manual.
i O
x i
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION IV t
REVISION:
6 l
O TITLE:
PROCUREMENT DOCUMENT CONTROL PAGE 1 OF 5 LEAD DEPARTMENT:
ElYaTIVE DATE 10-26-93 NUCLEAR OUALITY ASSURANCE i
REVISION
SUMMARY
r 1.
Updated to reflect the current Rancho Seco organization.
j C
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i O
I l
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- - - - -.., m%aw T'as PROCEDURE IS ISSUED POR INFORf1ATION ONLY AND MiALL NOT BE USED ForR WORK OR DESIGN.
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION IV REVISION:
6
()
TITLE:
PROCUREMENT DOCUMENT CONTROL PAGE 2 OF 5 IV.
PROCUREMENT DOCUMENT CONTROL l
l 1.0 PURPOSE 6-~
This section describes the Quality Assurance Program measures established to control procurement documents for material, equipment and services at the Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion IV, Procurement Document i
Control 2.2 ANSI N45.2-1971, Section 5, Procurement Document Control 2.3 Reg Guide 1.123/ ANSI N45.2.13-1976, Quality Assurance i
Requirements for Control of Procurement of Items and Services for Nuclear Power Plants l
()
3.0 POLICY Procurement documents for Rancho Seco materials, i
equipment, components / spares or services shall include applicable technical requirements, quality requirements, regulatory requirements and other provisions necessary to assure that purchased items and services are adequately described to the supplier.
4.0 GENERAL REOUIREMENTS 4.1 Procedures shall be established and implemented to control the preparation, review, approval and issuance of procurement documents.
4.2 Procurement documents shall include provisions for the following, as applicable:
a.
Description of item or service.
1 b.
Identification of design specifications and technical j
requirements by reference to specific drawings, codes, regulations, industry standards or other documentation, including the applicable revision I~)
thereto, that describe the items or services to be b-furnished.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION IV i
REVISION:
6 e
k TITLE:
PROCUREMENT DOCUMENT CONTROL PAGE 3 OF 5 c.
Identification of test, inspection and acceptance i
requirements, and any special instructidns and requirements for activities such as design, fabrication, identification, cleaning, erecting, l
packaging, handling, shipping and extended storage.
d.
Identification of applicable QA Program criteria.
e.
Applicability of 10 CFR 21.
j i
f.
Identification of the documentation, such as i
drawings, specifications, procedures, fabrication and inspection plans, inspection and test records, personnel and procedure qualifications, and chemical and physical test reports to be prepared and maintained by the supplier or contractor, and requirements for submittal to SMUD for review and approval.
g.
Identification of those records to be retained, controlled and maintained by the supplier or contractor and those to be delivered to SMUD at the time of shipment of the procured item.
h.
SMUD's right of access to the supplier's facilities and records for inspection and audits.
i i.
Extension of applicable requirements to lower tier subcontractors and suppliers, including SMUD's right of access to facilities and records.
j.
Supplier submittal of nonconforming items and SMUD approval for " Accept-as-is" or " Repair" dispositions of nonconformances.
I k.
SMUD's right to hold shipment if procurement document requirements, including those for documentation, have not been fulfilled.
4.3 Technical and quality review by qualified personnel and approval by designated individuals shall be performed prior to issuance of the procurement document.
The review and approval shall be documented and available for verification.
4.4 Review and concurrence by Quality shall be performed to assure adequacy of quality requirements and to verify that the requirements are correctly stated, inspectable and
()
controllable; that there are adequate acceptance and rejection criteria; that the procurement documents have been prepared, reviewed and approved in accordance with the requirements of the established procedures.
I MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION IV REVISION:
6 O'
TITLE:
PROCUREMENT DOCUMENT CONTROL PAGE 4 OF 5 4.5 Materials Group shall verify that the supplier is on the Approved Suppliers List ( ASL).
4.6 Revisions to procurement documents shall receive an j
equivalent review and approval as the original documents.
Exceptions to this include changes in quantity, estimated i
price, cost codes, taxes, format or editorial changes that do not affect the quality of the item or service.
I 4.7 Procurement documents for spare or replacement parts for l
safety-related structures or systems shall specify procurement controls'at least equivalent to those required j
for purchase of the original equipment.
4.8 Methods shall be established to assure that the items j
received are traceable to procurement documents.
5.0 RESPONSIBILITIES i
l
~
General organizational responsibilities are described in j
Section I, ORGANIZATION.
O6-i 5.1 General Services is responsible to:
j a.
Purchase items in conformance with procurement' documents.
t b.
Purchase safety-related items from approved l
suppliers.
t c.
Arrange for suppliers to be placed on the Approved Suppliers List.
d.
Arrange for source. inspection when specified on the procurement documents.
6-5.2 Technical Services is responsible to:
a.
Maintain a staff of qualified Engineers who provide technical and quality requirements for. purchasing safety-related items.
5.3 Nuclear Quality is responsible for:
a.
Review and concurrence of material management procedures.
()
b.
Review and concurrence of procurement documents for safety-related items.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION IV REVISION:
6 O
TITLE:
PROCUREMENT DOCUMENT CONTROL PAGE 5 OF 5 c.
Auditing the procurement program per Section XVIII of this manual.
d.
Developing and maintaining an Approved Suppliers List.
i O
O
i i
l MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:.
RSQM-SECTION V TITLE:
INSTRUCTIONS, REVISION:
6 PROCEDURES & DRAWINGS PAGE 1 OF 3 l
LEAD DEPARTMENT:
EFFECTIVE DATE:
i NUCLEAR OUALITY ASSURANCE 01-11-94 l
i F
REVISION
SUMMARY
1.
Updated to reflect the current Rancho-Seco organization.
l i
i j
O j
SffALL NOT DE USED FOR WORK l
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i MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION V TITLE:
INSTRUCTIONS, REVISION:
6
{O PROCEDURES & DRAWINGS PAGE 2 OF 3 1
V.
INSTRUCTIONS, PROCEDURES AND DRAWINGS a
1.0 PURPOSE 6**
This section describes the Quality Assurance Program measures established to assure that all the activities affecting the quality or safety of the Rancho Seco Nuclear l
Generating Station are described and accomplished in accordance with documented instructions, procedures, 2
drawings or other documents appropriate to the circumstances, l
2.0 REFERENCE DOCUMENTS
]
2.1 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures and Drawings i
2.2 ANSI N45.2-1971, Section 6, Instructions, Procedures and Drawings 2.3 Safety Guide 33/ ANSI N18.7, Administrative Controls for O
Nuclear Power Plants 3.0 POLICY Activities affecting the operational safety or quality performance at Rancho Seco shall be described by and implemented in accordance with documented instructions, procedures, and drawings.
4.0 GENERAL REOUIREMENTS 4.1 Written instructions, procedures, drawings, or other documents appropriate to the circumstances shall be prepared to provide measures for complying with the provisions of the Rancho Seco Quality Program.
4.2 Instructions, procedures, or drawings shall include applicable quantitative and/or qualitative acceptance criteria for verifying that the activities have been satisfactorily accomplished.
4.3 The responsible organizations shall establish procedures which define responsibilities and delineate the sequence
()
of actions to be accomplished in the preparation, review, approval and control of instructions, procedures, or drawings, and changes thereto.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION V TITLE:
INSTRUCTIONS, REVISION:
6 O
PROCEDURES & DRAWINGS PAGE 3 OF 3 4.4 Activities affecting quality shall be accompl,ished in accordance with approved instructions, procedures, and drawings.
5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
6*
5.1 Each department is responsible-for assuring that activities affecting quality performed by their departments are described in instructions, procedures and drawings.
5.2 Nuclear Quality is responsible for performing audits to verify that any activities affecting quality are described in instructions, procedures and drawings.
Audits shall be conducted in accordance with Section XVIII of this manual.
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VI TITLE:
DOCUMENT CONTROL REVISION:
6 LEAD DEPARTMENT:
PAGE 1 OF 3 s/
NUCLEAR OUALITY ASSURANCE 12YECTIVE DATE 10-26-93 REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
i O
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i l
3 -
'MS PROCEDURE IS ISSUED POR INFORMATION GsMLV AfiD na.w %... c..
v, w.h i.
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aitALL NOT BE USED FOR WORK OR DESIGN
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VI TITLE:
DOCUMENT CONTROL REVISION:
6 PAGE 2 OF 3 VI.
DOCUMENT CONTROL 1.0 PURPOSE 6**
This section describes the Quality Assurance Program measures established for the issuance and control of Rancho Seco Nuclear Generating Station. documents i
]
2.0 1
REFERENCE DOCUMENTS t
2.1 10 CFR 50, Appendix B, Criterion VI, Document Control i
2.2 ANSI N45.2-1971, Section 7, Document Control 2.3 i
ANSI N45.2.11-1974, Section 7, Document Control 3.0 POLICY
\\
i Applicable documents, including changes thereto, that-1 Rancho Seco shall be issued and controlled in'a O
{
that precludes the use of inappropriate or outdated r
i documents.
4.0 GENERAL REOUIREMENTE 4.1 issuance, Procedures shall be established for the review requirements such as instructions, procedures, cha
- approval, and other documents which implement the quality assurance drawings program.
4.2 Procedures which establish document control measure include:
shall a.
Identification of documents to be controlled;
~
b.
Identification of individuals or organizations responsible for the review, approval, issuance and revision of documents; Criteria to ensure that adequate technical and c.
quality requirements are incorporated prior to implementation; O
MANUAL:
RANCHO SECO QUALITY MANUAL i
NUMBER:
RSQM-SECTION VI TITLE:
DOCUMENT CONTROL REVISION:
6
,/TNv)
PAGE 3 OF 3 d.
Review of changes to documents by the same organizations that performed the initial review and'
{
approval or by the organizations designated in accordance with the applicable procedures.
)
4.3 controlled documents, and distributed to organizations noted on distributionin lists so that proper and current documents are available as required, identified and not used for prescribed activitiesand obso 4.4 Master lists or equivalent means shall be used to identif the current revision of controlled documen.
y made available at work locations as appropriate.and shall be ts, 5.0 RESPONSIBILITIES General organizational r3sponsibilities are described i Section I, ORGANIZATION.
n 6*
5.1 Document Control is responsible for developing and implementing a document control program in accordance'with this section.
5.2 Each department is responsible for:
a.
Defining document review, authority in department procedures. approval and revision b.
with quality assurance-related aspects by Nu Quality as appropriate.
5.3 Nuclear Quality is responsible for:
i Review and concurrence-of document control a.
procedures, b.
Review and concur with procedures, documents that implement the Quality Assuranceinstructions or
~
Program to assure compliance with the applicable provisions of this manual.
c.
Auditing the document control program per Section-XVIII of this manual.
O
^
l l
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VII TITLE:
CONTROL OF. PURCHASED MATERIAL, REVISION:
6 i
EOUIPMENT AND SERVICES PAGE 1 OF 4 LEAD DEPARTMENT:
EFFECTIVE DATE:
NUCLEAR OUALITY ASSURANCE 01-11-94 REVISION
SUMMARY
l 1.
Updated to reflect the current Rancho Seco organization.
i i
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6 I
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' N S PROCEDUEE IS ISSUED POR INFORMATION ONLV AND
-. - _.rt%LL NOT DE USED FOR WORK OR DESIGN.
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i 1
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VII TITLE:
CONTROL OF PURCHASED MATERIAL, REVISION:
6
()
EQUIPMENT AND SERVICES PAGE 2 OF 4 VII.
CONTROL OF PURCKASED MATERIAL, EQUIPMENT AND SERVICES 5
1.0 PURPOSE 6-~
This section describes the Quality Program measures established to assure that material, equipment and i
services purchased for the Rancho Seco Nuclear Generating Station conforms to the procurement documents.
2.0 REFERENCE DOCUMENTS i
2.1 10 CFR 50, Appendix B, Criterion VII, Control of Purchased Material, Equipment, and Services 2.2 ANSI N45.2-1971, Section 8, Control of Purchased Material, Equipment, and Services 2.3 Reg. Guide 1.123/ ANSI N45.2.13-76, Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants 3.0 POLICY Measures shall be established to assure that material, I
i equipment and services conform to the specified l
requirements of the related procurement documents.
l l
4.0 GENERAL REOUIREMENTS 1
4.1 Control of purchased material, equipment and services shall include the following, as appropriate:
Source evaluation and selection of suppliers.
a.
b.
Objective evidence of quality furnished by the supplier.
c.
Source inspection, audit, and/or surveillance activities.
d.
Examination of items or services upon delivery or completion.
4.2 Source evaluation and selection of suppliers shall be based on one or more of the following criteria:
i a.
An evaluation of the Supplier's QA Program / Manual / Procedures.
l l
)
I i
i MANUAL:
RANCHO SECO QUALITY MMUAL NUMBER:
RSQM-SECTION VII I
TITLE:
CONTROL OF PURCHASED HATERIAL, REVISION:
6
()
EQUIPMENT AND SERVICES PAGE 3 OF 4 b.
Review and evaluation of historical quality performance data.
c.
Supplier audits by SMUD or by utility groups to which SMUD belongs.
i d.
Utilities holding Nuclear Plant Operating Licenses e.
ASME Manufacturer / Material Supplier Certificate of i
Authorization.
)
i Results of source evaluation shall be documented and retained on file.
Acceptable suppliers shall be listed on SMUD's Approved Supplier List which is controlled by i
6**
Nuclear Quality.
I 4.3 Procedures for control of materials, equipment and services shall address the following:
3 a.
Responsibilities of departments performing supplier technical and quality evaluations, and the method of evaluation.
{
()
b.
Inspection activities that specify the characteristics or processes to be witnessed, inspected or verified; the method of verification and the extent of documentation required; and the 1
organization responsible for implementing the I
inspection.
c.
Auditing to verify conformance and implementation to requirements of this policy.
Source inspection and audits may not be necessary when conformance of an item to procurement requirements'can be' verified by receipt inspection, review of test reports, certified 6**
reports or other means specified by Nuclear Quality.
d.
Receipt inspection of supplier furnished items to assure:
(1) the proper identification of items on the receiving documentation, (2) that the items are inspected and judged acceptable in accordance with predetermined instructions prior to installation or use, (3) that inspection records or certificates of conformance are available at the plant site prior to installation or use of the items, and (4) that items accepted and released are identified as to their inspection status prior to storage or use.
O' e.
Review, acceptance, and maintenance of records to assure adequacy of documentation that identifies the purchased item, and that specific procurement
~, _ -.. -. _.....
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VII j
TITLE:
CONTROL OF PURCHASED MATERIAL, REVISION:
6
()
EOUIPMENT AND SERVICES PAGE 4 OF 4 requirements (e.g., codes, standards, specifications) have been met or satisfied.
j f.
Review and approval of documentation required to be j
submitted by the procurement documents (CMTR's, C of C,
Procedures, Specifications, etc.).
I g.
Procurement control of spare or replacement parts for j
safety-related systems to assure compliance with requirements that are equivalent to the original 1
item, or those specified by a properly reviewed and approved revision to the original requirements.
5.0 RESPONSIBILITIES l
General organizational responsibilities are described in Section I, ORGANIZATION.
l 64~
5.1 Technical Services is responsible to:
I a.
Ensure quality and qualifications of parts and materials by managing definition of quality
()
specifications, and storage in accordance with regulatory requirements, in close cooperation with maintenance and operations.
b.
Ensure regulatory compliance of materials and parts by managing documentation, and review (and implementation as appropriate) of NRC and related parts / materials bulletins.
Examination of items or services upon delivery or c.
completion, as deemed necessary to supplement or replace formal inspection activities.
6-~
5.2 Nuclear Quality is responsible for:
a.
Developing and maintaining an Approved Suppliers List.
b.
Performance of required inspections, evaluations, and audits.
Review and concurrence with material management c.
procedures.
d.
Auditing the Materials Management Program in N
accordance with Section XVIII of this manual.
1
l MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VIII TITLE:
IDENTIFICATION AND CONTROL OF.
REVISION:
6 MATERIALS. PARTS & COMPONENTS PAGE 1 OF 4 LEAD DEPARTMENT:
EFFECITVE DATE:
NUCLEAR OUAT. TTY ASSURANCE 01-11-94 1
q
.I I
REVISION
SUMMARY
i 1.
Updated to reflect the current Rancho Seco organization.
4
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Di'3 PROCEDUEE IS ISSUED POR INFORt1hTION i
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VIII TITLE:
IDENTIFICATION AND CONTROL OF REVISION:
6
(-}
(_j MATERIALS. PARTS & COMPONENTS PAGE 2 OF 4 VIII.
IDENTIFICATION AND CONTROL OF MATERIALS, PARTS E COMPONENTS 1.0 PURPOSE 6-~
This section describes the Quality Assurance Program measures established to provide for the identification and control of material, parts and components for the Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion VIII, Identification and Control of Materials, Parts and Components 2.2 ANSI N45.2-1971, Section 9, Identification and Control of Materials, Parts and Components 3.0 POLICY
(
Procedures shall be established and implemented to assure that materials, parts or components are properly identified and controlled to preclude the use of incorrect or nonconforming items.
4.0 GENERAL REOUIREMENTS 4.1 Materials, parts or components, including partially fabricated subassemblies and consumables, shall be 1
identified such that they can be related to their applicable drawing, specification, purchase document and inspection records at any stage from initial receipt through fabrication / construction, installation, repair, modification or use.
i 4.2 Identification, controls, implementation procedures and documentation shall be used to ensure that only correct and accepted items are used during all stages of construction, installation and operation.
4.3 Unique identification of items is required, e.g.,
by part number, serial number, heat number, drawing identification number or other traceable coding methods.
(
4.4 Identification is required to be maintained either on the item or on records traceable to the item.
Physical identification, such as by marking or tagging, shall be used to the maximum extent practical.
i i
i MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VIII TITLE:
IDENTIFICATION AND CONTROL OF REVISION:
6 O,
MATERIALS, PARTS & COMPONENTS PAGE 3 OF 4 4.5 When specified by codes, standards, procurement documents, or other requirements, identification is req 0 ired such that items are traceable to appropriate documentation (e.g.,
specifications, drawings, purchase orders, manufacturing and inspection documents, nonconformance reports, physical or chemical mill test reports).
4.6 Where identification marking is employed, the marking is required to be clear, unambiguous and indelible, and shall be applied such as not to affect the fit, function or quality of the item.
4.7 Markings shall be transferred to each part of an item, if subdivided. The markings shall not be obliterated or hidden by surface treatment or coatings unless other means of identification are substituted.
4.8 Procedures are required to provide for the verification and documentation of correct identification of items prior to release for use.
Items may be conditionally released under adequate procedural controls.
4.9 Bulk consumables (such'as weld rod, chemicals, reagents, s
gases, resins, lubricating oil and grease, fuel oil, cleaning solvents, etc.) are required to be identified and controlled in accordance with approved procedures that specify the applicable requirements for identification and use of the consumables.
4.10 In the event the identification or traceability of an item is lost, it shall be hanCled in accordance with Section XV of this manual.
5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
6-~
5.1 General Services is responsible for identification and control of items from procurement through withdrawal from the warehouse.
6*~
5.2 Nuclear Maintenance is responsible for maintaining identification and control of items from withdrawal from the warehouse through installation.
O
l MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VIII TITLE:
IDENTIFICATION AND CONTROL OF REVISION:
6 i
O, MATERIALS. PARTS & COMPONENTS PAGE 4 OF 4 i
6-*
5.3 Nuclear Quality is responsible for:
a.
Review and concurrence of procedures for controlling material, parts and components from procurement through storage, issuance and installation, b.
Auditing the process for identification and control of materials, parts and components in accordance with Section XVIII of this manual.
I s
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i 2
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION IX REVISION:
7 O
TITLE:
CONTROL OF SPECIAL PROCESSES PAGE 1 OF 3 LEAD DEPARTMENT:
EFFECTIVE DATE:
NUCLEAR OUALITY ASSURANCE 01-11-94 i
REVISION
SUMMARY
I 1.
Updated to reflect the current Rancho Seco l
organization.
2.
Maintained the requirement to have approved special process procedures before performing special process work while removing the stipulation to have and maintain special process procedures for those special i
processes having no anticipated usage.
3.
Consolidated the responsibility for having NDE' performed.
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'US PROCEDURE IS ISSUED POR INFORt1ATl0N ONLY Af4D j
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION IX O
REVISION:
7 TITLE:
CONTROL OF SPECIAL PROCESSES PAGE 2 OF 3 i
IX.
CONTROL OF SPECIAL PROCESSES 1.0 PURPOSE 7-This section describes the Quality Assurance Program measures established to control special processes used at the Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion IX, Control of Special Processes 2.2 ANSI N45.2-1977, Section 10, Control of Special Processes 2.3 ASME Section V and IX 3.0 POLICY O-*
Prior to performing any special processes, procedures shall be established and implemented to assure that special processes, and equipment are controlled and that the activities are accomplished by qualified personnel and procedures.
4.0 GENERAL REOUIREMENTS 7-*
4.1 Prior to performing any special processes, procedures shall be prepared to provide for proper control of special processes, which include welding, heat treating, chemical cleaning, application of protective coatings and nondestructive examination (NDE).
4.2 controls shall be established to assure that only approved materials and equipment are used to perform special processes.
4.3 Personnel who perform special processes shall be qualified in accordance with industry standards.
4.4 Special process requirements shall be prescribed in the i
controlling specifications, drawings, procurement documents or procedures.
O
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION IX 1
O REVISION:
7 TITLE:
CONTROL OF SPECIAL PROCESSES PAGE 3 OF 3 5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
7*
5.1 Technical Services is responsible for:
a.
Specifying the special processes on design documents governing maintenance / modifications activities.
b.
Developing, qualifying, and maintaining special process procedures in accordance with Para 4.1 of.
this section.
Qualifying personnel or approving contract personnel c.
to perform special processes identified in Para 4.1 of this section.
d.
Performing NDE or approving contract personnel to perform NDE.
5.2 Nuclear Quality is responsible for:
Review and concurrence of special process procedures.
a.
7**
b.
Auditing the special process program in accordance with Section XVIII of this manual.
i O
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION X i
REVISION:
.7 TITLE:
INSPECTION PAGE 1 OF 4 i
LEAD DEPARTMENT:
EFFFLTIVE DATE:
NUCLEAR OUALITY ASSURANCE 01-11-94 l
I REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco l
organization, 2.
Terminology was made consistent within the General l
Requirements and Responsibilities sections by replacing the word " developing" with the words
" preparing or reviewing."
This change did not reduce any requirements.
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION X REVISION:
7
()
I TITLE:
INSPECTION PAGE 2 OF 4 X.
INSPECTION 1.0 PURPOSE 7-*
This section describes the Quality Assurance Program measures established to provide for the inspection of material, parts and components for the Rancho Seco Nuclear l
Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion X, Inspection 2.2 ANSI N45.2-1971, Section 11, Inspection 2.3 Reg Guide 1.58/ ANSI N45.2.6-78, Qualification of Nuclear
.t Power Plant Inspection, Examination and Testing Personnel with exceptions noted in Section II of this manual.
2.4 Safety Guide 33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants 3.0 POLICY Procedures shall be established and implemented to assure that inspections are performed to verify compliance with specified requirements at Rancho Seco.
4.0 GENERAL REOUIREMENTS 4.1 Inspections shall be applied to receiving, maintenance, and modification activities to verify that items and activities conform to specified requirements.
4.2 Inspection planning documents shall be prepared or 7-~
reviewed by Nuclear Quality in accordance with established procedures.
Inspection planning documents shall identify the following as applicable:
a.
Characteristics and activities to be inspected; b.
Inspection organization; c.
Accept / reject criteria; d.
Hold points and/or witness points; e.
Inspection Methods;
i NANUAL:
RANCHO SECO QUALITY MANUAL xNUMBER:
RSQM-SECTION X REVISION:
7 i
()
TITLE:
INSPECTION PAGE 3 OF 4 f.
Provisions for recording objective evidence of inspection results; g.
Measuring and test equipment of the necessary accuracy for performing inspection.
t 4.3 Process monitoring may be used where direct inspection alone is impractical or inadequate.
Both inspection and process monitoring are performed when control is inadequate without both.
l 4.4 Training and qualification of personnel who perform j
inspections, including NDE, shall-be performed in accordance with approved procedures.
t l
4.5 Hold points are designated as mandatory inspection points when confirmation is needed that the work at the point is i
acceptable before additional work can proceed.
Hold point inspections are performed, and work is released for l
l further processing or use, by authorized personnel.
l 4.6 Inspections are performed and documented in accordance with written procedures.
The results are documented and
()
evaluated by qualified personnel in order to verify the
?
i acceptability of the item or work.
i 4.7 Inspections of receiving, maintenance and modification 7**
activities are performed by Nuclear Quality personnel.
4.8 Inspection records shall contain the following where applicable:
a.
Item inspected; b.
The date of the inspection; 1
l c.
Inspector or data recorder identification; d.
Identification of M&TE used to perform inspections; e.
Type of observation; f.
Results or acceptability; i
g.
Reference to information on action taken on nonconformances to resolve any discrepancies noted.
I i
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION X REVISION:
7
()
TITLE:
INSPECTION PAGE 4 OF 4 5.0 RESPONSIBILITIES General organizational responsibilities are described in i
Section I, ORGANIZATION.
7-*
5.1 Nuclear Quality is responsible for:
a.
Qualifying Quality Control Inspectors.
t i
7**
b.
Preparing or reviewing inspection planning documents for modification / maintenance activities, i
c.
Performing inspections per inspection plans.
)
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7-*
5.2 Nuclear Maintenance is responsible for assuring:
i i
a.
Inspections are performed as required by inspection i
planning.
b.
Work does not proceed beyond inspector signoffs for t
hold points.
7**
5.3 Each organization is responsible'for:
l a.
Supporting inspection activities.
b.
Providing prompt corrective action to any deficiencies found during.the inspection.
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XI REVISION:
6 TITLE:
TEST CONTROL PAGE 1 OF 4 LEAD DEPARTMENT:
YE DATE:
NUCLEAR OUALITY ASSURANCE
-4 REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
O)
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Tii:S PROCEDuitE IS ISSUED POR INFOR1 A f10N OriLY AND 1
9 HALL NOT BE USED FGR WORK OR DES!GT
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XI REVISION:
6
()
TITLE:
TEST CONTROL PAGE 2 OF 4 XI.
TEST CONTROL 1.0 PURPOSE 6*
This section describes the Quality Assurance Program measures established to provide for acceptance and surveillance test control at the Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XI, Test Control 2.2 ANSI N45.2-1971, Sect ion 12, Test Control 2.3 Safety Guide 33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants 3.0 POLICY
()
Procedures shall be established and implemented to assure that required testing to demonstrate that structures, systems and components will perform satisfactorily in service is. identified, performed and documented.
l 4.0 GENERAL REOUIREMENTS 4.1 Tests shall be performed in accordance with procedures and criteria that designate when tests are required and how they are to be performed.
Such testing includes the following:
a.
Qualification tests, as applicable, to verify design adequacy.
b.
Tests of equipment and components to assure their j
proper operation prior to delivery or pre-operational tests; c.
Pre-operational tests to assure proper and safe operation of systems and equipment prior to start-up tests or operations; d.
Start-up tests, including precritical, criticality,
('
low-power and power ascension tests performed after fuel loading to assure proper and safe operation of systems and equipment.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XI REVISION:
6 O
TITLE:
TEST CONTROL PAGE 3 OF 4 e.
Surveillance tests to assure continuing proper and safe operation of systems and equipment.
f.
Maintenance tests after preventive or corrective maintenance.
4.2 Test procedures and instructions shall include provisions for the following, as applicable:
a.
The requirements and acceptance limits contained in the applicable design and procurement documents; b.
Test prerequisites such as calibrated instrumentation, required test equipment, degree of completeness of the item to be tested, suitable and controlled environmental conditions and provisions for data collection and storage; c.
Verifying that test prerequisites have been met; d.
Instructions for performing the test; e.
Any inspection points; f.
Acceptance criteria; g.
Documenting or recording test data and results; and h.
Verification of completion.
4.3 Test procedures and instructions shall be reviewed by the applicable organizations for technical content.
4.4 Test results shall be documented and evaluated by responsible authorities to assure that test requirements have been satisfied.
4.5 Test records shall contain the following information where applicable:
a.
Item tested and type of observation; b.
The date and results of the test; c.
Information related to deviations or nonconformances; d.
Identification of person recording the data;
(}
Evidence as to the acceptability of the results; and e.
f.
Action taken to resolve any deviations and nonconformances noted.
- l MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XI REVISION:
6
()
TITLE:
TEST CONTROL PAGE 4 OF 4 5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
1 6**
5.1 Nuclear Quality is responsible for:
a.
Performance of audits to assure conformance to testing requirements applicable to safety-related items per Section.XVIII of this manual.
6**
5.2 Technical Services is responsible for:
i a.
Establishing the procedure for acceptance and surveillance testing.
j b.
Providing personnel to perform'the testing and acceptance evaluations.
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XII TITLE:
CONTROL OF REVISION:
6 MEASURING AND TEST EOUIPMENT PAGE 1 OF 4 LEAD DEPARTMENT:
NUCLEAR OUALITY ASSURANCE REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
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ROCEDURE is Isgy
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RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XII
{
TITLE:
CONTROL OF REVISION:
6
()
MEASURING AND TEST EOUIPMENT PAGE 2 OF 4 XII.
CONTROL OF MEASURING AND TEST EQUIPMENT l
l 1.0 PURPOSE i
I 6-~
This section describes the Quality Assurance Program measures established to provide for the control of measuring and test equipment at the Rancho Seco Nuclear Generating Station.
l 2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XII, Control of Measuring l
and Test Equipment 2.2 ANSI N45.2-1971, Section 13, Control of Measuring and Test Equipment 2,. 3 Safety Guide.33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants.
l 2.4 Reg. Guide 1.30/ ANSI N45.2.4-72, Quality Assurance
()
Requirements for the installation, inspection and Testing of Instrumentation and Electric Equipment with exception noted in Section II of this manual.
3.0 POLICY Procedures shall be established and implemented to assure i
that measuring and testing devices used in final i
acceptance of activities affecting quality are properly controlled, calibrated and adjusted at specified intervals to maintain the desired accuracy.
4.0 GENERAL REOUIREMENTS 4.1 Procedures shall be established for calibration, maintenance and control of measuring and test equipment utilized in the operation, measurement, inspection or monitoring of items.
4.2 Measuring and test equipment shall be uniquely identified and shall be traceable to its calibration test data.
1 4.3 Labels shall be attached to measuring and test' equipment
- O to display the next calibration due date.
Where labels cannot be attached, a control system shall be used that identifies to potential users any equipment which may be beyond the calibration due date.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XII TITLE:
CONTROL OF REVISION:
6 O
MEASURING AND TEST EOUIPMENT PAGE 3 OF 4 4.4 Measuring and test equipment shall be calibrated at specified intervals.
These intervals are based on the amount of use, stability, characteristics and other i
conditions that could adversely affect the required measurement accuracy.
Reference and secondary calibration standards shall be traceable to nationally recognized standards where they exist.
Where national standards do not exist, provisions shall be established to document the basis for calibration.
4.5 M&TE shall'be calibrated from reference standards with an i
accuracy ratio of at least four-to-one (reference standard to M&TE).
Calibration accuracy ratios of less than four but equal to or better than one (Reference standard to M&TE) shall be acceptable when equipment required to meet I
specified requirements is not commercially available.
The basis of acceptance in these cases shall be documented.
i 4.6 M&TE used for calibrating. plant process instrumentation (PI) shall have calibration ranges, precisions, and accuracies such that the PI can be calibrated from M&TE with an accuracy ratio of at least two-to-one (M&TE to PI).
Calibration accuracy ratios of less than two'but O
equal to or better than one shall be acceptable when j
equipment to meet specified requirements is not commercially available.
The basis of acceptance in these cases shall be documented.
4.7 When measuring and testing equipment used for final
)
inspection and test is found to be out of calibration,
-l evaluations shall be conducted to determine the validity i
of the results obtained since the most recent calibration.
The results of evaluations shall be documented.
Retests or reinspections shall be performed on suspect items as necessary.
4.8 Identification of measuring and test equipment used shall be documented and traceable to work performed to allow for corrective measures to be taken when a device is found to be out of calibration.
5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
6**
5.1 Nuclear Maintenance is responsible for-I a.
Establishing methods for control of measuring and test equipment.
i
i i
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XII TITLE:
CONTROL OF REVISION:
6
()
MEASURING AND TEST EOUIPMENT PAGE 4 OF 4 j
b.
Determining the need for calibrated instruments and measuring devices in Rancho Seco activities.
c.
Providing administrative procedures that address the requirements for calibration.
I d.
Control of measurement devices to ensure their use and accuracy.
6--
5.2 Nuclear Quality is responsible for:
a.
Performing audits in accordance with Section XVIII of this manual to assure conformance to the program for control of measuring and test equipment.
I
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1 i
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i i
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XIII-REVISION:-
6 i
TITLE:
HANDLING. STORAGE AND SHIPPING PAGE 1 OF 3 LEAD DEPARTMENT:
NUCLEAR QUALITY ASSURANCE REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XIII REVISION:
6 O
TITLE:
HANDLING. STORAGE AND SHIPPING PAGE 2 OF 3 XIII.
HANDLING, STORAGE AND SHIPPING 1.0 PURPOSE 6-This section describes the Quality Assurance Program measures established to provide for the handling, storage, shipping, cleaning and preservation of material and equipment at the Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XIII,. Handling, Storage and Shipping 2.2 ANSI N45.2-1971, Section 14, Handling, Storage and-Shipping 2.3 Reg Guide 1.38/ ANSI N45.2.2-1972, Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants with exceptions noted in Section II of this manual.
3.0 POLICY l
Procedures shall be established and implemented to assure l
that materials and equipment are properly handled, stored, I
shipped, cleaned and preserved to prevent damage or deterioration.
4.0 GENERAL REOUIREMENTS l
4.1 Procedures shall be established for assuring that proper l
handling, storage, shipping and preservation instructions are included in applicable drawings and/or specifications.
l 4.2 When required for specific items, special protective environments, such as inert gas atmosphere, specific moisture content levels, and temperature levels, shall be specified.
4.3 A shelf-life program shall be in effect and monitored to prevent usage after the expiration date without recertification for extension of shelf-life.
l 4.4 Special material handling and preservation instructions l
shall be developed when required by applicable drawings and/or specifications.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XIII REVISION:
6
()
TITLE:
HANDLING, STORAGE AND SHIPPING PAGE-3 OF 3 4.5 Materials for packaging, shipment, and storage with the potential for causing contamination or' radiation exposure require marking and labeling to indicate the need for special radiological controls.
l 5.0 RESPONSIBILITIES General organizational responsibilities are described in j
Section I, ORGANIZATION.
)
6**
5.1 Technical Services is responsible for:
I a.
Establishing methods and procedures to ensure that applicable drawings and/or' specifications include handling, storage, shipping, and preservation requirements.
6**
5.2 Nuclear Maintenance is responsible for:
1 l
a.
Establishing methods for special handling, storage, and preservation during maintenance activities.
()
b.
Providing administrative procedures which specify the required controls.
64*
5.3 Nuclear Quality is responsible for:
a.
Performing audits in accordance with Section XVIII of this manual to assure conformance to the program for handling, storage, and shipping.
6**
5.4 General Services is responsible for:
Maintaining material control / warehousing control of a.
items and equipment which require special handling and storage.
I O
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XIV TITLE:
INSPECTION, TEST REVISION:
6 AND OPERATING STATUS PAGE 1 OF 3 LEAD DEPARTMENT:
1 NUCLEAR OUALITY ASSURANCE REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
i O
l
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W t>RUCEDURE IS ISSUED POR IfiFORMATIOil OTO Y. '!D 6 ' i NOT BE USED FUR WORK OR DESIGli.
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RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XIV TITLE:
INSPECTION, TEST REVISION:
6 AND OPERATING STATUS PAGE 2 OF 3 4
XIV.
INSPECTION, TEST AND OPERATING STATUS 1.0 PURPOSE 6**
This section describes the Quality Assurance Program measures established to provide for a system to identify the inspection, test and operating status of individual items at the Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XIV, Inspection, Test and i
Operating Status 2.2 ANSI N45.2-1971, Section 15, Inspection, Test and Operating Status 3.0 POLICY j
Procedures shall be established and implemented to' assure j
()
that measures are provided to indicate the status of inspections, tests and operations.
4.0 GENERAL REOUIREMENTS 4.1 Procedures shall be written to control nonconforming material, parts and components to prevent their inadvertent use in plant operations.
4.2 Procedures shall specify the degree of control required for the indication of inspection and test status of items required for modification activities.
4.3 The sequence of inspections, tests, and other operations, and changes thereto shall be controlled by procedures.
4.4 Procedures shall provide methods for identifying the nonconforming items,. inoperable systems and components by tags, markings, labels, etc. to prevent inadvertent use.
O
l RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XIV TITLE:
INSPECTION, TEST REVISION:
6 AND OPERATING STATUS PAGE 3 OF 3 5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
6-*
5.1 Nuclear Operations is responsible for:
1 a.
Clearance procedures to ensure safety of personnel-
[
and equipment during maintenance and testing i
activities.
i b.
Installation and removal of test and operating status I
indicators.
f i
6-*
5.2 Nuclear Quality is responsible for:
a.
Identifying the quality status of material, parts, and components.
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XV TITLE:
NONCONFORMING REVISION:
6 O
MATERIALS. PARTS OR COMPONENTS PAGE 1 OF 4 LEAD DEPARTMENT:
EFFFLTIVE DATE NUCLEAR OUALITY ASSURANCE 10-26-93 REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
1 l
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Tms PROCEDUEE IS ISSUED POR INFORt1ATI j
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XV TITLE:
NONCONFORMING REVISION:
6
()
MATERIALS, PARTS OR COMPONENTS PAGE 2 OF 4 XV.
NONCONFORMING MATERIALS, PARTS OR COMPONENTS 1.0 PURPOSE 6-~
This section describes the Quality Assurance Program measures established for controlling material, components, parts, or systems that are not in conformance to specified requirements at the Rancho Seco Nuclear Generating Station.
1 2.0 REFERENCED DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XV, Nonconforming Materials, Parts or Components 2.2 ANSI N45.2-1971, Section 16, Nonconforming Items 3.0 POLICY t
Procedures shall be established and implemented to assure
()
that materials, parts or components which do not conform to specified requirements are controlled to prevent their inadvertent use or installation.
4.0 GENERAL REOUIREMENTS 4.1 Procedures shall be developed for controlling, documenting, and resolving items, services or activities identified as nonconforming.
4.2 Nonconforming items shall be identified by marking, tagging, segregating, or other means.
4.3 Nonconformances shall be documented, processed, controlled and retained to provide records of the action which was taken to resolve the nonconforming condition.
4.4 Appropriate levels of management will approve the disposition and technical justification of all dispositions.
4.5 The nonconformance program shall receive the attention of management personnel to assure prompt closure of
{
nonconformances in their area of_ responsibility.
O t
4.6 Trending may be used as a mechanism for providing j
management information on programmatic or other significant deficiencies.
'l
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XV TITLE:
NONCONFORMING REVISION:
6 O.
MATERIALS. PARTS OR COMPONENTS PAGE 3 OF 4 4.7 Nonconformances shall be reviewed to determine if they are l
potentially reportable per 10 CFR 21.
i 5.0 RESPONSIBILITIES General _ organizational responsibilities are described in Section I, ORGANIZATION.
l t
6-*
5.1 Nuclear Quality is responsible for:
a.
Providing management repre=entation and expertise on I
the Commitment Management beview Group (CMRG);
I reviewing identified conditions which are. adverse to l
quality and the corrective action associated with.
those conditions.
i b.
Establishing methods for controlling and documenting j
nonconformances.
c.
Ensuring expertise is available to disposition nonconformances.
()
d.
Developing safety analyses that address the l
4 nonconforming condition, if required.
i 6--
5.2 Technical Services is responsible.for:
l a.
Ensuring expertise is available to disposition l
nonconformances.
)
b.
Developing safety analyses that address the nonconforming condition, if required.
c.
Providing management representation and expertise on the Commitment Management Review Group (CMRG);
reviewing identified conditions which are adverse to quality and the corrective action associated with those conditions.
6-*
5.3 Operations is responsible for:
Taking appropriate action'to ensure operation of the a.
plant in conformance to' license requirements when a nonconformance identifies a condition prohibiting components, structures, or systems from returning to an acceptable condition.
O b.
Determining the safety significance of the nonconforming condition on the status of the plant.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XV TITLE:
NONCONFORMING REVISION:
6 i
()
MATERI ALS, PARTS OR COMPONENTS PAGE 4 OF 4 c.
Providing management representation and expertise on the Commitment Management Review Group (CMRG);
reviewing identified conditions which are adverse to quality and the corrective action associated with l
those conditions.
d.
Ensuring expertise is available to disposition nonconformances, j
e.
Developing safety analyses that address the j
nonconforming condition, if required.
6-~
5.4 Radiation Protection and Chemistry is responsible for:-
a.
Ensuring expertise is available to disposition nonconformances.
b.
Developing safety analyses that address the nonconforming condition, if required.
I c.
Providing management representation and expertise'on the Commitment Management Review Group (CMRG);
reviewing identified conditions which are adverse to O
quality and the corrective action associated with j
those conditions.
i 6-*
5.5 Maintenance is responsible for:
a.
Ensuring expertise is available to disposition nonconformances, b.
Developing safety analyses that address the nonconforming condition, if required.
Providing management representation and expertise on c.
the Commitment Management Review Group (CMRG) ;
reviewing identified conditions which are adverse to quality and the corrective action associated with those conditions.
l O
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVI REVISION:
6 TITLE:
CORRECTIVE ACTION PAGE 1 OF 3 LEAD DEPARTMENT:
EFFECTIVE DATE NUCLEAR OUALITY ASSURANCE 10-26-93 REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVI REVISION:
6 O
TITLE:
CORRECTIVE ACTION PAGE 2 OF 3 XVI.
CORRECTIVE ACTION i
1.0 PURPOSE 6-*
This section describes the Quality Assurance Program measures established to provide _for a corrective action i
program to assure that conditions adverse to quality are promptly identified and corrected at the Rancho Seco Nuclear Generating Station.
j 1
l 2.0 REFERENCE DOCUMENTS l
2.1 10 CFR 50, Appendix B, Criterion XVI, Corrective Action 2.2 ANSI N45.2-1971, Section 17, Corrective Action i
3.0 POLICY l
Procedures shall be established and implemented to assure I
that significant conditions adverse to quality are l
O identified and that corrective action is taken to preclude l
repetition.
4.0 GENERAL REOUIREMENTS f
4.1 Controls shall assure conditions adverse to quality such as malfunctions, errors, deficiencies or nonconformances are identified, documented and appropriate corrective action taken.
The controls shall assure that the corrective action is implemented in a " timely manner.
l 4.2 For significant conditions adverse to quality, corrective action includes determining the cause and extent of the condition, taking_ corrective action to remedy the' condition and taking action to prevent recurrence.
These actions shall be reported to management personnel for review and assessment.
J 2
4.3 Conditions adverse to quality are evaluated to determine if they are potentially reportable per 10 CFR 21 or i
H 4.4 Identified conditions adverse to qualitf shall be reviewed by the Commitment Management Review Group (CMRG) for O
severity.
Corrective action for identified conditions shall be reviewed and approved by the CMRG.
1
i MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVI REVISION:
6 i
()
TITLE:
CORRECTIVE ACTION PAGE 3 OF 3 5.0 RESPONSIBILITIES General organizational responsibilities are described in i
Section I, ORGANIZATION.
6-~
5.1 All departments are responsible for:
a.
Formulating appropriate corrective actions as they apply to their departments, b.
Implementing proposed corrective action.
c.
Assuring that proposed corrective action is effective.
6--
5.2 Nuclear Quality is responsible for:
a.
Establishing the corrective action program.
l b.
Performing audits of the Corrective Action Program, as implemented throughout the plant, in accordance with Section XVIII of this manual.
i O
O
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVII REVISION:
6 O
TITLE:
OUALITY ASSURANCE RECORDS PAGE 1 OF 3 LEAD DEPARTMENT:
EFFFLTIVE DATE NUCLEAR OUALITY ASSURANCE 10-26-93 REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVII REVISION:
6 (s}
TITLE:
OUALITY ASSURANCE RECORDS PAGE 2 OF 3 XVII.
QUALITY ASSURANCE RECORDS 1.0 PURPOSE 6-~
This section describes the Quality Assurance Program measures established for the storage and maintenance of Quality Assurance Records which provide the documentary evidence of activities affecting quality performed at Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XVII, Quality Assurance Records 2.2 ANSI N45.2-1971, Section 18, Quality Assurance Records 2.3 Safety Guide 33/ ANSI N18.7, Administrative Control for Nuclear Power Plants, para 5.2 2.4 RGl.28/ ANSI /ASME, NQA-1-1983, Supplement 17S-1,
()
Supplementary Requirements for Quality Assurance Records with exceptions noted in Section II of this manual.
6-*
2.5 Technical Specifications Section D6.0 3.0 POLICY Procedures shall be established and implemented to assure storage and maintenance of records which represent evidence of activities described in Section II, Paragraph 4.2 of this manual.
4.0 GENERAL REOUIREMENTS 4.1 Quality Assurance records shall be permanently stored in a facility that meets the requirements of Ref.
2.4.
4.2 Quality Assurance records shall be protected during interim storage in accordance with Ref.
2.4.
4.3 Documents that furnish evidence of the quality of items and services are generated and controlled in accordance with the procedures that govern those activities.
Such
(^)
documents are considered Quality Assurance Records upon
(_-
completion.
Quality Assurance Records are considered completed when they have been stamped, initialed or signed
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVII REVISION:
6 l
()
TITLE:
OUALITY ASSURANCE RECORDS PAGE 3 OF 3 and dated by authorized personnel or otherwise authenticated.
4.4 The record system shall provide for identification and retrievabilit' of the records to the extent that information can be obtained in a reasonable amount of time.
4.5 The records program shall address records classification (retention period), storage location and responsibility for retention and retrievability.
4.6 A records retention schedule shall be established which addresses the requirements of Ref. 2.4 and 2.5.
5.0 RESPONSIBILITIES General organizational responsibilities are described in l
Section I, ORGANIZATION 6-~
5.1 Records Control is responsible for:
()
a.
Establishing methods for control of records.
b.
Providing administrative procedures which define the records storage program and provide for ready retrievability.
6-5.2 Each department is responsible for:
a.
Transmitting completed records to Records Control.
b.
Providing interim storage in accordance with Section 4.2, prior to transmittal to Records Management.
6-~
5.3 Nuclear Quality is responsible for:
a.
Conducting audits in accordance with Section XVIII of this manual of the records management system to assure conformance to specified requirements.
I 1
l l
O
i MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVIII REVISION:
6 TITLE:
AUDITS PAGE 1 OF 3 LEAD DEPARTMENT:
DATE NUCLEAR OUALITY ASSURANCE REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVIII REVISION:
6
()
TITLE:
AUDITS PAGE 2 OF 3 XVIII.
AUDITS 1.0 PURPOSE 6-*
This section describes the Quality Assurance Program measures established for a comprehensive system of planned and periodic audits to determine the effectiveness of the Quality Program at the Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XVIII, Audits 2.2 Safety Guide 33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants 2.3 Reg. Guide 1.144/ ANSI N45.2.12-1977, Requirements for Auditing of Quality Assurance Programs for Nuclear Power Plants
()
2.4 Reg Guide 1.146/ ANSI N45.2.23-1978, Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants 6--
2.5 Technical Specifications, Section D6.0 3.0 POLICY Procedures shall be established and implemented to assure that planned and periodic audits are conducted to verify compliance with all aspects of the Rancho Seco Quality 6-~
Assurance Program and Technical Specifications.
I 4.0 GENERAL REOUIREMENTS 6-~
4.1 Nuclear Quality shall establish a schedule for auditing the activities affecting quality.
The audit schedule
)
shall be consistent with the Technical Specification 1
requirements at Rancho Seco.
4.2 The audit program shall be described in procedures which implement the requirements of this section.
(
4.3 Audits shall be conducted to determine the adequacy and effectiveness of programs implemented for the design, l
procurement, modification, maintenance and operational activities at Rancho Seco.
i MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVIII REVISION:
6 O
TITLE:
AUDITS PAGE 3 OF 3 4.4 Audit plans shall be developed which identify the audit scope, the requirements, activities to be audited,
)
organizations to be notified, the applicable documents and the audit schedule.
6-*
4.5 Audits shall be performed using approved audit checklists.
4.6 Audit reports shall be issued which identify the activity which was audited, personnel contacted during the audit, and any conditions adverse to quality noted during the audit.
4.7 Identified conditions adverse to quality will be processed using the Rancho Seco Corrective Action Program.
4.8 Personnel conducting audits shall be trained and qualified in accordance with Reference 2.4.
4.9 Regularly scheduled audits shall be supplemented by special audits when conditions which warrant special audits exist or when requested by Management.
()
5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
6-*
5.1 Nuclear Quality is responsible for:
a.
Establishing a schedule for performance of required audits.
)
i b.
Reviewing audit results to evaluate the effectiveness of the Quality Program.
c.
Implementation of the established audit program.
d.
Training and qualification of audit personnel, e.
Preparation of trend analysis data.
6-~
5.2 Each department is responsible for:
a.
Supporting the audit activities, b.
Providing prompt response to any deviations from quality identified in the audit.
O RANCHO SECO QUALITY MANUAL l
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CONTROL DATE:
01/17/94 NUCLEAR 00E R A T I NG RE E ORDS M AN AGE ME N1 SYSTEM PROGRAM NAME: VPO506GP CONTROL TIME:
11: 29 OPERATING RECORD 5 TABLE OF CONTENTS PAGE:
1 FOR: L51 URGE - STURGEON, LOR]
DOCUMENT TYPEt R50M
- RANCHO SECO QUALITY MANUAL DOCUMENT ID REV STAT CHANGE NO EFF DATE EMP DATE SUBJECT R50M-OAP 5
A 10/23/91 OUALITY AS5URANCE POLICY R50M-I 7
A 8/03/92 ORGANIZATION R50M-II 6
A 8/03/92 OUALITY ASSURANCE PROGRAM R50M-111 6
A 12/16/93 DESIGN CONTROL R50M-IV 6
A 10/26/93 PROCUREMENT DOCUMENT CONTROL A50M-V 6
A 1/11/94 INSTRUCTION
S. PROCEDURE
S AND DRAWINGS R504-VI 6
A 10/26/93 DOCUMENT CONTROL R50M-VII 6
A 1/1 194 CONTROL OF PURCHASED MATERIAL. EQUIPMENT AND SERVICES R50M-vill 6
A 1/11/94 IDENT]FICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS R50M-IA 7
A 1/11/94 CONTROL OF SPECIAL PROCESSES R50M-x 7
A 1/11/94 INSPECTION R50M-x1 6
A 1/11/94 TEST CONTROL R50M-X11 6
A 1/11/94 CONTROL OF MEASURING AND TEST EQUIPMENT R50M-M11]
6 A
1/11/94 HANDLING, STORAGE AND SHIPP]NG R50M-XIV 6
A 1/11/94 INSPECTION. TEST AND OPERATING STATUS R50M-XV 6
A 10/26/93 NONCONFORMING MATERIALS, PARTS OR COMPONENT $
R50M-XVI E.
A 10/26/93 CORRECTIVE ACTION R$0M-XV11 6
A 10/26/93 OUALITY ASSURANCE RECORDS R50M-XVIII 6
A 10/26/93 AUDITS TOTAL NUMBEP OF RECORD 5:
19 i
l NUMBER:
RSQM - POLICY O
RANCHO SECO QUALITY MANUAL REVISION: 5 i
- PAGE 1 0F 2 i
LEAD DEPARTHENT:
EEFECTlyE DATE NUCLEAR OUALITY ASSURANCE 10-23-91 j
l REVISION
SUMMARY
1.
Updated to reflect current organizational titles, responsibilities and requirements.
j 2.
c.larified Policy Statements II and III to be consistent with
- tements made in Section II of RSQM regarding the
. j app
' ability of and responsibility for the Quality Asst J ae Program.
]
1 3.
Added "k( ision Summary" page to this and all other sections i
of this Manual.
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SW,LL NOT BE USED FOR wuRK 09 DESIGH.
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NUMBER:
RSQM - POLICY
(
RANCHO SECO QUALITY MANUAL REVISION:
5 PAGE 2 0F 2 QUALITY ASSURANCE POLICY 5--
The Sacramento Municipal Utility District's (SMUD) policy regarding Nuclear Quality Assurance is as follows:
I.
Organizations involved in safety related activities shall be structured, managed, and operated to provide compliance with this manual.
Procedures and instructions shall be prepared to implement the activities required to provide direct support of the operation of Rancho Seco Nuclear Generating Station to achieve the following objectives:
a.
To comply with government regulations and established SMUD management policies and procedures, applying a systematic, disciplined and uniform approach to Quality Assurance.
b.
To perform assigned work correctly the first time.
c.
To provide facilities which are designed, modified, constructed, tested and operated in accordance with specified requirements, with assurance against failure or malfunctions, ard without endue risks to the health and safety of the public.
d.
To ensure prompt identification and resolution of actual and
{x potential problem areas in design, procurement, construction, s
testing, operations, maintenance and modification of safety related systems, structures and components.
5-II.
The Rancho Seco Quality Assurance Program applies to activities, plans and programs affecting the operation and the quality of structures, systems, components, and services.
This Program will be implemented by organizations responsible for achieving and verifying quality.
III. The Deputy Assistant General Manager, Nuclear has delegated the i
responsibility and authority for development and execution of the Rancho Seco Quality Assurance Program to Manager, Quality Assurance. Any conflicts or questions involving interpretation of the requirements or resulting from the implementation of the Quality Assurance Program must be referred to the Manager, Nuclear Quality Assurance for resolution.
4 Paul BenYer JffShetier
- Manager, Deputy Nuclear Quality Assurance Assistant General Manager, Nuclear m
N
.i NUMBER:
RSQM - TOC RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 1 0F 2 LEAD DEPARTMENT:
((F{gTfyEDATE NUCLEAR OUALITY ASSURANCE REVISION
SUMMARY
t 1.
Deleted columns for " Latest Revision" and "Date of Revision." This control is provided through Nuclear Operating Records Management System via the Procedures Control gret.p in Administrative Services who maintain this status information.
2.
Added " Revision Summary" page to this and all other sections of this Manual.
I O
THI'i P'GCEDURE IS ISSUED POR INFORMATION ONLY AND R
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rw NUMBER:
RSQM - TOC
('j RANCHO SEC0 QUALITY HANUAL REVISION:
6 PAGE 2 0F 2 RANCHO SECO QUALITY MANUAL TABLE OF CONTENTS SECTION i
NO.
TITLE 6-Quality Assurance Policy i
I Organization II Quality Assurance Program III Design Control j
IV Procurement Document Control V
Instructions, Procedures and Drawings VI Document Control VII Control of Purchased Material, Equipment and Services O
VIII Identification and Control of Materials, Parts and Components IX Control of Special Processes X
Inspection XI Test Control XII Control of Measuring and Test Equipment i
XIII Handling, Storage and Shipping XIV Inspection, Test and Operating Status XV Nonconforming Materials, Parts or Components j
XVI Corrective Action XVII Quality Assurance Records XVIII Audits O
V
i
[
NUMBER:
RSQM - SECTION I
\\
RANCHO SECO QUALITY MANUAL REVISION:
7 PAGE 1 0F 5 LEAD DEPARTMENT:
EFFECTIVE DATE:
NUCLEAR OUALITY ASSURANCE 08-03-92 k
REVISION
SUMMARY
The following revisions were made to make the RSQM-Section I consistent with the Defueled Technical Specifications (License Amendment No.119).
1.
Added General Manager responsibility statement.
(Para 4.1) l 3.
Revised MSRC and PRC reporting chain.
(Paras 4.S and 4.6) 4.
Revised MSRC review and audit activities.
(Para 4.6) i O
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RSQM-SECTION I l
RANCHO SECO QUALITY MANUAL-REVISION:
7 PAGE 2 0F 5 I.
ORGANIZATION j
1.0 PURPOSE 4
I This section describes the Sacramento Municipal Utility District (SMUD) organizations and personnel responsible.for establishing, implementing, r
and verifying the Quality Assurance Program at Rancho Seco Nuclear Generating Station.
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2.0 REEERENCE DOCUMENTS 2.1 10CFR50, Appendix'B, Criterion I, Organization l
2.2 ANSI N45.2-1971, Section 2, Organization 2.3 Safety Guide 33/ ANSI N18.7, Administrative Controls for Nuclear Power-Plants j
i 2.4 Rancho Seco Technical Specifications, Section 6.0 l
O 3.0 EQLLC1 3.1 The establishment and implementation of the Rancho Seco Quality.
Assurance Program shall be the responsibility of SMUD.
Portions of the Quality Assurance Program functions may be delegated to'other SMUD approved external organizations, but overall responsibility for the i
program is retained and exercised'by SMUD.
i 3.2 Definitive lines of authority, responsibility'and communication shall be established for those organizations involved in the Rancho Seco Quality Assurance Program.
3.3 Quality Assurance personnel assigned to Rancho Seco have defined responsibilities and organizational freedom to identify problems that affect quality; to initiate, recommend, or provide solutions; and to verify implementation of solutions.
They have the_ authority to initiate.
i action to stop unsatisfactory work pending implementation of necessary corrective action to bring the unsatisfactory conditions into-conformance.
3.4 The organizational structure and functional responsibility assignments shall be such that attainment of program objectives is accomplished by individuals or groups who inspect, examine, audit or otherwise verify f^
conformance to established requirements, and'who are independent of the-individuals or groups who performed the original activity.
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RSQM-SECTION I RANCHO SECO QUALITY MANUAL REVISION:
7 PAGE 3 0F 5 4.0 ORGANIZATION AND RESPONSIBILITIES 7+
4.1 The General Manager (GM) through the Assistant General Manager (AGM) and Chief Operations Officer shall have corporate responsibility for overall safe operation of the facility and i
shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the facility to ensure NUCLEAR SAFETY.
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4.2 The Deputy Assistant General Manager, Nuclear reports directly to the Assistant General Manager (AGM) and Chief Operations Officer of the Sacramento Municipal Utility District.
The Deputy AGM, Nuclear assures that Rancho Seco is properly staffed and adequately budgeted to safely carry out its responsibilities.
He assures the staff responds to the recommendations of the Management Safety Review Committee (MSRC) and coordinates concerns relating to nuclear safety with the Manager, Nuclear Quality Assurance.
The Deputy Assistant General Manager, Nuclear is responsible for the safe and reliable decommissioning of Rancho Seco and reports O
to the AGM and Chief Operations Officer.
The Deputy AGM has the d
responsibility and authority for development and execution of the Rancho Seco Quality Assurance Program and ensures optimum quality performance of Rancho Seco.
In fulfilling this commitment, the Deputy AGM shall conduct a final review of Rancho Seco Quality Manual revisions and shall provide signature approval upon concurrence.
The Deputy AGM has delegated authority and responsibility for development and execution of the Quality Assurance Program to the Manager, Nuclear Quality Assurance.
The Deputy AGM, Nuclear is responsible for the administrative actions necessary to assure that the Rancho Seco Quality Assurance Program is implemented by the organizations under his direction. To this extent, the Deputy AGM shall maintain a continuing involvement in quality matters and shall assess the scope, status, implementation and effectiveness of the Quality Assurance Program through Quality Status Reports, Trend Analyses, Quality Audits or Surveillances and Management Safety Review Committee (MSRC) meeting minutes.
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RSQM-SECTION I RANCHO SECO QUALITY MANUAL REVISION: 7 PAGE 4 0F 5 4.3 The Manager, Nuclear Quality Assurance reports directly to the Deputy AGM, Nuclear, is independent from the pressures of other lines of authority, and ensures that an active Quality Assurance Program is implemented at Rancho Seco in accordance with regulatory requirements.
The Manager, Nuclear Quality Assurance shall have sufficient authority and organizational freedom to identify problems that j
affect quality, recommend solutions, and verify implementation of 1
solutions as appropriate.
Commensurate with this responsibility is the authority to initiate action to stop unsatisfactory work and control further processing, delivery, installation, construction or modification or nonconforming items, or i
continuation of nonconforminc services / operations, pending correction of the unsatisfactory condition.
4.4 Corporate and on-site organizational responsibilities are described in greater detail in Rancho Seco Administrative Procedures.
Specific duties and responsibilities for l
organizations whose activities affect quality are described in Sections II through XVIII of this manual.
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4.5 The Plant Review Committee (PRC) advises the Deputy AGM, Nuclear and the Management Safety Review Committee (MSRC) on all matters related to nuclear safety.
The Committee composition, j
responsibility and authority, subjects to be reviewed, and reporting requirements are addressed in Section 6.0 of the Rancho Seco Technical Specifications and the PRC Procedure.
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4.6 The Management Safety Review Committee (MSRC) advises the AGM and Chief Operations Officer on facility operations.
Composition,
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responsibility and authority of the MSRC as well as the subjects to be reviewed, administrative controls, and reporting requirements are addressed in Section 6 of the Rancho Seco Technical Specifications and the MSRC Procedure.
The MSRC also functions to provide for an independent review and i
audit of designated activities in areas of:
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a.
Facility Operation b.
Engineering and Nuclear Engineering c.
Chemistry and P,adlochemistry d.
Radiological Safety
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e.
Quality Assurance Practices O
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RSQM-SECTION I
'- /
RANCHO SECO QUALITY MANUAL REVISION:
7 PAGE 5 0F 5 4.7 The Commitment Management Review Group (CMRG) is the senior management group responsible for reviewing all Potential Deviations from Quality (PDQ) to determine if a condition requires determination of the cause, extent, remedial corrective action and action to prevent recurrence.
The CMRG reviews and approves Deviation from Quality (DQ) dispositions and assigns action for implementation.
The CMRG also determines whether a PDQ is potentially reportable under 10 CFR 21.
5.0 GENERAL RESPOMSIBILIILES Each organization involved in the design, operation, maintenance and modification of Rancho Seco is responsible for describing and clearly defining the duties and authority of individuals whose work affects quality.
Each organization has the responsibility to ensure that their procedures implement the Rancho Seco Quality Assurance Program requirements.
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NUMBER:
RSQM - SECTION II RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 10F 15 LEAD DEPARTMENT:
EFFECTIVE DATE:
NUCLEAR 00ALITY ASSURANCE 08-03-92 REVISION
SUMMARY
1.
Updated References cited on Attachment II-1 to agree with Defueled Technical Specifications.
(License Amendment No. 119)
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RSQM-SECTION II RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 2 OF 15 II.
QUALITY ASSURANCE PROGRAM 1.O PJJRE0SE The purpose of this section is to describe the Quality Assurance Program which shall be implemented at Rancho Seco Nuclear Generating Station.
2.0 REEERENCES 2.1 10 CFR 50, Appendix B, Criterion II, Quality Assurance Program 2.2 ANSI N45.2-1971, Section 3, Quality Assurance Program 2.3 Safety Guide 33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants 2.4 10 CFR 71, Subpart H, Quality Assurance Requirements for Packaging and Transportation of Radioactive Material 3.0 POLICY The Quality Program described herein is designed to assure compliance with the requirements of 10 CFR 50, Appendix B,
" Quality Assurance Criteria for Nuclear Power Plants and fuel Reprocessing Plants," including the requirements of applicable NRC Regulatory Guides, and ANSI Standards.
4.0 GENERAL REQUIREMENTS 4.1 This Quality Manual is organized to present the Rancho Seco Quality Assurance Program in the order of the 18 criteria of 10 CFR 50 Appendix B.
The manual states the Rancho Seco policy for each of the criteria and describes how the controls pertinent to each are to be carried out. Any changes made to this manual that do not reduce the commitments previously accepted by the Nuclear Regulatory Commission (NRC) shall be submitted to the NRC at least annually. Any changes made to this manual that reduce the commitments previously accepted by the.NRC will be submitted to the NRC and shall receive NRC approval prior to implementation.
The submittal of the changes described above will be made in accordance with the requirements of 10 CFR 50.54(a).
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RSQM-SECTION II RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 3 0F 15 4.2 The Rancho Seco Quality Assurance Program is impiemented by organizations responsible for achieving quality and by organizations responsible for verifying quality.
The Manager, Nuclear Technical Services is responsible to develop a Master Equipment list (MEL).
The MEL is a list of equipment that have been assigned an equipment ID.
The MEL provides a ready reference for design and procurement information for each listed equipment. Q-List is a subset of the MEL, that includes all equipment that have been assigned QA Class 1 or identified as requiring Environmental Qualification.
The MEL is revised as a result of design changes.
4.3 The Quality Assurance Program applies to activities affecting the operation and the quality of safety related structures, systems, components, and services during plant operation, maintenance, testing and modifications.
Appropriate elements of this manual apply to emergency plans, radiation protection procedures, radioactive waste shipment programs, fire protection, effluent control and environmental
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monitoring as indicated in Attachment II-1.
4.3.1 1-1 illustrates minimal regulatory and licensing requirements; implementing procedures shall meet or exceed these requirements.
4.4 The programmatic Regulatory Guides and ANSI Standards, and the applicable revisions, to which SMUD commits with regard to quality assurance matters and an appropriate explanation of interpretations and exceptions are tabulated in Attachment 11-2 and II-3 of this section.
4.5 The extent to which the Quality Assurance Program and its controls are applied are established as follows:
a.
SMUD uses the criteria specified in Technical Services Procedures for identifying structures, systems and components to which the Quality Assurance Program applies; b.
This identification process results in a MEL which identifies safety-related items.
The MEL is a controlled document.
Safety-related items are determined by engineering analysis of the function (s) of plant structures, systems and components in relation to safe operation and shutdown;
.sh c.
The controls specified in the Quality Assurance Program described in this manual are applied to safety-related items.
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RSQM-SECTION II RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 4 0F 15 4.6 Safety-related activities are accomplished under controlled conditions.
Preparations for such activities include confirmation that prerequisites have been met.
4.7 Development, control, and use of computer programs affecting nuclear power plant safety-related design and operation are subject to appropriate controls.
4.8 Training and indoctrination programs shall be es'ablished to assure that personnel responsible for performing and verifying activities that affect quality have the required proficiency and qualifications to perform the assigned tasks.
4.9 Quality Assurance Program:
Policy / Procedures / Instructions a.
The Quality Assurance Program is documented by written Rancho Seco policies, procedures, and instructions.
The overall policies and general requirements are outlined in the Rancho Seco Quality Manual (RSOM).
Specific details related to implementation of the established quality l
l policies are contained in the Rancho Seco Administrative
' (O Procedures (RSAP).
Additional implementing procedures shall d
be prepared as required by the organizations responsible for performing the function.
The quality organization reviews such procedures to assure that quality-related functions are accomplished in a controlled manner, with specified equipment, under suitable environmental conditions, and that prerequisites have been satisfied prior to inspection or testing.
b.
The Manager, Nuclear Quality Assurance is responsible for the preparation, issuance, and control of the Rancho Seco Quality Manual.
j c.
Proposed changes to the Quality Manual shall be reviewed and approved by the Manager, Nuclear Quality Assurance and the AGM, Nuclear.
Requests to revise any portion of this manual shall be submitted in writing to the Manager, Nuclear Quality Assurance.
d.
The Rancho Seco Quality Manual, including any changes, supplements, or attachments, is issued and maintained as a controlled document.
e.
Rancho Seco Quality Manuals are assigned by the Manager, Nuclear Quality Assurance to managers of departments.
All changes will be distributed to the assignees and they will be responsible for inserting the revisions in their manuals.
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NUMBER:
RSQM-SECTION II RANCHO SECO QUALITY MANUAL REVISION:
6 i
PAGE 5 0F 15 l
4.10 Resolution of Differences l
l The provisions. delineated in the Rancho Seco Quality Manual shall
.j take precedence over differing quality requirements specified in:
other departmental procedures until the Manager, Nuclear Quality i
Assurance has evaluated the issue and determined which requirement (s) are to be-modified.
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Questions on disputes involving interpretation of the l
requirements or implementation of this manual must be referred.to i
the Manager, Nuclear Quality Assurance for resolution and/or-initiating changes to commitments or procedures as necessary to j
resolve the differences.
4.11 Packaging and Transportation'of Radioactive Material.
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This Quality' Assurance Program shall be applied to packaging and i
transportation of radioactive material as spe.cified in Ref. 2.4.
i 5.0 '
RESPONSIBILITIES l
l General organizational responsibilities are described.in Section I, ORGANIZATION.
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6.0 ATTACHMENTS l
II-1, Application of Rancho Seco Quality Program Criteria-II-2, Regulatory Commitments II-3, Exceptions O
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NUMBER:
RSQM-SECTION II RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 6 0F 15 ATTACHMENT II-1 6+
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NUMBER:
RSQM-SECTION 11 RANCHO SECO QUALITY MANUAL REVISION: 6 PAGE 7 0F 15 l
ATTACHMENT II-2 REGULATORY COMMITMENTS j
SMUD commits to the requirements of the regulations and industry. standards listed below with any exceptions identified in Attachment'II-3.
DOCUMENT REVISION /DATE TITLE i
- 1. Reg. Guide 1.8 Personnel Selection and Training 1
- As referenced.in the Tech. Spec.
j
- 2. Safety-Guide'28 6/7/72 Quality Assurance Requirements ANSI N45.2 71 for Nuclear Power Plants
- 3. Reg. Guide 1.28 8/85 Supplementary Requirements for ANSI /ASME NQA-1 83 Quality Assurance Records (See Supplement 175-1 exception No. 1.in Attachment II-3) i
- 4. Safety Guide 30 8/11/72 Quality Assurance Requirements-O ANSI N45.2.4 72 for the Installation, Inspection, and
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Testing of Instrumentation and Electrical Equipment (See exception No. 2 in-I Attachment II-3)
- 5. Safety Guide 33 Administrative Controls for Nuclear Power Plants
- As referenced in the Tech. Spec.
- 6. Reg. Guide 1.37 3/16/73 Quality Assurance Requirements for ANSI N45.2.1 73 Cleaning Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants (See exception No. 3 in Attachment II-3)
't
- 7. Reg. Guide 1.38 3/16/73 Quality Assurance Requirements for ANSI N45.2.2 72 Packaging, Shipping Receiving, Storage and Handling of Items for Water-Cooled Nuclear Power Plants (See exception No. 8 in Attachment II-3)
- 8. Reg. Guide 1.39 3/16/73 Housekeeping Requirements'for Water-ANSI N45.2.3 73 Cooled Nuclear Power Plants (See exception No. 4 in Attachment II-3) 1 O
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RSQM-SECTION II RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 8 0F 15 ATTACHMENT II-2 (Continued) l 5
t REGULATORY COMMITMENTS DOCUMENT REVISION /DATE TITLE'
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- 9. Reg. Guide 1.54 6/73 Quality Assurance Requirements for ANSI N101.4 72 Protective Coatings Applied to' Nuclear Facilities
- 10. Reg. Guide 1.58 9/80 Qualification of Nuclear Power Plant'-
l ANSI N45.2.6 78 Inspection, Examination, and Testing Personnel (See exception No. 5 in Attachment II-3) j i
- 11. Reg. Guide 1.64 10/73 Quality Assurance Requirements'for the ANSI N45.2.11 74 Design of Nuclear Power Plants (See exception No. 6 in Attachment II-3) i
- 12. Reg. Guide 1.74 2/74 Quality Assurance Terms and Definitions
-j ANSI N45.2.10 73 (See exception.No. 7'in Attachment II-3)-
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- 13. Reg. Guide 1.94 2
Quality Assurance Requirements for ANSI N45.2.5 78 Installation, Inspection, and Testing of Structural Concrete and Structural Steel I
During the Construction Phase of Nuclear Power Plants
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- 14. Reg. Guide 1.116 6/76 Quality Assurance Requirements for ANSI N45.2.8 75 Installation, Inspection, and Testing of Mechanical Equipment and Systems
- 15. Reg. Guide 1.120 11/77 Fire Protection Guidelines for Nuclear Power Plants
- 16. Reg. Guide 1.123 7/77 Quality Assurance Requirements for ANSI N45.2.13 76 Control of Procurement Items and Services for Nuclear Power Plants
- 17. Reg. Guide 1.144 1/79 Auditing of Quality Assurance Programs ANSI N45.2.12 77 for Nuclear Power Plants
- 18. Reg. Guide 1.146 8/80 Qualification of Quality Assurance Program ANSI N45.2.23 78 Audit Personnel for Nuclear Power Plants
- 19. Reg. Guide 4.15 2/79 Quality Assurance for Radiological 1
Monitoring Programs
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RSQM-SECTION II RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 9 0F 15 ATTACHMENT II-3 EXCEPTIONS l
i EXCEPTION NO. 1:
Reg. Guide 1.28/NQA-1, Supplement 17S-1 i
i SMUD complies with the recommendations of this regulatory guide with the following clarifications:
With regard to Section 2.4 of Supplement 175-1 titled Index: The phrase l
"an index" is clarified to mean a collection of documents or indices which, when taken together, supply the information attributed to "an j
index" in the standard.
6 The specific location of a record "within a storage area"'may not be delineated (e.g. The specific location within a. computer record file may not be constant.
Further, SMUD may utilize a computer. assisted. random access filing system where such location could not be readily
" documented," or would such a location be " relevant.")
The storage location will be delineated, but where file. locations change with time, j
O the specific location of a record within that file may not always be i
documented.
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With regard to Section 4.3, Sup>'ement 175-1 titled Safekeeoina:
Routine general office and nucl ar site security systems and access controls are provided:
No special security systems are required to be established for record storage areas.
With regard to Section 4.4, Supplement 17S-1, titled Facility:
This Section provides no distinction between temporary and permanent facilities.
To cover temporary storage, the following clarification is added:
" Records completed but not yet transferred for permanent storage may be temporarily stored in one-hour fire rated file cabinets.
In general, records shall not be maintained in such temporary storage for more than four months after completion without being microfilmed or placed in permanent storage. Open-ended documents revised or updated on a more-or-less continuing basis over an extended period of time (e.g.
personnel qualification and training documents, equipment history cards)
~
which are cumulative in nature (e.g. nonconforming item logs and control room log books) shall become QA records when they are issued as a specific revision (e.g. the master audit schedule);'when they are filled-up or discontinued (e.g log books or equipment history cards); on a predefined periodic basis when the completed portion of the on-going document shall be transferred to records control as a " record" (e.g.
training and qualification records).
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RSQM-SECTION II RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 10 0F 15 ATTACHMENT II-3 (Continued)
EXCEPTIONS EXCEPTION NO. 2:
REG. GUIDE 1.30/ ANSI N45.2.4-72 4
Specific clarifications for ANSI N45.2.4 - 1972 are indicated below by sections.
Section 1.4 Definitions in this standard which are not included in ANSI N45.2.10 shall be used; all definitions which are included in ANSI N45.2.10 shall be used as clarified in SMUD commitment to Regulatory Guide 1.74.
l Section 2.1 P_lannina requirements, as determined by engineering, shall be incorporated into modification procedures.
Section 2.3 Procedures and Instructions shall be' implemented as. set forth in Sections II, III, V, X and XI of this program and by compliance with the Rancho Seco Plant Technical
. Specifications and Regulatory Guide 1.33 (ANSI N18.7).
l Section 2.4 Results will.be implemented as set forth in Sections X, XI, and XVII of this program and by compliance with ANSI N18.7 in lieu of the requirements set forth here.
Section 2.5.2 Calibration and Control covers three classes of instrumentation used by SMUD:
(1) M&TE (portable measuring instruments, test equipment, tools, gages, and non-destructive test equipment used in measuring and inspecting safety-related structures, systems, and components); (2) reference standards (primary, secondary, transfer, and working); and (3) permanently installed process instrumentation (PI).
Hith respect to the first sentence, M&TE and reference standards shall be included in calibration program and shall either be calibrated at prescribed intervals or shall be calibrated prior to use.
Hith respect to the last sentence, personnel shall be trained and procedures shall require that the calibration sticker shall be'
)
reviewed to determine calibration status prior to use:
This label shall be considered to clearly identify equipment which is out of calibration.
Lack of a sticker shall require record review and affixing a new sticker based on calibration data.
M&TE and reference standards O
shall comply with sentences 2, 3 and 4.
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RSQM-SECTION II RANCHO SECO QUALITY MANUAL REVISION: '6 PAGE 11 0F 15 ATTACHMENT II-3 (Continued) i EXCEPTIONS EXCEPTION NO. 2:
REG. GUIDE 1.30/ ANSI N45.2.4-73 (Continued)
With respect.to.the third sentence, SMUD uniquely identifies each safety-related component of permanently i
installed process instrumentation.
This identification provides traceability to calibration data. 'These actions are SMUD's alternative to the tagging or labeling of items to indicate the calibration date and the identity of the person who performed the calibration.
Permanently installed process instrumentation shall comply with sentences 1, 2, and 5.
Section 3 Preconstruction Verification will be implemented as follows:
(1) is required only for modifications, (2) no i
special checks are required to be made by the person withdrawing a replacement part from the warehouse -
i equivalent controls are assured by compliance.with i
Regulatory Guide 1.38 (ANSI N45.2.2) as set forth in this table, and, (3) shall be complied with as determined by engineering, by individual technicians as part of the modification process.
Section 5.1 Insoections, including subsections 5.1.1, 5.1.2, and 5.1.3, will be implemented as set forth in Section X of this program.
The inspection program will incorporate, l
as determined by engineering and Quality those' items l
listed in these subsections.
Section 5.2 Tests, including subsections 5.2.1 through 5.2.3, will be implemented as set forth in Sections III and XI of this program.
In some cases Surveillance testing may be used to meet the appropriate requirements of this section.
Section 6 Post-Construction Verification is not generally considered applicable at operating facilities because of the scope of the work and the relatively short interval between installation'and operation.
Where considered necessary by engineering and Quality, the elements described in this Section will be used in the development and implementation of inspection and testing programs as l
describe in Sections III, X, and XI of this program.
Section 7 Data Analysis and Evaluation will be implemented as stated herein after adding the clarifying phrase "Where.
used" at the beginning of that paragraph.
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RSQM-SECTION II RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 12 0F 15 ATTACHMENT II-3 (Continued)
EXCEPTIONS i
EXCEPTION NO. 3:
REG. GUIDE 1.37/ ANSI N45.2.1-73 Specific clarifications for this Regulatory Guide and ANSI N45.2.1 -
l 1973 are indicated below:
l Hith~ regard to Paragraph C.3 of Regulatory Guide 1.37:
The water quality for final flushing of fluid systems and associated' components l
shall be at least equivalent to the quality of the operating system water, except for the oxygen and nitrogen content; but this.does'not i
infer that chromates or other additives, normally in the system water, will be added to the flush water.
With regard to Paragraph C.4 of Regulatory Guide 1.37:
Expendable i
materials, such.as inks and related products; temperature indicating-sticks; tapes; gummed-labels; wrapping materials (other than polyethylene); water soluble dam materials; lubricants; NDT penetrant O
materials and couplants, desiccants, which contact stainless steel or-nickel' alloy surfaces shall not contain lead, zinc, copper, mercury,-
~
cadmium and other low melting points metals, their alloys or~ compounds as basic and essential chemical constituents.
no more than 0.1 percent (1,000 ppm) halogens will be allowed where such elements are leachable i
or where they could be released by breakdown of the compounds under expected environmental conditions.
With regard to Section 5 of ANSI N45.2.1 - 1973 titled Installation Cleanina:
The recommendation that local rusting on corrosion resistant alloys be removed by mechanical methods is interpreted to mean that.
local rusting may be removed mechanically, but the use of other removal
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means is not precluded, as determined by engineering or. Chemistry.
EXCEPTION NO. 4:
REG. GUIDE 1 3Sl ANSI N45.2.3-73 Specific classifications for ANSI N45.2.3 - 73 are indicated for specific sections below.
i Section 1.4 Definitions:
Definitions in this Standard which are not 1
included in Regulatory Guide 1.74 (ANSI N45.2.10) will be used:
all definitions which are included in ANSI N45.2.10 will be used as clarified in SMUD's commitment to Regulatory Guide 1.74.
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6 PAGE 13 0F 15 l
ATTACHMENT II-3 (Continued)
EXCEPTIONS EXCEPTION NO. 4:
REG. GUIDE 1.39/ ANSI N45.2.3-73 (Continued)
Section 2.1 Plannina: SMUD may choose not to utilize the five-level
. zone designation system, but will utilize standard janitorial and work practices to maintain a level of cleanliness commensurate with program requirements in the areas of housekeeping, plant and personnel safety,'and fire protection.
Cleanliness will be maintained, consistent with the work being performed, so as to prevent the entry.of foreign material into safety-related systems.
This'will include, as a minimum, documented cleanliness inspections which will be performed prior to system closure. As necessary,.
(e.g. the opening is larger than the tools being used) control of personnel, tools. equipment, and supplies will O
be established ~when the reactor system is opened for inspection, maintenance, modification or repair.
Additional housekeeping requirements will be implemented as required for control of radioactive contamination.
Section 2.2 Procedures and Instructions:
Appropriate procedures will be written and implemented.
)
Section 3.2 Control of Facilities:
SMUD may choose not to utilize the five-level zone designation system, but will utilize standard janitorial and work practices to maintain a level of cleanliness commensurate with program requirements in the areas of housekeeping, plant and personnel safety, and fire protection.
Cleanliness will be maintained, consistent with the work being performed, so as to prevent the entry of foreign material into safety-related systems.
This will include,_
as a minimum, documented cleanliness inspections which will be performed prior to system closure. As necessary, (e.g. the opening is larger than the tools being used) control of personnel, tools, equipment, and supplies will be established when the reactor system is opened'for J
inspection, maintenance, modification or repair.
Additional housekeeping requirements will be implemented as required for control of radioactive contamination.
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RSOM-SECTION II l
RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 14 0F 15-l ATTACHMENT II-3 (Continued)
EXCEPTIONS NCEPTION NO. 5:
REG. GUIDE 1.58/ ANSI N45.2.6
.i UD complies with the recommendation of the regulatory guide with the i
following clarification.
' tith regard to Paragraph C.5:
The ' Level III function of inspection alanning,. reviewing and concurring with inspection, examination and testing procedures is performed by designated individuals from_the l
Quality & Industrial Safety Department.
EXCEPTION NO. 6:
REG. GUIDE 1.64/ ANSI N45.2.11 SMUD complies with the recommendation of th'e regulatory guide with the following clarification:
)
Hith regard to Paragraph C.2:
In exceptional circumstances, the i
O designer's immediate supervisor can perform design verification, provided:
l 1.
The supervisor is the only technically qualified' individual i
available.
2.
The need is individually documented and approved in advance by'the j
supervisor's management.
3.
QA audits cover frequency and effectiveness of use of supervisors as design verifters to guard against abuse.
EXCEPTION NO. 7:
REG. GUIDE 1.74/ ANSI N45.2.10-73 SMUD complies with the recommendations of this regulatory guide with the following clarifications.
SMUD reserves _the right to define additional words or phrases which are not included in this Standard, Such additional definitions will be documented in appropriate procedures.
In addition to the Standard's definition of " Inspection," SMUD will use the following:
" Inspection (when used to refer to activities that are NOT performed by QC personnel) - Examining, viewing closely, scrutinizing, looking over or otherwise checking activities.
Personnel performing these functions are not necessarily certified to Regulatory O
Guide 1.58 (ANSI N45.2.6)."
i i
l NUMBER:
RSQM-SECTION II RANCHO SECO QUALITY MANUAL REVISION:
6 PAGE 15 0F 15 ATTACHMENT II-3 (Continued)
EXCEPTIONS I
EXCEPTION NO. 7 (Continued)
When SMUD intends for Inspection to be performed in accordance with the QA Program by personnel certified as required by that program and for activities defined by " inspection" in ANSI N45.2.10, appropriate references to the plant QC organization or the procedures to be used for performing the activity will be made.
If such references are NOT made, inspections are to be considered under the additional definition given l
above.
" Independent Verification": - Verification by an indiviaual other than the person who performed the operation or activity being verified that j
required actions have been completed. Such verification may not i
necessarily require confirmation of the action at tiie physical location if adequate remote indication of completion of action is available.
In determining the acceptability of remote verification, the consequences O
of the action not being 100% completed and the validity of the remote indication for confirming the completion of the desired action will be i
considered.
Examples include, but are not limited to: Verification of-a breaker opening by observed remote breaker indication lights; verification of a set point (made with a voltmeter or ammeter for example) by observing the actuation of status or indicating lights at the required panel-meter indicated value; verification that a valve hr.s been positioned by observing the starting or stopping of flow on meter indicaticns or by remote valve positions indicating lights.
"Will" - (Not defined in any ANSI Standard) - Means the same as "shall" except when used to denote simple futurity.
When used to denote futurity, "will" is normally followed by "be".
EXCEPTION NO. 8:
REG. GUIDE 1.38/ ANSI N45.2.2 Section 2.7 Classification of Items - SMUD may choose not to utilize j
the four level classification of items, but will address 1
packaging and storage requirements for items based on the needs of individual items and manufacturers recommendation.
O
(
I l
d 9
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION III i
REVISION:
6 i
TITLE:
DESIGN CONTROL PAGE 1 OF 5 l
4 LEAD DEPARTMENT:
EFFFLTIVE DATE:
t NUCLEAR OUALITY ASSURANCE 12-16-93 i
i t
REVISION
SUMMARY
i i
1.
Updated to reflect the current Rancho Seco l
organization.
l 2.
Removed references to the training simulator, j
technical support for the training simulator and environmental qualification.
i l
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i i
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g T e*G PROCEDURE IS ISSUED POR INFOR11AT10N ONLY AND l
4-t a,mm<! ALL N'2T SE USED FOR WORK OF DistGH.
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION III O
REVISION:
6 J
I IJTLE:
DESIGN CONTROL PAGE 2 OF 5 III.
DESIGN CONTROL 5
t 1.0 PURPOSE 6**
This section describes the Quality Assurance Program f
measures established for control of design activities affecting structures, systems and components at the Rancho Seco Nuclear Generating Station.
In addition, this section also defines the requirements for the development and implementation of control measures to assure that design functions affecting performance of operational, construction and modification activities are carried out in a planned, controlled, and orderly manner and are in compliance with applicable regulatory j
commitments.
2.0 REFERENCES
2.1 10 CFR 50, Appendix B, Section III, " Design Control" i
- 0. 4-d 2.2 10 CFR 50.59, " Changes, Tests and Experiments"
+
2.3 Reg Guide 1.64/ ANSI N45.2.11, 1974, " Quality Assurance Requirements for the Design of Nuclear Power Plants", with exceptions noted in Section II of this manual.
2.4 ANSI N45.2, Section 4,
" Design Control" 3.0 POLICY The requirements specified in this section apply to all organizations performing design functions for i
modifications, changes, replacement or addition of structures, systems or components at Rancho Seco.
4.0 GENERAL REOUIREMENTS Procedures shall be established and executed to control design activities.
Procedures covering design control activities shall include the following requirements:
4.1 Applicable design inputs such as design bases, regulatory requirements, codes and standards, methodology and all O.
assumptions with appropriate justifications are identified, documented and correctly translated into design output documents such as specifications, drawings, procedures or instructions.
n MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION III
()
REVISION:
6 TITLE:
DESIGN CONTROL PAGE 3 OF 5 4.2 Exceptions, waivers to or deviations from engineering requirements are documented and controlled.
4.3 Methods are specified for the selection and classification of suitable materials, parts, equipment, and processes used in meeting applicable requirements for structures, systems and components.
Materials, parts, components and equipment which are 6-*
standard, commercial (off-the-shelf), or whic~.. have been previously approved for other similar applications are reviewed for suitability and appropriately classified.
4.4 Systematic methods are established for communicating and controlling the flow of related design information across the external and internal design interfaces, including any changes to the design information as the work progresses.
6**
4.5 Interfaces between Technical Services and other participating design organizations (either internal or external to SMUD) are identified and documented.
This identification includes those organizations providing
('>')
design inputs, design analyses, design specifications, and
(
design verification for operational, construction and modification design activities.
4.6 Participating design organizations establish and describe the controlled methods for preparation, review, approval, release, distribution, and revision of documents (such as design analyses, specifications, drawings, reports) involving design interfaces.
4.7 Verifying or checking the adequacy of design for modifications or changes performed.
Acceptable verification methods include, but are not limited to design reviews, alternate calculations or qualification testing.
If a test program is used to verify the adequacy of a design, it must include qualification testing of a prototype unit under the most adverse design conditions.
4.8 Computer program codes used for design calculations are certified for use and their use is specified.
4.9 Design verification is performed by competent individuals or groups other than those who performed the original design but who may be from the same organization.
This verification may be performed by the originator's Os supervisor provided the supervisor is the only technically qualified individual available and meets the appropriate clarification provisions of Ref.
2.4.
The results of the design verification efforts must be documented with the identification of the verifier clearly provided.
1 l
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION III O
REVISION:
6 TITLE:
DESIGN CONTROL PAGE 4 OF 5 4.10 Provisions are specified for the control of design analyses such as reactor physics, stress, thermal, f
hydraulic, and accident; compatibility of materials; accessibility for inservice inspection, maintenance, and repair; and delineation of acceptance criteria for inspections and tests.
4.11 Design problems which are identified during field installation or testing activities shall be documented and 6*~
forwarded to Technical Services for evaluation and resolution.
4.12 Design and specification changes, including field changes, receive the same degree of control and approval as the original design unless another qualified, responsible organization is specifically designated.
4.13 Errors and deficiencies in the design process, including computer programs, that could adversely affect structures, systems or components are documented and corrective action is taken to preclude repetition.
O Proposed modifications or design changes which involve an 4.14 unreviewed safety question or a change to the Rancho Seco l
Technical Specifications are handled in accordance with the requirements of 10 CFR 50.59.
l t
4.15 Modifications are reviewed by plant personnel for effect on plant operation prior to making the modification operational.
4.16 Design documents are reviewed for accessibility of equipment and components for inservice. inspection, tests, maintenance or modifications.
4.17 Design and/or test documentation must be obtained from all suppliers on procurements of ASME code components used for replacement or modification to Rancho Seco.
5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
6-*
5.1 Technical Services is responsible for implementing a design control process per this section and to:
()
Provide and control design change packages.
a.
b.
Optimize nuclear fuel value and reactor safety by managing fuels management and core analysis.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION III (s.
REVISION:
6 TITLE:
DESIGN CONTROL PAGE 5 OF 5 c.
Ensure integrity and regulatory conformance of configuration control.
d.
Provide plant configuration control including establishing and maintaining baseline documents.
e.
Provide computer engineering support for plant 6-~
computers, IDADs, etc.
f.
Perform probabilistic analysis in support of plant design.
6-g.
Provide engineering support to the Rancho Seco nuclear organization, j
I h.
Provide and maintain engineering procedures, standards and specifications and drawings.
6**
i.
Prepare and maintain the Master Equipment List described in Section II.
6-*
5.2 Nuclear Quality is responsible for:
0)
Review and concurrence of design control procedures.
(_,
a.
b.
Monitoring implementation of the Design Control 1
Program.
Auditing the Design Control Program per Section XVIII c.
of this manual.
l
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION IV REVISION:
6 l
TITLE:
PROCUREMENT DOCUMENT CONTROL PAGE 1 OF 5-LEAD DEPARTMENT:
g g gjE DATE NUCLEAR OUALITY ASSURANCE REVISION
SUMMARY
t 1.
Updated to reflect the current Rancho Seco i
organization.
I t
i f
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.,,,.......n_
jh T ' NOCEDURE IS ISSUED POR INFORt1 AT10N ONLY AND l
l I
9 EUA NOT BE USED FOR WORX OR DESIGN.
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION IV
-' ()
REVISION:. 6 TITLE:
PROCUREMENT DOCUMENT CONTROL PAGE 2 OF 5 l
IV.
PROCUREMENT DOCUMENT CONTROL i
1.0 PURPOSE 6~~
This section describes the Quality Assurance Program measures established to control procurement documents for a
j material, equipment and services at the Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS f
2.1 10 CFR 50, Appendix B, Criterion IV, Procurement Document I
i Control 2.2 ANSI N45.2-1971, Section 5, Procurement Document Control i
2.3 Reg Guide 1.123/ ANSI N45.2.13-1976, Quality-Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants 3.0 POLICY Procurement documents for Rancho Seco materials, equipment, components / spares or services shall include applicable technical requirements, quality requirements, regulatory requirements and other provisions necessary to assure that purchased items and services are adequately described to the supplier.
4.0 GENERAL REOUIREMENTS 4.1 Procedures shall be established and implemented to control the preparation, review, approval and issuance of procurement documents.
4.2 Procurement documents shall include provisions for the following, as applicable:
a.
Description of item or service, b.
Identification of design specifications and technical requirements by reference to specific drawings, codes, regulations, industry standards or other documentation, including the applicable revision O
thereto, that describe the items or services to be furnished.
i MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION IV O
REVISION:
6 TITLI:
PROCUREMENT DOCUMENT CONTROL PAGE 3 OF 5 c.
Identification of test, inspection and acceptance requirements, and any special instructions and requirements for activities such as design, fabrication, identification, cleaning, erecting, packaging, handling, shipping and extended storage.
d.
Identification of applicable QA Program criteria.
i e.
Applicability of 10 CFR 21.
i f.
Identification of the documentation, such as-drawings, specifications, procedures, fabrication and inspection plans, inspection and test records, personnel and procedure qualifications, and chemical and physical test reports to be prepared and maintained by the supplier or contractor, and requirements for submittal to SMUD for review and approval.
g.
Identification of those records to be retained, i
controlled and maintaine'd by the supplier'or contractor and those to be delivered to SMUD at the
(
time of shipment of the procured item.
h.
SMUD's right of access to the supplier's facilities and records for inspection and audits.
i.
Extension of applicable requirements to lower tier subcontractors and suppliers, including SMUD's right of access to facilities and records.
j.
Supplier submittal of nonconforming items and SMUD approval for " Accept-as-is" or "R,epair" dispositions l
of nonconformances.
k.
SMUD's right to hold shipment if procurement document requirements, including those for documentation, have not been fulfilled.
4.3 Technical and quality review by qualified personnel and approval by designated individuals shall be performed prior to issuance of the procurement document.
The review and approval shall be documented and available for l
verification.
4.4 Review and concurrence by Quality shall be performed to assure adequacy of quality requirements and to verify that O
the requirements are correctly stated, inspectable and controllable; that there are adequate acceptance and rejection criteria; that the procurement documents have l
been prepared, reviewed and approved in accordance with j
the requirements of the established procedures.
i
---a
I l
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION IV l
O-REVISION:
6 i
TITLE:
PROCUREMENT DOCUMENT CONTROL PAGE 4 OF 5 4.5 Materials Group shall verify that the supplier is on the i
Approved Suppliers List ( ASL).
i i
4.6 Revisions to procurement documents shall receive an i
equivalent review and approval as the original documents.
Exceptions to this include changes in quantity, estimated-price, cost codes, taxes, format or editorial changes that i
do not affect the quality of the item or service.
l 4.7 Procurement documents for spare or replacement parts for safety-related structures or systems shall specify procurement controls at least equivalent to those required for purchase of the original equipment.
4.8 Methods shall be established to assure that the items received are traceable to procurement documents.
5.0 RESPONSIBILITIES General organizational responsibilities are described'in Section I, ORGANIZATION.
5.1 General Services is responsible to:
i Purchase items in conformance with procurement a.
documents.
b.
Purchase safety-related items from approved suppliers.
Arrange for suppliers to be placed on the Approved c.
Suppliers List.
{
\\
d.
Arrange for source inspection when specified on the i
6*
5.2 Technical Services is responsible to:
Maintain a staff of qualified Engineers who provide a.
technical and quality requirements for purchasing safety-related items.
5.3 Nuclear Quality is responsible for:
~
Review and concurrence of material management a.
procedures.
b.
Review and concurrence of procurement documents for safety-related items.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION IV
(,
REVISION:
6 TITLE:
PROCUREMENT DOCUMENT CONTROL PAGE 5 OF 5 c.
Auditing the procurement program per Section XVIII of i
this manual.
i d.
Developing and maintaining an Approved Suppliers List.
I 1
1 I
O I
l O
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION V TITLE:
INSTRUCTIONS, REVISION:
6 PROCEDURES & DRAWINGS PAGE 1 OF 3 LEAD DEPARTMENT:
EFFFLTIVE DATE:
NUCLEAR OUALITY ASSURANCE 01-11-94 REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
}
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__,,,_j T
' CEDURE IS ISSt!ED FOR INFORt1AT10N ONLY M D i
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M'
- f.!T 9E i:SE! F OR y/0.W OR DESIGN.
- c. n.
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i i
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION V O
TITLE:
INSTRUCTIONS,
' REVISION:
6 PROCEDURES & DRAWINGS PAGE 2 OF 3 V.
INSTRUCTIONS, PROCEDURES AND DRAWINGS 1.0 PURPOSE 6**
This section describes the Quality Assurance Program measures established to assure that all the activities affecting the quality or' safety of the Rancho Seco Nuclear Generating Station are described and accomplished.in accordance with documented instructions, procedures, drawings or other documents appropriate to the circumstances.
2.0 REFERENCE DOCUMENTS i
2.1 10 CFR 50, Appendix B, Criterion V, Instructions, l
Procedures and Drawings 2.2 ANSI N45.2-1971, Section 6, Instructions,-Procedures.and Drawings 2.3 Safety Guide 33/ ANSI N18.7, Administrative Controls'for O
Nuclear Power Plants i
3.0 POLICY
'l Activities affecting the operational safety or quality performance at Rancho Seco shall be described by and implemented in accordance with documented instructions, procedures, and drawings.
j 4.0 GENERAL REOUIREMENTS 4.1 Written instructions, procedures, drawings, or other documents appropriate to the circumstances sha31 be prepared to provide measures for complying-with the provisions of the Rancho Seco Quality Program.
4.2 Instructions, procedures, or drawings shall include applicable quantitative and/or qualitative acceptance-criteria for verifying that the activities have been satisfactorily accomplished.
4.3 The responsible organizations shall establish procedures which define responsibilities and delineate the sequence O
of actions to be accomplished in the preparation, review, approval and control of instructions, procedures, or drawings, and changes thereto.
i 4
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION V
()
TITLE:
INSTRUCTIONS, REVISION:
6 PROCEDURES & DRAWINGS PAGE 3 OF 3 J
4.4 Activities affecting quality shall be accomplished in i
accordance with approved instructions, procedures, and drawings.
5.0 RESPONSIBILITIES 6
General organizational responsibilities are described in Section I, ORGANIZATION.
6*
5.1 Each department is responsible for assuring that activities affecting quality performed by their departments are described in instructions, procedures and J
drawings.
5.2 Nuclear Quality is responsible for performing audits to
~
verify that any activities affecting quality are described in instructions, p ocedures and drawings.
Audits shall be conducted in ac drdance with Section XVIII of this manual.
O
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VI O'
REVISION:
6 TITLE:
DOCUMENT CONTROL PAGE 1 OF 3 LEAD DEPARTMENT:
tynX, IVE DATE T
NUCLEAR OUALITY ASSURANCE 10-26-93 REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
,n,~....~..m..__
.. ~,,, _ _
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' '"'flCEDURE IS ISSUED FOR IkFORP1AT!ON ONLY AND l
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s
1 MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VI TITLE:
DOCUMENT CONTROL REVISION:
6 PAGE 2 OF 3 VI.
DOCUMENT CONTROL 1.0 PURPOSE 6-~
This section describes the Quality Assurance Program i
measures established for the issuance and control of Rancho Seco Nuclear Generating Station. documents
.0
._ REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B,-Criterion VI, Document Control 2.2 ANSI N45.2-1971, Section 7, Document Control
\\
2.3 ANSI N45.2.11-1974, Section 7, Document Control 3.0 POLICY Applicable documents, including changes thereto, Rancho Seco shall be issued and controlled in a
()
that i
t that precludes the.use of inappropriate or outdated -
documents.
i 4.0 GENERAL REOUIREMENTS 4.1 Procedures shall be established for the review
- issuance, requirements such as instructions, change and use of docu
- approval, and other documents which implement the quality assurance procedures, drawings program.
4.2 Procedures which establish document control measu include:
a.
Identification of documents to be controlled; b.
Identification of individuals or organizations responsible for the review, approval, issuance and revision of documents; Criteria to ensure that adequate technical and c.
quality requirements are incorporated prior to implementation; i
_ _ _.. ~..
_ _ _. _ _ ~,. _ _ _ _._ _
i i
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VI f
(
REVISION:
6 TITLE:
DOCUMENT CONTROL PAGE 3 OF 3 d.
Review of changes to documents by the same organizations that performed the initial review and approval or by the organizations designated in accordance with the applicable procedures.
4.3 Controlled documents, including changes, shall be issued and distributed to organizations noted on distribution lists so that proper and current documents are available as required, and obsolete or superseded documents are identified and not used for prescribed activities.
4.4 Master lists or equivalent means shall be used to identify the current revision of controlled documents, and shall be made available at work locations as appropriate.
5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
6-5.1 Document Control is responsible for developing and
/'
implementing a document control program in accordance with this section.
5.2 Each department is responsible for:
a.
Defining document review, approval and revision j
authority in department procedures.
b.
Providing for a review of documents for concurrence with quality assurance-related aspects by Nuclear Quality as appropriate.
5.3 Nuclear Quality is responsible for:
a.
Review and concurrence of document control procedures.
b.
Review and concur with procedures, instructions or documents that implement the Quality Assurance-Program to assure compliance with the applicable provisions of this manual.
c.
Auditing the document control program per Section XVIII of this manual.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VII TITLE:
CONTROL OF PURCHASED MATERIAL, REVISION:
6 EOUIPMENT AND SERVICES PAGE 1 OF 4 LEAD DEPARTMENT:
EFFECTIVE DATE:
NUCLEAR OUALITY ASSURANCE 01-11-94 l
REVISION
SUMMARY
I l
1.
Updated to reflect the current Rancho Seco l
organization.
l l
l l
l l
6 s
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s, m,,
w Ti ' ' ROCEDURE iS ISSL; D FOR IS'FOT !1 AT!GN C a:LV AND
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l MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VII O
TITLE:
CONTROL OF PURCHASED MATERIAL, REVISION:
6 EOUIPMENT AND SERVICES PAGE 2 OF 4 I
VII.
CONTROL OF PURCHAEOD MATERIAL, EQUIPMENT AND SERVICES 1.0 PURPOSE 6**
This section describes the Quality Program measures i
established to-assure that material, equipment and l
services purchased for the Rancho Seco Nuclear Generating Station conforms to the procurement documents.
j 4
2.O REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion VII, Control of Purchased Material, Equipment, and Services 2.2 ANSI N45.2-1971, Section 8, Control of Purchased Material, I
Equipment, and Services 2.3 Reg. Guide 1.123/ ANSI N45.2.13-76, Quality' Assurance Requirements for Control of Procurement of' Items and l
Services for Nuclear Power Plants O
i 3.0 POLICY j
Measures shall be established to assure that material, equipment and services conform to the specified requirements of the related procurement documents.
i 4.0 GENERAL REOUIREMENTS 4.1 Control of purchased material, equipment and services shall include the following, as appropriate:
a.
Source evaluation and selection of suppliers.
b.
Objective evidence of quality furnished by the supplier.
c.
Source inspection, audit, and/or surveillance activities.
d.
Examination of items or services upon delivery or completion.
O Source evaluation and selection of suppliers shall be 4.2 based on one or more of the following criteria:
a.
An evaluation.of the Supplier's QA Program / Manual / Procedures.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VII
(
TITLE:
CONTROL OF PURCHASED MATERIAL, REVISION:
6
\\
EOUIPMENT AND SERVICES PAGE 3 OF 4 b.
Review and evaluation of historical quality performance data, c.
Supplier audits by SMUD or by utility groups to which SMUD belongs.
d.
Utilities holding Nuclear Plant Operating Licenses e.
ASME Manufacturer / Material Supplier Certificate of Authorization.
Results of source evaluation shall be documented and retained on file.
Acceptable suppliers shall be listed on SMUD's Approved Supplier List which is controlled by 6*~
Nuclear Quality.
4.3 Procedures for control of materials, equipment and services shall address the following:
Responsibilities of departments performing supplier a.
technical and quality evaluations, and the method of evaluation.
()
b.
Inspection activities that specify the characteristics or processes to be witnessed, inspected or verified; the method of verification and the extent of documentation required; and the organization responsible for implementing the inspection.
c.
Auditing to verify conformance and implementation to requirements of this policy.
Source inspection and audits may not be necessary when conformance of an item to procurement requirements *can be verified by receipt inspection, review of test reports, certified 64*
reports or other means specified by Nuclear Quality.
d.
Receipt inspection of supplier furnished items to assure:
(1) the proper identification of items on the receiving documentation, (2) that the items are inspected and judged acceptable in accordance with predetermined instructions prior to installation or use, (3) that inspection records or certificates of conformance are available at the plant site prior to installation or use of the items, and (4) that items accepted and released are identified as to their inspection status prior to storage or use.
Os e.
Review, acceptance, and maintenance of records to assure adequacy of documentation that identifies the purchased item, and that specific procurement
1 MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VII j
TITLE:
CONTROL OF PURCHASED MATERIAL, REVISION:
6 3
EOUIPMLSI_AND SERVICES PAGE 4 OF 4 requirements (e.g., codes, standards, specifications) have been met or satisfied.-
f.
Review and approval of documentation required-to be s
submitted by the procurement documents (CMTR's, C of C,
Procedures, Specifications, etc.).
I g.
Procurement control of spare or replacement parts for safety-related systems.to assure compliance with requirements that are equivalent to the original i
item, or those specified by a properly reviewed and approved revision to the original requirements.
5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
6*~
5.1 Technical Services is responsible to:
a.
Ensure quality and qualifications of parts and O
materials by managing definition of_ quality specifications, and storage in accordance with regulatory requirements, in close cooperation with maintenance and operations.
b.
Ensure regulatory compliance of materials and parts by managing documentation, and review (and implementation as appropriate) of NRC and related parts / materials bulletins.
c.
Examination of items or services upon delivery or completion, as deemed necessary.to supplement or replace formal inspection activities.
6**
5.2 Nuclear Quality is responsible for:
a.
Developing and maintaining an Approved Suppliers List.
b.
Performance of required inspections, evaluations, and audits.
c.
Review and concurrence with material management procedures.
O Auditing the Materials Management Program in d.
accordance with Section XVIII of this manual.
i MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VIII TITLE:
IDENTIFICATION AND CONTROL OF REVISION:
6 MATERIALS. PARTS & COMPONENTS PAGE 1 OF 4 LEAD DEPARTMENT:
EFFECTIVE DATE:
NUCLEAR OUALITY ASSURANCE 01-11-94 REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
O
,7_~ _1"' 90CEDURE IS ISSUED FG!? INFOT'H tT'OP CWL'! AMD
- l
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VIII O
TITLE:
IDENTIFICATION AND CONTROL OF REVISION:
6 MATERIALS. PARTS & COMPONENTS PAGE 2 OF 4 i
i VIII.
IDENTIFICATION AND CONTROL OF MATERIALS, PARTS &
COMPONENTS 1.0 PURPOSE 6-~
This section describes the Quality Assurance Program measures established to provide for the identification and control of material, parts and components for the Rancho 1
Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion VIII, Identification and Control of Materials, Parts and Components 2.2 ANSI N45.2-1971, Section 9, Identification and Control of Materials, Parts and Components 3.0 POLICY i
Procedures shall be established and implemented to assure that materials, parts or components are properly identified and controlled to preclude the use of incorrect or nonconforming items.
4.0 GENERAL REOUIREMENTS 4.1 Materials, parts or components, including partially fabricated subassemblies and consumables, shall be identified such that they can be related to their applicable drawing, specification, purchase document and inspection records at any stage from initial receipt j
through fabrication / construction, installation, repair, modification or use.
4.2 Identification, controls, implementation procedures and documentation shall be used to ensure that only correct
{
and accepted items are used during all stages of construction, installation and operation.
4.3 Unique identification of items is required, e.g.,
by part number, serial number, heat number, drawing identification number or other traceable coding methods.
()
4.4 Identification is required to be maintained either on the item or on records traceable to the item.
Physical identification, such as by marking or tagging, shall be used to the maximum extent practical.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VIII l
O TITLE:
IDENTIFICATION AND CONTROL OF REVISION:
6 i
MATERIALS, PARTS & COMPONENTS PAGE 3 OF 4 i
4.5 When specified by codes, standards, procurement documents, or other requirements, identification is required such that items are traceable to appropriate documentation (e.g.,
specifications, drawings, purchase orders, r
manufacturing and inspection documents, nonconformance reports, physical or chemical mill test reports).
4.6 Where identification marking is employed, the marking is required to be clear, unambiguous and indelible, and shall be applied such as not to affect the fit, function or quality of the item.
4.7 Markings shall be transferred to each part of an-item, if subdivided. The markings shall not be obliterated or i
hidden by surface treatment or coatings unless other means of identification are substituted.
4.8 Procedures are required to provide for the verification and documentation of correct identification of items prior to release for use.
Items may be conditionally released under adequate procedural controls.
4.9 Bulk consumables (such as weld rod, chemicals, reagents, O
gases, resins, lubricating oil and-grease, fuel oil, cleaning solvents, etc.) are requirrid to be identified and controlled in accordance with apprc;ed procedures that specify the applicable requirements fe,7 identification and use of the consumables.
i 4.10 In the event the identification or traceability of an item is lost, it shall be handled in accordance with Section XV i
of this manual.
l 5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
6**
5.1 General Services is responsible for identification and control of items from procurement through withdrawal from' the warehouse.
6-*
5.2 Nuclear Maintenance is responsible for maintaining.
identification and control of items from withdrawal from the warehouse through installation.
O
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION VIII
()
TITLE:
IDENTIFICATION AND CONTROL OF REVISION:
6 MATERIALS. PARTS & COMPONENTS PAGE 4 OF 4 6-~
5.3 Nuclear Quality is responsible for:
a.
Review and concurrence of procedures for controlling material, parts and components from procurement through storage, issuance and installation.
b.
Auditing the process for identification and control of materials, parts and components in accordance with Sec, tion XVIII of this manual.
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1 1
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION IX REVISION:
7 l
TITLE:
CONTROL OF SPECIAL PROCESSES PAGE 1 OF 3 LEAD DEPARTMENT:
EFFFLTIVE DATE:
NUCLEAR OUALITY ASSURANCE 01-11_-94 i
REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
i 2.
Maintained the requirement to have approved special process procedures before performing special process work while removing the stipulation to have and maintain special process-procedures for those special processes having no anticipated usage.
3.
Consolidated the responsibility for having NDE performed.
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1 THIS PROCEDURE IS ISSUED POR INFORMATION ONLY [..ND
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SC.Lt. NOT BE USED FOR WORX OR DECIGri i
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION IX O
REVISION:
7 TITLE:
CONTROL OF SPECIAL PROCESSES PAGE 2 OF 3 IX.
CONTROL OF SPECIAL PROCESSES 1.0 PURPOSE 7*
This section describes the Quality Assurance Program measures established to control special processes used at the Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion IX, Control of Special Processes 2.2 ANSI N45.2-1977, Section 10, Control of Special Processes 2.3 ASME Section V and IX 3.0 POLICY
/~7-*
Prior to performing any special processes, procedures shall be established and implemented to assure that special processes, and equipment are controlled and that the activit ies are accomplished by qualified personnel and procedures.
4.0 GENERAL REOUIREMENTS
]
7**
4.1 Prior to performing any special processes, procedures shall be prepared to provide for proper control of special processes, which include welding, heat treating, chemical cleaning, application of protective coatings and nondestructive examination (NDE).
4.2 Controls shall be established to assure that only approved materials and equipment are used to perform special processes.
4.3 Personnel who perform special processes shall be qualified in accordance with industry standards.
4.4 Special process requirements shall be prescribed in the controlling specifications, drawings, procurement documents or procedures.
O
s MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION IX REVISION:
7 TITLE:
CONTROL OF SPECIAL PROCESSES PAGE 3 OF 3 5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
7-5.1 Technical Services is responsible for:
a.
Specifying the special processes on design documents governing maintenance / modifications activities.
b.
Developing, qualifying, and maintaining special process procedures in accordance with Para 4.1 of this section.
c.
Qualifying personnel or approving contract personnel to perform special processes identified in Para 4.1 of this section.
d.
Performing NDE or approving contract personnel to perform NDE.
5.2 Nuclear Quality is responsible for:
Review and concurrence of special process procedures.
a.
7-*
b.
Auditing the special process program in accordance with Section XVIII of this manual.
i l
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION X REVISION:
7 1
TITLE:
INSPECTION PAGE 1 OF 4 LEAD DEPARTMENT:
EFFECI'IVE DATE:
NUCLEAR OUALITY ASSURANCE 01-11-94 REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
i 2.
Terminology was made consistent within the General Requirements and Responsibilities sections by replacing the word " developing" with the words
" preparing or reviewing."
This change did not reduce any requirements.
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION X O
REVISION:
7 TITLE:
INSPECTION PAGE 2 OF 4 X.
INSPECTION 1.0 PURPOSE 7-~
This section describes the Quality Assurance Program measures established to provide for the inspection of material, parts and components for the Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion X, Inspection 2.2 ANSI N45.2-1971, Section 11, Inspection l
2.3 Reg Guide 1.58/ ANSI N45.2.6-78, Qualification of Nuclear Power Plant Inspection, Examination and Testing Personnel with exceptions noted in Section II of this manual.
2.4 Safety Guide 33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants O
3.0 POLICY i
Procedures shall be established and implemented to assure that inspections are performed to verify compliance with i
specified requirements at Rancho Seco.
4.0 GENERAL REOUIREMENTS 4.1 Inspections shall be applied to receiving, maintenance, and modification activities to verify that items and activities conform to specified requirements.
4.2 Inspection planning documents shall be prepared or 7*~
reviewed by Nuclear Quality in accordance with established procedures.
Inspection planning documents shall identify the following as applicable:
Characteristics and activities to be inspected; a.
b.
Inspection organization; c.
Accept / reject criteria; d.
Hold points and/or witness points; e.
Inspection Methods;
i 1
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION X O
REVISION:
7 TITLE:
INSPECTION PAGE 3 OF 4 f.
Provisions for recording objective evidence of inspection results; g.
Measuring and test equipment of the necessary accuracy for performing inspection.
4.3 Process monitoring may be used where direct i spection.
i alone is impractical or inadequate.
Both inspection and process monitoring are performed when control'is 1
inadequate without both.
4.4 Training and qualification of personnel who perform inspections, including NDE, shall be performed in accordance with approved procedures.
4.5 Hold points are designated as mandatory inspection points when confirmation is needed that the work at the point is acceptable before additional work can proceed.
Hold point inspections are performed, and work is released for further processing or use, by authorized personnel.
4.6 Inspections are performed and documented in accordance_
O with written procedures.
The results are documented and evaluated by qualified personnel in order to verify the acceptability of the item or work.
4.7 Inspections of receiving, maintenance and modification 7*~
activities are performed by Nuclear Quality personnel.
j 4.8 Inspection records shall contain the following where i
applicable:
i a.
Item inspected; b.
The date of the inspection; c.
Inspector or data recorder identification; d.
Identification of M&TE used to perform inspections; e.
Type of observation; f.
Results or acceptability; g.
Reference to information on action taken on nonconformances to resolve any discrepancies noted.
l O
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION X O
REVISION:
7 TITLE:
INSPECTION PAGE 4 OF 4 5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
7-~
5.1 Nuclear Quality is responsible for:
a.
Qualifying Quality Control Inspectors.
7-*
b.
Preparing or reviewing inspection planning documents for modification / maintenance activities.
c.
Performing inspections per inspection plans.
7-~
5.2 Nuclear Maintenance is responsible for assuring:
a.
Inspections are performed as required by inspection planning.
b.
Work does not proceed beyond inspector signoffs for hold points.
5.3 Each organization is responsible for:
~~
a.
Supporting inspection activities.
b.
Providing prompt corrective action to any deficiencies found during the inspection.
O
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XI
[^
REVISION:
6 TITLE:
TEST CONTROL PAGE 1 OF 4 LEAD DEPARTMENT:
EF VE DATE:
NUCLEAR OUALITY ASSURANCE Ut-
-4 1
REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
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l MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XI j
O REVISION:
6 i
TITLE:
TEST CONTROL PAGE 2 OF 4 XI.
TEST CONTROL 1.0 PURPOJX 6*
This section describes the Quality Assurance Program measures established to provide for acceptance and surveillance test control at the Rancho Seco Nuclear l
Generating Station.
2.0 REFERENCE DOCUMENTS i
2.1 10 CFR 50, Appendix B, Criterion XI, Test Control i
i 2.2 ANSI N45.2-1971, Section 12, Test Control 2.3 Safety Guide 33/ ANSI N18.7, Administrative Controls for.
Nuclear Power Plants 3.0 POLICY (f
Procedures shall be established and implemented to assure that required testing to demonstrate that structures, systems and components will perform satisfactorily in service is identified, performed and documented.
4.0 GENERAL REOUIREMENTS 4.1 Tests shall be performed in accordance with procedures and I
criteria that designate when' tests are required and how i
they are to be performed.
Such testing includes the following:
Qualification tests, as applicable, to verify design a.
adequacy.
b.
Tests of equipment and components to assure their proper operation prior to delivery or pre-operational tests; c.
Pre-operational tests to assure proper and safe operation of systems and equipment prior to start-up tests or operations; i
d.
Start-up tests, including precritical,. criticality, I
O low-power and power ascension tests performed after fuel loading to assure proper and safe operation of systems and equipment.
(%,
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XI REVISION:
6 TITLE:
TEST CONTROL PAGE 3 OF 4 e.
Surveillance tests to assure continuing proper and safe operation of systems and equipment.
f.
Maintenance tests after preventive or corrective maintenance.
4.2 Test procedures and instructions shall include provisions for the following, as applicable:
a.
The requirements and acceptance limits contained in the applicable design and procurement documents; b.
Test prerequisites such as calibrated instrumentation, required test equipment, degree of completeness of the item to be tested, suitable and controlled environmental conditions and provisions for data collection and storage; c.
Verifying that test prerequisites have been met; d.
Instructions for performing the test; e.
Any inspection points; f.
Acceptance criteria; g.
Documenting or recording test data and results; and h.
Verification of completion.
4.3 Test procedures and instructions shall be reviewed by the applicable organizations for technical content.
4.4 Test results shall be documented and evaluated by responsible authorities to assure that test requirements have been satisfied.
4.5 Test records shall contain the following information where applicable:
a.
Item tested and type of observation; b.
The date and results of the test; c.
Information related to deviations or nonconformances; d.
Identification of person recording the data;
()
Evidence as to the acceptability of the results; and e.
f.
Action taken to resolve any deviations and nonconformances noted.
.-. _ _. ~
i 4
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XI O
REVISION:
6 TITLE:
TEST CONTROL PAGE 4 OF 4 i
5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
6**
5.1 Nuclear Quality is responsible for:
a.
Performance of audits to assure conformance to testing requirements applicable to safety-related items per Section XVIII of this manual.
6**
5.2 Technical Services is responsible for:
i a.
Establishing the procedure for acceptance and surveillance testing.
b.
Providing personnel to perform the testing and acceptance evaluations.
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. =.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XII TITLE:
CONTROL OF REVISION:
6 O
MEASURING AND TEST EOUIPMENT PAGE 1 OF 4 LEAD DEPARTMENT:
NUCLEAR OUALITY ASSURANCE REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
O, 3
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~
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re; PROCEDURE IS ISSUED FOR INFORMATIOM OW!'! AND l
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XII O
TITLE:
CONTROL OF REVISION:
6 MEASURING AND TEST EOUIPMENT PAGE 2 OF 4 XII.
CONTROL OF MEASURING AND TEST EQUIPMENT-1.0 PURPOSE 6-*
This section describes the Quality Assurance Program measures established to provide for the control of measuring and test equipment at the-Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XII, Control of Measuring and Test Equipment 2.2 ANSI N45.2-1971, Section 13, Control of Measuring and Test Equipment 2.3 Safety Guide 33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants.
l 2.4 Reg. Guide 1.30/ ANSI N45.2.4-72, Quality. Assurance Requirements for the installation, inspection and Testing of Instrumentation and Electric Equipment with exception noted in Section II of this manual.
l 3.0 POLICY Procedures shall be established and-implemented to. assure that measuring and testing devices used in final acceptance of activities affecting quality are properly controlled, calibrated and adjusted at"specified intervals to maintain the desired accuracy.
4.0 GENERAL REOUIREMENTS 4.1 Procedures shall be established for calibration, maintenance and control of measuring and test equipment-utilized in the operation, measurement, inspection or monitoring of items.
4.2 Measuring and test equipment shall be uniquely.identifieu and shall be traceable to its calibration test data.
4.3 Labels shall be attached to measuring and test equipment O
to display the next calibration due date.
Where labels cannot be attached, a control system shall be used that identifies to potential users any equipment which may be beyond the calibration due date.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XII TITLE:
CONTROL OF REVISION:
6 i
MEASURING AND TEST EOUIPMENT PAGE 3 OF 4 4.4 Measuring and test equipment shall be calibrated at specified intervals.
These intervals are based on the amount of use, stability, characteristics and other conditions that could adversely affect the required measurement accuracy.
Reference and secondary calibration standards shall be traceable to nationally recognized standards where they exist.
Where national standards do not exist, provisions shall be established to document the basis for calibration.
4.5 M&TE shall be calibrated from refsrence standards with an accuracy ratio of at least four-to-one (reference standard to M&TE).
Calibration accuracy ratios of less than four but equal to or better than one (Reference standard to M&TE) shall be acceptable when equipment required to meet specified requirements is not commercially available.
The basis of acceptance in these cases shall be documented.
4.6 M&TE used for calibrating plant process instrumentation (PI) shall have calibration ranges, precisions, and accuracies such that the PI can be calibrated from M&TE with an accuracy ratio of at least two-to-one (M&TE to ON PI).
Calibration accuracy ratios of less than two but equal to or better than one shall be acceptable when equipment to meet specified requirements is not commercially available.
The basis of acceptance in these cases shall be documented.
4.7 When measuring and testing equipment used for final inspection and test is found to be out of calibration, evaluations shall be conducted to determine the validity of the results obtained since the most recent calibration.
The results of evaluations shall be documented.
Retests or reinspections shall be performed on suspect items as necessary.
4.8 Identification of measuring and test equipment used shall be documented and traceable to work performed to allow for corrective measures to be taken when a device is found to be out of calibration.
5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
7-'54*
5.1 Nuclear Maintenance is responsible for:
Establishing methods for control of measuring and a.
test equipmer.t.
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XII O
TITLE:
CONTROL OF REVISION:
6 MEASURING AND TEST EOUIPMENT PAGE 4 OF 4 b.
Determining the need for calibrated instruments and measuring devices in Rancho Seco activities.
c.
Providing administrative procedures that address the requirements for calibration.
d.
Control of measurement devices to ensure their use and accuracy.
6-~
5.2 Nuclear Quality is responsible for:
a.
Performing audits in accordance with Section XVIII of this manual to assure conformance to the program for control of measuring and test equipment.
O l
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XIII REVISION:
6 TITLE:
HANDLING, STORAGE AND SHIPPING PAGE 1 OF 3 LEAD DEPARTMENT:
NUCLEAR OUALITY ASSURANCE REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
C
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4 MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XIII REVISION:
6 TITLE:
HANDLING. STORAGE AND SHIPPING PAGE 2 OF 3 1
XIII.
HANDLING, STORAGE AND SHIPPING d
1.0 PURPOSE j
6-This section describes the Quality Assurance Program i
measures established to provide for the handling, storage, shipping, cleaning and preservation of material and equipment at the Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XIII, Handling, Storage and Shipping 2.2 ANSI N45.2-1971, Section 14, Handling, Storage and Shipping 2.3 Reg Guide 1.38/ ANSI N45.2.2-1972, Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants with exceptions noted in Section II of this manual.
3.0 POLICY 1
Procedures shall be established and implemented to assure that materials and equipment are properly handled, stored, shipped, cleaned and preserved to prevent damage or i
deterioration.
4.0 GENERAL REOUIREMENTS 4.1 Procedures shall be established for assuring that proper handling, storage, shipping and preservation instructions f
are included in applicable drawings and/or specifications.
4.2 When required for specific items, special protective environments, such as inert gas-atmosphere, specific moisture content levels, and temperature levels, shall be specified.
4.3 A shelf-life program shall be in effect and monitored to prevent usage after the expiration date without recertification for extension of shelf-life.
\\
4.4 Special material handling and preservation instructions O
shall be developed when required by applicable drawings and/or specifications.
i MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XIII J
Os REVISION:
6 TITLE:
HANDLING. STORAGE AND SHIPPING PAGE 3 OF 3 4.5 Materials for packaging, shipment, and storage with the potential for causing contamination or radiation exposure require marking and labeling to indicate the need for special radiological controls.
5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
6**
5.1 Technical Services is responsible for:
a.
Establishing methods and procedures to ensure that applicable drawings and/or specifications include handling, storage, shipping, and preservation l
requirements.
6-~
5.2 Nuclear Maintenance is responsible for:
a.
Establishing methods for special handling, storage, 1
and preservation during maintenance activities.
()
b.
Providing administrative procedures which specify the required controls.
64*
5.3 Nuclear Quality is responsible for:
a.
Performing audits in accordance with Section XVIII of this manual to assure conformance to the program for handling, storage, and shipping.
6-*
5.4 General Services is responsible for:
a.
Maintaining material control / warehousing control of items and equipment which require special handling and storage.
O
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XIV O
TITLE:
INSPECTION, TEST REVISION:
6 AND OPERATING STATUS PAGE 1 OF 3 LEAD DEPARTMENT:
NUCLEAR OUALITY ASSURANCE REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
O
[
b9 DROCEDURE IS ISSUED FOR INFORMATION ONLY AND c
si;%L AGT 3E USED FOR WORK OR DESIGN.
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O
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XIV O-TITLE:
INSPECTION, TEST REVISION:
6 AND OPERATING STATUS PAGE 2 OF 3 XIV.
INSPECTION, TEST AND OPERATING STATUS 1.0 PURPOSE 6**
This section describes the Quality Assurance Program measures established to provide for a system to identify the inspection, test and operating status of individual items at the Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XIV, Inspection, Test and operating Status 2.2 ANSI N45.2-1971, Section 15, Inspection, Test and Operating Status 3.0 POLICY
^
Procedures shall be established and implemented to assure
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that measures are provided to indicate the status of inspections, tests and operations.
4.0 GENERAL REOUIREMENTS 4.1 Procedures shall be written to control nonconforming material, parts and components to prevent their inadvertent use in plant operations.
4.2 Procedures shall specify the degree of control required for the indication of inspection and test status of items required for modification activities.
4.3 The sequence of inspections, tests, and other operations, and changes thereto shall be controlled by procedures.
4.4 Procedures shall provide methods for identifying the nonconforming items, inoperable systems and components by tags, markings, labels, etc. to prevent inadvertent use.
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XIV O
TITLE:
INSPECTION, TEST REVISION:
6 AND OPERATING STATUS PAGE 3 OF 3 5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
6**
5.1 Nuclear Operations is responsible for:
a.
Clearance procedures to ensure safety of personnel and equipment during maintenance and testing activities.
b.
Installation and removal of test and operating status indicators.
6-~
5.2 Nuclear Quality is responsible for:
a.
Identifying the quality status of material, parts, and components.
O O
t MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XV TITLE:
NONCONFORMING REVISION:
6 MATERI ALS. PARTS OR COMPONENTS PAGE 1 OF 4 LEAD DEPARTMENT:
EITECTIVE DATE NUCLEAR OUALITY ASSURANCE 10-26-93 REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
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TPis P5?OCEDURE IS ISSUED POR INFOT211AT10N ONLY AND L,..n=S4f ALL NOT BE USED FOR WORK OR DESIGN.
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4 MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XV O-TITLE:
NONCONFORMING REVISION:
6 MATERIALS, PARTS OR COMPONENTS PAGE 2 OF 4 l
XV.
NONCONFORMING MATERIALS, PARTS OR COMPONENTS l
1.0 PURPOSE
{
4 6-~
This section describes the Quality Assurance Program measures established for controlling material, components, i
parts, or systems that are not in conformance to specified requirements at the Rancho Seco Nuclear Generating l
Station.
2.0 REFERENCED DOCUMENTS i
2.1 10 CFR 50, Appendix B, Criterion XV, Nonconforming Materials, Parts or Components 2.2 ANSI N45.2-1971, Section 16, Nonconforming Items 3.0 POLICY 4
Procedures shall be established and implemented to assure O
that materials, parts or components which do not conform i
to specified requirements are controlled to prevent their inadvertent use or installation.
I i
i 4.0 GENERAL REOUIREMENTS I
4.1 Procedures shall be developed for controlling, documenting, and resolving items, services or activities identified as nonconforming.
4.2 Nonconforming items shall be identified by marking, tagging, segregating, or other means.
4.3 Nonconformances shall be documented, processed, controlled and retained to provide records of the action which was taken to resolve the nonconforming condition.
4.4 Appropriate levels of management will approve the disposition and technical justification of all j
dispositions.
4.5 The nonconformance program shall receive the attention of
)
management personnel to assure prompt closure of i
nonconformances in their area of responsibility.
O 4.6 Trending may be used as a mechanism for providing management information on programmatic or other i
significant deficiencies.
i 1
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XV O.
TITLE:
NONCONFORMING REVISION:
6 MATERIALS. PARTS OR COMPONENTS PAGE 3 OF 4 4.7 Nonconformances shall be reviewed to determine if they are potentially reportable per 10 CFR 21.
5.0 RESPONSIBILITIES General organizational responsibilities'are described-in Section I, ORGANIZATION.
I 6-~
5.1 Nuclear Quality is responsible for:
a.
Providing management representation and expertise on 4
the. Commitment Management Review Group (CMRG);
j reviewing identified conditions which are adverse to l
quality and the corrective action associated with those conditions.
b.
Establishing methods for controlling and documenting nonconformances.
c.
Ensuring expertise is available to disposition i
nonconformances.
O d.
Developing ~ safety analyses that address the
{
nonconforming condition, if required.
j l
6-*
5.2 Technical Services is responsible-for:
i a.
Ensuring expertise is available to disposition j
nonconformances.
b.
Developing safety analyses that address the nonconforming condition, if required.
c.
Providing management representation and expertise on the Commitment Management Review Group (CMRG);
reviewing identified conditions which are adverse to quality and the corrective action associated with those conditions.
6-*
5.3 Operations is responsible for; a.
Taking appropriate action to ensure operation of the plant in conformance to license requirements when a nonconformance' identifies a condition prohibiting components, structures, or systems from returning to an acceptable condition.
(
b.
Determining the safety significance of the nonconforming condition on the status of the plant.
~
i l
P MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVI REVISION:
6 g
TITLE:
CORRECTIVE ACTION PAGE 1 OF 3 s
LEAD DEPARTMENT:
EFFECTIVE DATE NUCLEAR OUALITY ASSURANCE 10-26-93 REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco organization.
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- ' OCEDURE IS ISSUED FOR f
- r0Rr1AT10N ONLY AND l
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O BE USED FOR WORK OR DESIGN.
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l MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XV l
O TITLE:
NONCONFORMING REVISION:
6 MATERIALS. PARTS OR COMPONENTS PAGE 4 OF 4 c.
Providing management representation and expertise on the Commitment Management Review Group (CMRG);
reviewing identified conditions-which are adverse.to quality and the corrective action associated with those conditions.
d.
Ensuring expertise is'available to disposition nonconformances.
e.
Developing safety analyses that address the nonconforming condition, if required.
i 6-*
5.4 Radiation Protection and Chemistry is responsible for:
l a.
Ensuring expertise is available to disposition i
nonconformances.
b.
Developing safety analyses that address the nonconforming condition, if required.
j c.
Providing management representation and expertise on the Commitment Management Review Group (CMRG) ;
i O
reviewing identified conditions which are adverse to j
quality and the corrective action associated with those conditions.
6-~
5.5 Maintenance is responsible for:
a.
Ensuring expertise is available to. disposition nonconformances.
b.
Developing safety analyses that address the nonconforming condition, if required.
c.
Providing management representation and expertise on the Commitment Management Review Group (CMRG);
reviewing identified conditions which are' adverse to quality and the corrective action associated with those conditions.
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVI O
REVISION:
6 i
TITLE:
CORRECTIVE ACTION PAGE 2 OF 3 f
XVI.
CORRECTIVE ACTION 1.0 PURPOSE 6**
This section describes the Quality Assurance Program measures established to provide for a corrective action program to assure that conditions adverse to quality are promptly identified and corrected at the Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XVI, Corrective Action 2.2 ANSI N45.2-1971, Section 17, Corrective Action 3.0 POLICY 5
Procedures shall be established and implemented to assure O
that significant conditions adverse to quality are identified and that corrective action is taken to preclude l
repetition.
4.0 GENERAL REOUIREMENTS 4.1 Controls shall assure conditions adverse to quality such i
as malfunctions, errors, deficiencies or nonconformances are identified, documented and appropriate corrective action taken.
The controls shall assure that the corrective action is implemented in a timely manner.
4.2 For significant conditions adverse to quality, corrective action includes determining the'cause and extent of the condition, taking corrective action to remedy the condition and taking action to prevent recurrence.
These 1
actions shall be reported to management personnel for review and assessment.
4.3 Conditions adverse to quality are evaluated to determine I
if they are potentially reportable per 10 CFR 21 or 10 CFR 50.73.
4.4 Identified conditions adverse to quality shall be reviewed by the Commitment Management Review Group (CMRG) for O
severity.
Corrective action for identified conditions shall be reviewed and approved by the CMRG.
l t
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVI O
REVISION:
6 TITLE:
CORRECTIVE ACTION PAGE 3 OF 3 i
i 5.0 RESPONSIBILITIES.
General organizational responsibilities are described in Section I, ORGANIZATION.
l l
I 6-*
5.1 All departments are responsible for:
a.
Formulating appropriate corrective actions as they
}
apply to their departments.
I b.
Implementing proposed corrective action.
c.
Assuring that proposed corrective action is l
effective.
i 6-*
5.2 Nuclear Quality is responsible for:
i a.
Establishing the corrective action program.
b.
Performing audits of the Corrective Action Program, as implemented throughout the plant, in accordance with Section XVIII of this manual.
j i
l l
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVII i
01 REVISION:
6 TITLE:
OUALITY ASSURANCE RECORDS PAGE 1 OF 3 LEAD DEPARTMENT:
EFFECTIVE DATE NUCLEAR OUALITY ASSURANCE 10-26-93 REVISION
SUMMARY
1.
Updated to reflect the current Rancho Seco-organization.
i O
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TMS PROCEDURE IS ISSUED POR INFOR11AT10N ONLY AND t[~:-nn- +.
ntALu NOT BE USED FOR WORK OR DESIGN.
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MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVII
[\\
REVISION:
6 TITLE:
OUALITY ASSURANCE RECORDS PAGE 2 OF 3 XVII.
QUALITY ASSURANCE RECORDS 1.0 PURPOSE 6-*
This section describes the Quality Assurance Program measures established for the storage and maintenance of Quality Assurance Records which provide the documentary evidence of activities affecting quality performed at Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XVII, Quality Assurance Records 2.2 ANSI N45.2-1971, Section 18, Quality Assurance Records 2.3 Safety Guide 33/ ANSI
.7, Administrative Control for Nuclear Power Plants, para 5.2
('
2.4 RGl.28/ ANSI /ASME, NQA-1-1983, Supplement 17S-1,
(_)T Supplementary Requirements for Quality Assurance Records with exceptions noted in Section II of this manual.
6--
2.5 Technical Specifications Section D6.0 3.0 POLICY Procedures shall be established and implemented to assure storage and maintenance of records which represent evidence of activities described in Section II, Paragraph 4.2 of this manual.
4.0 GENERAL REOUIREMENTS 4.1 Quality Assurance records shall be permanently stored in a facility that meets the requirements of Ref.
2.4.
4.2 Quality Assurance records shall be protected during interim storage in accordance with Ref.
2.4.
4.3 Documents that furnish evidence of the quality of items and services are generated and controlled in accordance with the procedures that govern those activities.
Such s
documents are considered Quality Assurance Records upon N
completion.
Quality Assurance Records are considered completed when they have been stamped, initialed or signed
I J
1 i
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION-XVII L
REVISION:
6 TITLE:
OUALITY ASSURANCE RECORDS PAGE 3 OF 3 and dated by authorized personnel =or otherwise authenticated.
4.4 The record system shall provide for identification and retrievability of the records to the extent that information can be obtained in a reasonable amount of
}
time.
4.5 The records program shall address records classification (rotention period), storage location and responsibility for retention and retrievability.
4.6 A records retention schedule shall be established which addresses the requirements of Ref. 2.4 and 2.5.
l l
5.O RE_SPONSIBILIT_I_ES S
General organizational responsibilities are described in-Section I, ORGANIZATION i
6--
5.1 Records Control is responsible for:
a.
Establishing methods for control of records.
b.
Providing administrative procedures which define the records storage program and provide for ready retrievability.
6-5.2 Each department is responsible for:
a.
Transmitting completed records to Records Control.
i b.
Providing interim storage in accordance with section 4.2, prior to transmittal to Records Management.
6-~
5.3 Nuclear Quality is responsible for:
a.
Conducting audits in accordance with'Section XVIII of this manual of the records management' system'to assure conformance to specified requirements.
O
9 i
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVIII O
REVISION:
6 i
h TI'TLE :
AUDITS PAGE 1 OF 3 j
LEAD DEPARTMENT:
Y r Yts DATE i
NUCLEAR OUALITY ASSURANCE 3
REVISION
SUMMARY
i 1.
Updated to reflect the current Rancho Seco 1
organization.
i 6
.h I
1 l
i O
t THIS PROCEDURE IS..lSSUED POR INFORl1AT10N ONLY AND-IL__M;ALL NOT BE USED FOR WORK OR DESIGN.
O
MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVIII
"'i REVISION:
6 TITLE:
AUDITS PAGE 2 OF 3 XVIII.
AUDITS 1.0 PURPOSE 6-~
This section describes the Quality Assurance Program measures established for a comprehensive system of planned and periodic audits to determine the effectiveness of the Quality Program at the Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10 CFR 50, Appendix B, Criterion XVIII, Audits 2.2 Safety Guide 33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants 2.3 Reg. Guide 1.144/ ANSI N45.2.12-1977, Requirements for Auditing of Quality Assurance Programs for Nuclear Power Plants
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^
Reg Guide 1.146/ ANSI N45.2.23-1978, Qualification of 2.4 Quality Assurance Program Audit Personnel for Nuclear Power Plants 6-~
2.5 Technical Specifications, Section D6.0 3.0 POLICY Procedures shall be established and implemented to assure that planned and periodic audits are c'onducted to verify compliance with all aspects of the Rancho Seco Quality 6-*
Assurance Program and Technical Specifications.
4.0 GENERAL REOUIREMENTS 6-~
4.1 Nuclear Quality shall establish a schedule for auditing the activities affecting quality.
The audit schedule shall be consistent with the Technical Specification requirements at Rancho Seco.
4.2 The audit program shall be described in procedures which implement the requirements of this section.
[ )
4.3 Audits shall be conducted to determine the adequacy and k/
effectiveness of programs implemented for the design, procurement, modification, maintenance and operational activities at Rancho Seco.
h MANUAL:
RANCHO SECO QUALITY MANUAL NUMBER:
RSQM-SECTION XVIII l
O REVISION:
6 TITLE:
AUDITS PAGE 3 OF 3 4
4.4 Audit plans shall'be developed which identify the audit i
scope, the requirements, activities to be audited, organizations to be notified, the applicable documents and the audit schedule.
6**
4.5 Audits shall be performed using approved audit checklists.
4.6 Audit reports shall be issued which identify the activity
{
which was audited, personnel contacted during the audit, and any conditions adverse to quality noted during the
-j audit.
4.7 Identified conditions adverse to quality will be processed using the Rancho Seco Corrective Action Program.
4.8 Personnel conducting audits shall be. trained and qualified in accordance with Reference 2.4.
l 4.9 Regularly scheduled audits shall be supplemented by special audits when conditions which warrant special i
audits exist or when requested by Management.
i O
5.0 RESPONSIBILITIES i
General organizational responsibilities are described in Section I, ORGANIZATION.
i 6**
5.1 Nuclear Quality is responsible for:
a.
Establishing a schedule for performance of required l
audits.
i b.
Reviewing audit results to evaluate the effectiveness of the Quality Program.
c.
Implementation of the established audit program.
d.
Training and qualification of audit personnel.
e.
Preparation of trend analysis data.
6-*
5.2 Each department is responsible for:
a.
Supporting the audit activities.
b.
Providing prompt response to any deviations from quality identified in the audit.
.