ML20235N993
| ML20235N993 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 09/18/1987 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20235N984 | List: |
| References | |
| NUDOCS 8710070133 | |
| Download: ML20235N993 (78) | |
Text
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NUMBER:. R$QM RANCHO SECO QUALITY MANUAL 4
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i R A N C H 0 S E C 0 J
QU A L I T Y H A N U A L l
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P SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT
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NUMBER: RSQM RANCHO SECO QUALITY MANUAL LEAD DEPARTMENT:
QUALITY ASSURANCE
.......9lv.lC7 fftw*' _f l V DIRE OR. NUCLE OUALITY / DATE CE,. NUCLEKR / DATE REVISION
SUMMARY
Rancho Seco Quality Program, Rev. O, dated 1/1/86 is included in the USAR in App. 128.
The Quality Program was revised and renamed Rancho Seco Quality Manual.
Rev. 1 was approved on 4/27/87 and submitted to the NRC for approval per 10 CFR 50.54(a) on S/l/87.
This Rev. 2 is being prepared to address comments received from the NRC dated 7/31/87.
I Significant changes in this revision include:
Change from Deputy General Manager to CEO, Nuclear Change from Corporate Quality Manager and Rancho Seco Quality Manager to Director, Nuclear Quality Added organization chart Added responsibilities and reporting requirements for the Manager Scheduling and Outage Management, the Security Supervisor and the Director, Management Systems HP5882P/D-0432P
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"[iUH8ER:
RSQM RANCHO SEC0 QUALITY MANUAL REVISION:. 2 PAGE 1 0F l' RANCHO SECO QUALITY MANUAL TABLE OF CONTENTS :
SECTION LATEST-DATE OF NO.
TITLE REVISION REVISION-t 2- - -
Quality Assurance Policy 2
9-18-87 I
Organization 2
, 9-18-87 II Quality Assurance Program 2
9-18-87 III Design Control 2
'9-18-87 IV Procurement Document Control 2
9-18-87 V
Instructions, Procedures and Drawings 2
9-18-87 l
VI Document Control
'2 9-18-87
]
VII Control of Purchased Material, Equipment and Services 2
9-18-87 VIII Identification and Control of Materials, Parts and Components 2
9-18-87 IX Control of Special Processes '
2 9-18-87:
X Inspection 2
9-18 XI Test Control 2
9-18-87 XII Control of Measuring and Test Equipment
.2 9-18-87.
XIII Handling, Storage and Shipping 2
9-18-87 XIV Inspection, Test and Operating q
Status 2
9-18-87 XV Nonconforming Materials, Parts ~or Components 2
9-18-87 XVI Corrective Action 2
9-18-87 XVII Quality Assurance Records 2
9-18-87 XVIII Audits 2
9-18-87
NUMBER:
RSQM RANCHO SECO QUALITY MANUAL REVISION:
2 PAGE 1 0F 1 QUALITY ASSURANCE POLICY The Sacramento Municipal Utility District's (SMUD) policy regarding Quality Assurance function 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:
2-~
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.
i c.
To provide facilities which are designed, modified, constructed, tested and operated in accordance with specified requirements, with assurance against failure of malfunctions, and without undue risks to the health and safety of the public.
I d.
To ensure prompt identification and resolution of actual and potential problem areas in design, procurement, construction, testing, operations, maintenance and modification of safety related systems, structures and components.
II. Accountability for achieving the quality of structures, systems, components and services rests with the organizations and individuals performing the functions of design, construction, maintenance, modifications, and operations.
III. Accountability for determining that the structures, systems, components and services meet the stated requirements rests with the organizations and individuals performing quality verification functions, such as design review, document review, inspection, surveillance and audits.
The responsibility for implementation of the overall Rancho Seco Quality 2-~
Program is delegated to the Director, Nuclear Quality. He shall be responsible for assuring the adequacy, implementation, effectiveness and status of the quality program. Any conflicts resulting from the implementation of the Quality Program which cannot be resolved by the 2--
Director, Nuclear Quality shall be referred to the CEO, Nuclear for resolution.
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DIRECTOR, NUCLEAR QUALITY
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RSOH-SECTION I RANCHO SEC0 QUALITY MANUALc REVISION:
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ORGANIZATION 1
1.0 BIRPOSE f
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. Ed This section describes the Sacramento Municipal Utility District (SMUD) organizations and key personnel responsible for:
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establishing, implementing, and. verifying the effectiveness of
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the Quality Assurance Program to assure safe and reliable operation of the Rancho'.Seco Nuclear Generating Station.
3; 2.0 BffERENCE DOCUMENIS Y
2.1 10CFR50, Appendix B, Criterion I, Organization a
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2.2 ANSI N45.2-1971, Sectio #2, Organization
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2.3 Reg. Guide 1.33/ ANSI N18.7, Administrative Controls-for' Nuclear.
Power P1 ants-t 3.0 POLICY 3.1 SMUD acknowledges full res)onsibility for the establishment and implementation of the Ranclo Seco Quality Program.
Portions of the Quality Program functions may be delegated to other SMUD approved external organizations, but overall responsibility for the program is retained and exercised by SMUD.
3.2 Definitive lines of authority, responsibility and~ commuriication have been established for those: organizations involved in the Rancho Seco Quality Program and are illustrated in the SMUD organizational charts. These lines extend from the' highest management level through intermediate levels, to and iiicluding 4
onsite organizational elements.
3.3 Quality Assurance personnel assigned to Rancho Seco have defintid ~
2-responsibilities and organizational freedom ~ to_ identify problems 1
that affe n quality; to initiate, recommend, or provide solutions; and to verify implementation of solutions.
They have
'2-the authority, with the concurrence of..the Director, Nuclear Quality.or his designee, to initiate action to stop unsatisfactory work pending implementation of'necessary).
. corrective ~ action to bring the unsatisfactory conditions into conformance.
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y PAGE 2 0F 14 The organizational struckure and fwetional responsibility 3.4 assignments are such that attainnent of program objectives is accomplished by individuals or groups who inspect, examine, audit or otherwise verify conformance.to etablished requirements, and
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who are independent of the individu'als or groups who performed
.i the original activity.
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4.0 ORGANIZATION AND RESPONSIBILITIES 1
2-Attachment i depicts the Rancho Seco Nuclear Organization Chart.
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Specific duties and responsibilities of positions / groups that involve performance of quality functions are as follows:
2--
4.1 THE CRLEf_ EXECUTIVE OFFICER (CEO) - RUCLE M is responsible to.the.
l District Board of Directors for the safe and reliable operation i
2-of Rancho Seco.
In fulfilling this respo,nsibility, the CEO, Nuclear establishes the District Nuclear Policy through written i
directives, and has delegated authority and responsibility for 2-development and execution of the Quality Program to the Director, Nuclear Quality, i
Positions or organizations reporting directly to the CEO, Nuclear
/
2-~-
include: Assistant General Manager (AGM) Technical and-l Administrative Services, and Assistant General Manager (AGM) l 2--
Nuclear Power Production and the Director, !!uclear Quality.
j The CEO, Nuclear has the responsibility and authority for l
development and execution of the Rancho Seco Quality Program and f
is committed to achieving the objectives to ensure optimum a'
quality performance and safe, reliable operation.
In fulfillment of this commitment, the CEO, Nuclear conducts a final review of 2'- 4 the Rancho Seco Quality Manual and subsequent revisions, and provides signature approval upon concurrence.
The CEO, Nuclear is responsible for the administrative actions necessary to assupa that the Rancho Seco Quality Program is implemented by the organizations under his direction. To this extent, the CEO, Nuclear maintains a continuing involvement in quality matters and anesses the scope, status, implementation and effectiveness of the Quality Program through Quality Status 1
Reports, Trend Analyses, Root Cau m Analyses, independent Quality Audits or Surveillance Summary Reports, and Management Safety Review Committee (MSRC) meeting minutes.
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RANCHO SEC0 QUALITY MANUAL REVISION: 2.pJ.-
1 PAJE 3 0F 14 I l..
I 4.2 ASSJSTANT GENERAL MANAGER (AGM). TECHNICAL AND ADMItqSTRATIVE SERj/JfES reports directly to the CEO, Nuclear.
Provides j
centralized administrative and technical services to Muclear Power Production in the form of Engineering, Environmental
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Protection, Licensing, Cost Control, Materials Control, Document
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Control and Records Management.
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4.2.1 DIRECTOR. ADMINISTRATIVE SERVICES reports directly to the AGM, Technical and Administrative Services.
Provides centralized.
services.and support for other Nuclear Organization Departments s
in the areas of materials management, budget and contract preparation'and control, information management, docnnent control, records management, and general office servi'ces.
4.2.2 BA @ ER. MATERIAL CONTROL reports to the Director, Administrative Services.
Establishes and manages the Materials Control Department to ensure a suppl.t of appropriately qualified,. stored,'
and identified, spare parts and construction materials.
2-Manager, Material Cstrol is responsible for procurement and control of purchased inaterials. Spdfic duties and responsibilitic of the Manager, Material Control are' outlined in 1-Section IV, VII, VIII and XIII of this manual.
4.2.3 MAN _A_GER. _ COST CONTROL AND OFIJ_CE SERVICES reports directly to the 2-~
Director, Administrative Services.
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The duties and responsibilities of the Manager, Cost Control and Office Servics, include:
i ai EnsureeffectivedocumentcontrolforNue$arOrganization
',.j Departments.
b.
Ensure regule+ory compliance of'reco s management and other I
aud'ted functions by managir,9 interpretation and application of regulatory requirements.
j
'2-Specific duties and responsibilities of the-Manager, Cost Control and Office Services are outlined in Section VI and XVII.
h 4.3 QJRECTOR. TECHNEAL SEMIES reports directlyf to the AGM, s
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Technical and Administrative Services.
Provides engineering and
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- regulatory support of nurfear operations to ensure a safe and
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reliable plant design Mch is operated in full compliance with
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regulations.
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RSQM-SECTION I RANCHO SECO QUALITY MANUAL REVISION:
2 PAGE 4 0F 14 1
4.3.1 MANAGER. NUCLEAR LICENSING reports directly to the Director, Technical Services.
Provides regulatory guidance, compliance and licensing services to maintain the operating license at Rancho Seco.
I The duties and responsibilities of the Manager, Nuclear Licensing
'nclude:
a.
. Manage licensing activities, including those related to maintaining the license, generic licensing issues, and the Updated Safety Analysis Report commitments, b.
Prepare all safety analysis as required per 10CFR50.59.
(
c.
. Provide guidance,'and counsel on current and future regulatory matters.
l d.
Maintain the USAR, including the technical specifications.
e.
Determine and analyze selected events for root causes of Leks, trips and other assigned events, f.
Ensure compliance with regulatory requirements and commitments.
g.
Provide a centralized communication channel with all regulatory and insuring agencies including NRC, INPO, and ANI.
h.
Administer the Commitment Control Program.
2-~
i.
Reporting of occurrences or significant events.
4.3.2 MANAGER. ENVIRONMENTAL PROTECTION reports directly to ine Director, Technical Services.
Ensures the health and safety of the public and plant personnel during normal operation, and in the event of an emergency at Rancho Seco.
The duties and responsibilities of.the Manager, Environmental Protection include:
I a.
Develop, maintain, and implement an emergency plan in accordance with specified requirements, b.
Develop, maintain, and implement the ALARA Program.
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RSQM-SECTION I RANCHO SECO. QUALITY MANUAL REVISION: 2 1
PAGE 5 0F 14 4.3.2 (Coritinued) c.
Conduct emergency drill and personnel training on'the.
d.
Minimize preventable cont' amination' of plant personnel and -
areas.by supporting 'and auditing ' radiation protection.
4.3.3 MANAGER. NUCLEAR ENGINEERING reports directly.to the Director, Technical Services.
Provides design documents such as drawings, specifications, and other documents defining technical.
requirements of systems, structures, and components to. yield-a safe and reliable plant design.
Specific duties and responsibilities of the Manager, Nuclear 2--'
Engineering are outlined in Section II, III IX, XIII', and'XV of this manual.
2-~
4.4 DIRECTOR. NUCLEAR OVALITY, reports directly'to the CEO, Nuclear.
Ensures that 6.. active quality program is implemented at SMUD in accordance with regulatory requirements.
2--
The Director, Nuclear Quality is independent of.the pressures of production and has sufficient authority and organizational 2--
freedom to identify problems that affect quality, recommend solutions, and verify implementation of solutions. Commensurate with this responsibility is the authority to initiate action to stop unsatisfactory work and control further processing, delivery, installation, construction or modification of nonconforming items, or continuation of nonconforming services / operations, pending correction of the unsatisfactory-condition.
2-The qualification requirements of the Director, Nuclear Quality are as follows:
a.
Education: BS in Engineering or related science-b.
Experience:
Four years experience in.the field of quality:-
assurance, or equivalent number of years of nuclear plant experience in a supervisory. position, preferably at an operating nuclear plant or a combination.of the two. At least one. year of this four years experience shall be nuclear' power plant experience'in the implementation of the quality assurance program.-
NUMBER:
RSQM-SECTION I RANCHO SECO QUALITY MANUAL REVISION:
2 PAGE 6 0F 14 4.4 (Continued) 2-The duties and responsibilities of the Director, Nuclear QualityJnclude:
a.
Develop, maintain, and ensure the effective implementation of the Rancho Seco Quality Program.
2-~
b.
Develop a vendor quality assurance evaluation program for maintenance of an Approved Suppliers List (ASL).
c.
Administer a corrective action program.
d.
Administer a nonconformance control program, i
2--
e.
Direct the activities of the Quality Assurance Department.
2--
f.
Develop and implement an audit and surveillance program to ensure conformance to the Quality Manual, Technical Specifications, Federal Regulations, applicable Regulatory Guides, Codes and Standards, g.
Provide qualified inspection personnel to perform inspection activities for plant operations, receiving, maintenance, modifications / construction, and source inspections.
h.
Ensure that a training program for Quality personnel who perform audits, surveillance activities, inspections, documentation control or other quality related activities is maintained, i.
Provide for periodic review and trend analysis of deficiency documents to detect possible adverse quality trends.
j.
Maintain communications with regulatory agencies, suppliers, 2-~
contractors and other Rancho Seco departments on Quality matters.
k.
Participate in the disposition of nonconformances.
1.
Participate as a member of the Management Safety Review Committee.
2-~
m.
Report to the CEO, Nuclear on the status and adequacy of the Quality Program.
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RSQM-SECTION I RANCHO SEC0 QUALITY MANUAL REVISION:
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PAGE 7 0F 14 4.4 (Continued) 2--
n.
Notify management of problems affecting quality and l
recommend corrective actions.
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Establish and verify that appropriate qual !y requirements.
for procurement of safety-related materials, components or
'l services are specified in procurement documents.
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Coordinate with the managers of other organizations to assure that their organizational procedures comply with
. applicable requirements of the overall Quality Program and regulatory documents.
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2-Specific duties and responsibilities of the Director, Nuclear l
Quality are outlined in Section III through XVIII.
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4.5 ASSISTANT GENERAL MANAGER (AGM). NUCLEAR POWER PRODUCTION reports l
directly to the CEO, Nuclear. Provides overall direction of the i
production of nuclear power and plant support activities to I
optimize safety, capacity, and availability of the Rancho Seco l
Nuclear Generating Station.
Also functions as the principle SMUD officer on site, responsible for maintaining a safe, secure, and efficient work place.
4.6 DIRECTOR. NUCLEAR OPERATIONS AND MAINTENANCE reports directly to the AGM, Nuclear Power Production <.
Provides nuclear operations, maintenance, and scheduling functions' required to safely, legally, and reliably generate electricity.
The duties and responsibilities of the Director, Nuclear Operations and Maintenance include:
a.
Ensure safety of operations by effective management.
Control the operational status of plant systems and equipment to maintain personnel and reactor safety, and preserve the integrity of the design configuration.
b.
Ensure overall nuclear safety and compliance with regulatory requirements by promoting a positive attitude and managing adherence to regulations and safe work practices.
2-Specific duties and responsibilities of the Director, Nuclear Operations and Maintenarice are outlined in Section XV.
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RSQM-SECTION I RANCHO SECO QUALITY MANUAL REVISION:
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PAGE 8 0F 14 4.6.1 MANAGER. 0.P_ERATIQNji reports directly to the Director, Nuclear 1
Operations and Maintenance.
Responsible for plant ava.ilability and for operating the plant in a safe, reliable, and legal manner.
i The duties and responsibilities of the Manager, Operations 1
include:
l a.
Ensure compliance with internal and external control i
requirements by mar. aging adherence to regulations, l
l procedures, policies, standards and specifications.
i b.
Maintain plant within technical specification limits during l
all operating and shutdown modes.
l c.
Ensure plant safety during normal, abnormal, and accident modes by providing adequate qualified and trained personnel.
d.
Establish and adhere to procedural controls for operations
)
activities.
{
2-e.
Establishment and maintenance of the Shift Technical Advisor i
(STA) Program.
I Specific duties and responsibilities of the Manager, Operations j
are outlined in Section XIV.
J 4.6.2 MANAGER. MAINTENANCE reports directly to the Director, Nuclear Operations and Maintenance. Maintains the physical condition of the plant in a reliable and safe condition.
1 Th9 duties and responsibilities of the Manager, Maintenance i
include:
i a.
Manage maintenance and assigned modifications activities, b.
Ensure department compliance with internal and external requirements by managing adherence'to applicable codes, regulations, procedures, policies, standards and I
specifications.
I c.
Establish and maintain a maintenance program of planned preventive maintenance, standard work packages, and other tools and methodologies to achieve mission effectively.
d.
Work in conjunction with Systems Engineering to plan preventive maintenance.
I 2-Specific duties and responsibilities of the Manager, Maintenance are outlined in Section VIII, XI and XIII.
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RSQM-SECTION I RANCHO SECO QUALITY MANUAL REVISION:
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PAGE 9 0F 14 1
4.6.3 MANAGER. MODIFICATIONS reports directly to the Director, Nuclear Operations and Maintenance. The duties and responsibilities of the Manager, Modifications include:
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i a.
Assemble and implement modification work package upon-issuance of design.
i b.
Provide field engineering support during modifications work activities to resolve in-process problems; verify.
performance to design requirements and assigned procedures.
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c.
Ensure department compliance with internal'and external requirements by managing adherence to applicable codes, j
regulations, procedures, policies, standards, and-specifications.
2-Specific duties and responsibilities of the Manager, Modifications are outlined in Section VIII.
4.7 DJRECTOR. PLANT SUPPORT reports directly to the AGM, Nuclear Power Production.
Provides technical support to Nuclear i
Operations and Maintenance relating to radiation protection, chemistry, plant performance, and training.
The duties and responsibilities of the Director, Plant Support include:
a.
Develop program to minimize employee and public exposure to radiation hazards.
b.
Ensure overall plant operating safety, and meet regulatory inspection / testing requirements by directing the Plant Performance Department.
l c.
Ensure accreditation of programs, employee performance on j
qualification exams, and effective learning by directing the 1
Nuclear Training Department.
1 d.
Ensure health and safety of Plant Support employees and j
compliance with the Rancho Seco ALARA Program.
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f RANCHO SECO QUALITY MANUAL.
REVISION: 2 PAGE 10 0F 14
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'24 4.7.1 MANAGER. RADIATION PROTECTION reports directly.to the-Director -
1 Plant Support.
Responsible for minimizing employee and public' exposure to radioactivity, and meeting: regulatory requirements.
The' dutips and responsibilities of the Manager, Radiation Protection include:
1 a.
Implement program to minimize-the radiation exposure to plant employees and contractors.
I b.
Ensure proper controls over radioactive waste by managing radwaste processing and control.
3 c.
Ensure compliance with regulatory requirements for radiation i
protection and radwaste by managing requirements and programs, and ensuring adherence to procedures'.
d.
Ensure that' radiation protection (RP) functions support plant operations and maintenance by planning,. scheduling, and managing the department.
4.7.2 MANAGER. PLANT PERFORMANCE reports directly to the Director, Plant Support. Provides performance and system' engineering support to plant operations,' maintenance, and testing to enhance 1
plant performance and to ensure operational readiness.
The duties and responsibilities of the Manager, Plant Performance l
include:
a.
Maintain performance and safety of operating plant safety:
systems by. effectively utilizing-Systems Engineering concept for plant support.
b.
Ensure health and safety of staff.by fostering adherence to radiation protection practices.
c.
Provide design documents.such as drawings; specifications and other documents defini_ng technical requirements of..
i systems, structures, and components that yield a safe and reliable plant design.
d.
Interface with engineering to obtain response to plant problems.
e.
Establish and implement fire protection program in accordance with regulatory requirements.
2-+
f.
Establish and implement a Inservice Inspection (ISI) Program.
Specific duties and responsibilities of the Manager, Plant Performance are outlined in Section XI.
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RSQM-SECTION I RANCHO SECO QUALITY MANUAL REVISION:
2 PAGE 110F 14 g
4.7.3 M1ANAGER. TRAIME reports directly to the Director, Plant I
Support.
Provides training support to Nuclear Organization Departments through required accredited training programs, and other requested and approved training activities.
The duties and responsibilities of the. Manager, Training include:
i a.
Overall management and direction of training programs.
b.
Achieve and maintain accreditation of prescribed training programs and ensure that training program and activities 3
satisfy NRC regulatory and industry standards.
l c.
Develop and provide training for departments within and outside of the Nuclear Organization in accordance with accredited training programs and approved Training Plans including all formal classroom, laboratory and simulator training.
j d.
Review training programs and materials for use within other departments.
e.
Maintain the Training Plan and Schedule, f.
Maintain training records in accordance with NRC regulatory and industry standards and the District requirements.
2-4.7.4 MANAGER. CHEMISTRY reports directly to the Director, Plant Support.
Responsible for maintaining control of plant chemistry and meeting regulatory requirements.
The duties and responsibilities of the Manager, Chemistry include:
a.
Ensure control of plant chemistry, and support efficient operations by managing and advising management on chemistry issues.
b.
Ensure compliance with regulatory requirements for chemistry by managing requirements and programs, and ensuring i
adherence to procedures.
Ensure that chemistry functions support plant operations and c.
maintenance by planning, scheduling, and managing the department.
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REVISION:- 2 l
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2-4.8 MANAGER. S.CHEDULING AND OUTAGE MhNAGEMENT reports directly to the AGM,' Nuclear Power Production. Directs the execution of those
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activities that support the plant operation, through implemenfationofschedulingand;outagemanagement.
The duties and' responsibilities of th'e. Manager, Scheduling and -
Outage Management. include:
a.
Apprise management,of schedule impediments and'obtain commitments for corrective action.
b.
Establish realistic long-term planning, scheduling, and
.I completion of NRC required modif_ications and establish and._
stabilize required resources.
t c.
Ensure safetycsystem availability by timely completion of corrective maintenance work requests by monitoring status, assigning priorities, and. reviewing.and scheduling work.
4.9 SECURITY SUPERVISOR reports to the AGM, Nuclear. Power Production i
and is responsible for the security force'at Rancho Seco.
The l
Security Group is also responsible for maintaining' the security plan and security plan implementing procedures in accordance with 10CFR73.55.
2-4.10 DIRECTOR. MANAGEMENT SYSTEMS reports directly to the CEO, j
Nuclear.
Responsible for technical and administrative' direction.
to accomplish the following activities:
q q
Design, development, testing and validation,' configuration a.
and implementation of Rancho Seco'Hanagement Control Systems (Procedural and automated applications)..
b.
Procurement, installation, testing, validation and maintenance of all management systems' support hardware, operating system software and data base software.
c.
Procurement, installation, testing, validation and maintenance of all communication related hardware and
'l software.
4.11 PLANT REVIIH COMMITTEE (PRC) Th'e Committee composition, responsibility and authority, subjects.to be reviewed, and reporting requirements are addressed in Section 6 of the Rancho' Seco Technical Specifications and the PRC Charter.
The PRC.
functions to advise the AGM, Nuclear Power Production on all matters related to nuclear' safety.
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RSQM-SECTION I RANCHO SECO QUALITY MANUAL REVISION:
2 PAGE 13'0F 14 4.12 MANAGEMENT SAFETY REVIEW COMMITTEE (MSRC) The Committee composition,, responsibility and authority, subjects to be reviewed, administrative controls, and reporting requirements are addressed in Section 6 of the Rancho Seco Technical Specifications and the MSRC Charter.
The MSRC also functions to provide for an independent review and audit of designated activities in areas of:
j J
a.
Nuclear power plant operations
)
b.
Chemistry and radiochemistry J
c.
Radiological safety i
d.
Records / documentation e.
Modifications / maintenance f.
EQ Program-g.
Fire protection h.
Refueling i.
Emergency planning j.
Quality Assurance practices k.
Training 5.0 GENERAL RESPONSIBILITIES Each department or organization involved in the design, construction / modification, maintenance and operation of Rancho
)
Seco is responsible for documenting and maintaining its internal j
organization charts, supported by written job descriptions or j
other narrative material in sufficient detail that the duties and j
authority of each individual whose work affects quality is clearly be defined.
1 Each manager has the responsibility to ensure that department programs implement the quality program requirements.
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NUMBER: RSQM-SECTION II RANCHO SECO QUALITY MANUAL-REVISION: 2 PAGE 10F 13 II.
QUALITY ASSURANCE PROGRAM 1.0 PURPOSE I
The purpose of this section is to describe the Quality Program which shall be implemented at Rancho Seco Nuclear Generating Station.
2.0 REFERENCES
2.1 10CFR50, Appendix 8, Criterion II, Quality Assurance Program 2.2 ANSI N45.2-1971, Section 3, Quality Assurance Program 2~
2.3 Reg, Guide 1.33/ ANSI N18.7, Administrative Controls'for Nuclear Power Plants.
2.4 10CFR71, Subpart H, Quality Assurance Requirements for Packaging andTransportationofRadioactiveMatefal.
i 3.0 POLICY j
l The Quality Program. described herein is designed.to assure.
'I l
compliance with the requirements of 10CFR50, Appendix B, " Quality l
Assurance Criteria for Nuclear Power Plants and fuel Reprocessing i
Plants", including the requirements of applicable NRC Regulatory Guides, and ANSI Standards.
\\
4.0 G_ENERAL RE0VIREMENTS 4.1 This Quality Manual is organized to present.the Rancho Seco Quality Program in the order of the 18 criteria of 10CFR50 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.
1 east' annually. Any changes made to this manual tha t do' reduce the commitments previously accepted by the NRC will be submitted l
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 10CFR50.54(a).
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NUMBER:: RSQM-SECTION II RANCHO SEC0 QUALITY MANUAll REVISION:
2 PAGE'2 0F 13 4.2.
'TheRanchoSecoQuaNtyProgramisimplementedbyorganizations responsible for achieving quality _and by_ organizations..
responsible for verifying quality.'.
I 4.3' The Operations Phase Quality Assurance Program applies to 2-activities affecting.the' operation and the quality of safety-1 related structures, s'ystems, components, and services during
)
plant operation, maintenance, testing.and modifications'.
j 2-The Manager, Nuclear Engineering is responsible to develop a-Master Equipment List.(MEL). The MEL is a list of equipment that have been assignedran equipment ID. The'MEL:provides a ready-j 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.
Appropriate elements.of this manual apply to emergency plans,
-radiation protection procedures, radioactive waste shipment programs and fire protection.
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 l
interpretations and exceptions are tabulated in Attachment 2.1 I
and 2.2 of this section.
4.5 The extent to which the Quality Program and its controls are applied'are established as'follows:.
I a.
SMUD uses the criteria specified in Engineering Procedures for identifying structures, systems and components to which j
the Quality Program applies; i
l 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
^
described in this manual'are applied to safety-related items.
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1 NUMBER:
RSQM-SECTION II RANCHO SEC0 QUALITY HANUAL REVISION: 2 PAGE 3 0F 13 I
4.6 Safety-related activities are accomplished under controlled conditions. Preparations for such activities include confirmation that prerequisites have been met.
Development, control, and use of computer programs affecting 4.7 nuclear power plant safety-related design and operation are subject to appropriate controls.
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 l
qualifications to perform the assigned tasks.
)
i 4.9 Quality Program:
Policy / Procedures / Instructions The Quality Program is documented by written Rancho Seco l
a.
policies, procedures, and instructions.
The overall-policies and general requirements are outlined in the Rancho Seco Quality Manual.
Specific details related to 1
implementation of the established quality policies are 2-~
contained in the Rancho Seco Procedures. Additional l
implementing procedures shall be prepared as required by the
{
organizations responsible for performing the function.
The j
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.
2--
b.
The Director, Nuclear Quality is responsible for the preparation, issuance, and control of the Rancho Seco 1
2--
Quality Manual.
c.
Proposed changes to the Quality Manual shall be reviewed and 2-+ -
approved by the Director, Nuclear Quality and the CEO, 1
Nuclear.
Requests to revise any portion of this manual 2-shall be submitted in writing to the Director, Nuclear-l Quality.
d.
The Rancho Seco Quality Manual, including any changes, supplements, or attachments, is issued and maintained as a controlled document.
2-e.
Rancho Seco Quality Manuals are assigned by the Director, Nuclear Quality 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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l NUMBER:- RSQM-SECTION II RANCHO SEC0' QUALITY MANUAL REVISION: 2
'PAGE 4 0F 13 2-4'10 Resolution of Differences.
The provisions. delineated in'the' Rancho Seco Quality Manualushall 7
take.prepedence over differing-Quality requirements specified-in-other. departmental: procedures.until, the Director, Nuclear Quality-has evaluated-the' issue and~ determined which. requirement (s) are:
to be. modified.
i Questions on disputes. involving. interpretation of the requirements:or implementation of this manual must;be referred to:
the. Director, Nuclear Quality for resolution and/or initiating changes to commitments or procedures as.necessary to-resolve 'the differences.-
p 4.11 Packaging and Transportation of Radioactive Material i
This-Quality Program.shall be applied to packaging and transportation of. radioactive. material as.specified in' Ref. 2.4. 4 5.0 RESPONSIBILITIES General organizational responsibilities are ' described in Section I, ORGANIZATION.
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NUMBER: RSQM-SECTION II RANCHO SECO QUALITY MANUAL REVISION:
2 PAGE 5 0F 13 I
ATTACHMENT 2.1 REGULATORY COMMITMENTS f
-)
SMUD commits to the requirements of the regulations and. industry standards I
listed below with any exceptions identified in Attachment 2.2.
f p_QCJ) MENT REVISION /DATE TITLE 1
2--
- 1. Reg. Guide 1.8 Personnel Selection and Training j
g
- As referenced in the Tech. Spec.
l
- 2. Safety Guide 28 6/7/72 Quality Assurance Requirements ANSI N45.2 71 for Nuclear Power Plants i
- 3. Reg. Guide 1.28 8/85 Supplementary Requirements for f
ANSI /ASME NQA-1 83 Quality Assurance Records (See Supplement 17S-1 exception No.1 in Attachment 2.2).
4 Safety Guide 30 8/11/72 Quality Assurance Requirements i
l ANSI N45.2.4 72 for the Installation, Inspection, and Testing of Instrumentation and Electrical Equipment (See exception No. 2 in.2) 4 2--
- 5. Reg. Guide 1.33 Administrative Controls for Nuclear Power Plants
- As referenced in the Tech. Spec.
- 6. Reg. Guide 1.37 3/16/73 Quality Assurance Requirements for l
ANSI H45.2.1 73 Cleaning Fluid Systems and Associated Components of Hater-Cooled Nuclear Power Plants (See exception No. 3 in Attachment 2.2)
- 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 l
Nuclear Power Plants (See exception No. 8 in Attachment 2.2)
- 8. Reg. Guide 1.39 3/16/73 Housekeeping Requirements for Water-ANSI N45.2.3 73 Coo' led Nuclear Power Plants (See exception No. 4 in Attachment 2.2) l
J N'JMBER:
RSQM-SECTION II l
RANCHO SECO QUALITY MANUAL REVISION:
2 i
PAGE 6 0F 13 ATTACHMENT 2.1 (Continued)
QQCUMENT 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 Personnel (See exception No. 5 in.2)
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 2.2)
- 12. Reg. Guide 1.74 2/74 Quality Assurance Terms and ANSI N45.2.10 73 Definitions (See exception No. 7 in.2)
- 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 l
ANSI N45.2.8-75 Installation, Inspection, and Testing of
-l Mechanical Equipment and Systems l
- 15. Ref. Guide 1.120 11/77 Fire Protection Guidelines for Nuclear Power Plants l
1
- 16. Reg. Guide 1.123 7/77 Quality Assurance Requirements for ANSI N45.2.13 76 Control'of Procurement Items and Services f
for Nuclear Power Plants
)
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- 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 ANSI N45.2.23 78 Program Audit Personnel for Nuclear Power j
l Plants 3
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NUMBER:
RSQM-SECTION II RANCHO SEC0 QUALITY MANUAL REVISION: 2 PAGE 7 0F 13 ATTACHMENT 2.2 i
4 EXCEPTIONS I
EXCEPTION NO. 1:
Reg. Guide 1.28/NQA-1, Supplement 17S-1 SMUD complies with the recommendations of this regulatory guide with the following clarifications:
Hith regard to Section 2.4 of Supplement 175-1 titled Index:
The phrase "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 j
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 documented.
With regard to Section 4.3, Supplement 17S-1 titled Safekeeplag:
l Routine general office and nuclear site security systems and access 1
controls are provided: No special security systems are required to be established for record storage areas.
l With regard to Section 4.4, Supplement 175-1, titled Facility:
This l
Section provides no distinction between temporary and permanent facilities. To cover temporary storage, the following clarification is added:
" Active records (those completed but not yet duplicated or placed on microfilm) may be temporarily stored in one-hour fire rated file cabinets.
In general, records shall not be maintained in such 2- -
temporary storage for more than four months af ter completion without being duplicated (for dual storage) or being placed on microform.
Open-ended documents those 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, master j
i cumulative in nature (e.g. nonconforming item logs and control room log 1
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 I
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 document control as a " record" (e.g. training and j
qualification records).
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7 NUMBER: zRSQM-SECTION II RANCHO SEC0 QUALITY MANUAL REVISION:
2
'PAGE 8 0F 13 j
ATTACHMENT 2.2 -(Continued)'
EXCEPTION NO. 2: RG 1.30/ ANSI N45.2.4 '
Specific clarifications for' ANSI.N45.2.4 - 1972 are indicated below by' sections.
s
'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
.l SMUD commitment to Regulatory Guide 1.74.
Section 2.1 Plannina requirements, as determined by engineering, i
shall be incorporated into modification procedures _.
Section 2.3 Procedures and Instructical shall be implemented as setL forth in Sections II, III, V, X and XI of this. program i
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 as sat forth in.this table 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).
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..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 idantify equipment which is out of calibration.
Lack of a sticker-shall require record review and affixing a new sticker based on calibration data. H&TE and reference standards shall comply with sentonces 2, 3 and 4.
l NUMBER:
RSQM-SECTION II
' RANCHO SEC0 QUALITY MANUAL-REVISION:
2 p
PAGE 9 0F 13 ATTACHMENT. 2.2 - (Continued)
EXCEPTION N0. 2:
RG 1.30/ ANSI N45.2.'-73 (Continued) 4 Nithrespect'tothethird' sentence,SMUDuniquely identifies. each safety-related component 'of permanently installed process instrumentation.
This identification l
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 Erroastruction 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.-
l equivalent controls are assured by compliance.with L
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 Inspections, 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 l
implemented as set forth in Sections III and XI of this program. In some cases Surveillance testing may be used.
l to meet the appropriate requirements of this.section.
Section 6 Epst-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'wil1~be used in the development' and implementation of inspection and testing programs as descr_ibe 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.
NUMBER:
RSQM-SECTION II RANCHO SECO QUALITY MANUAL REVISION:
2 PAGE 10 0F 13 ATTACHMENT 2.2 (Continued)
EXCEPTION NO. 3:
RG 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:
Hith regard to Paragraph C.3 of Regulatory Guide 1.37: The water quality for final flushing of fluid systems and associated components shall be at least equivalent to the 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 materials and couplants, dessicants, 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 i
as basic and essential chemical constituents.
no more than 0.1 percent
]
l (1,000 ppm) halogens will be allowed where such elements are leachable j
or where they could be released by breakdown of the compounds under I
expected environmental conditions.
I Hith regard to Section 5 of ANSI N45.2.1 - 1973 titled Installation l
ChanjAg: The recommendation that local rusting on corrosion resistant j
alloys be removed by mechanical methods is interpreted to mean that local rusting may be removed mechanically, but the use of other removal j
means is not precluded, as determined by engineering or Chemistry.
EXCEPTION N0. 4:
RG 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 l
N45.2.10 will be used as clarified in SMUD's commitment f
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1 NUMBER:
RSQM-SECTION II.
RANCHO SECO QUALITY MANUAL.
REVISION: 2 PAGE 11 0F 13 ATTACHMENT 2.2 (Continued) i
. EXCEPTION NO. 4: RG 1.39/ ANSI N45.2.3-73 (Continued)
/
Section 2.1 Planhina:
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.
clean 1iness commensurate with program requirements in'the' 1
areas of housekeeping, plant and personnel safety,.and -
. fire protection.
Cleanliness will be maintained, consistent with the work
)
l being performed, so as to prevent the entry of foreign l
material into safety-related systems.- This:will include,.
as a minimum, documented-cleanliness.in'spections 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
- 1 be established when the reactor system is opened for-inspection, maintenance," modification. or repair.
1 i
Additional housekeeping requirements will be implemented as required for^ control of radioactive contamination.
L Section 2.2 Procedures and Instruction: Appropriate procedures will be written and implemented.
Section 3.2 Control of Facilities:
SMUD may choose not to utilize l
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.
L Cleanliness will be maintained,' consistent with the work l-l being performed, so as to prevent the entry of foreign material into safety-related systems.
This will include, l
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 suppl.ies will 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, i
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NUMBER:
RSQM-SECTION II RANCHO SEC0 QUALITY MANUAL REVISION:
2 PAGE 12 0F 13 ATTACHMENT 2.2 (Continued)
EXCEPTION NO. 5:
Reg. Guide 1.58/ ANSI N45.2.6 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 2-testing procedures is performed by designated individuals from the Quality Assurance Department.
EXCEPTION NO. 6: Reg. Guide 1.64/ ANSI N45.2.11 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, provided:
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:
RG 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 cctivities 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)."
1 NUMBER:
RSQM-SECTION II RANCHO SEC0 QUALITY MANUAL REVISION: 2 i
PAGE 13 '0F 13
)
i ATTACHMENT 2.2 (Continued)
EXCEPTION NO. 7 (Continued)
I 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 givea above.
" Independent Verification": - Verification by an individual other than 4
the person who performed the operation or activity being verified that 2-required actions have been completed.
Such verification may not necessarily require confirmation of the action at the physical location if adequate remote indication of completion of action.is available.
In determining the acceptability of remote verification, the consequences of the action not being 1001, completed and the validity of the remote indication for confirming the completion of the desired action will be 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 4
the required panel-meter indicated value; verification that a valve has been positioned by observing the starting or stopping of flow on meter indications or by remote valve positions indicating lights.
"Will" - (Not define; 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:
RG 1.38/ ANSI N45.2.2 Section 2.7 Classifhation of Items - SMUD may choose not to utilize the four level classification of items, but will address packaging and storage requirements for items based on the needs of individual items and manufacturers recommendation.
NUMBER:
RSQM-SECTION III RANCHO SECO QUALITY MANUAL REVISION: 2 PAGE 1 0F 5 III.
DESIGN CONTROL 1.0 EURREQSE f This section describes the Quality Program measures established for control of design activities affecting safety-related 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 10CFR50, Appendix B, Section III, " Design Control" 2.2 10CFR50.49, " Environmental Qualification of Electrical Equipment" 2.3 10CFR50.59, " Changes, Tests and Experiments" 2.4 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.
2.5 ANSI N45.2, Section 4, " Design Control" 3.0 EOLICY The requirements specified in this section apply to all organizations performing design functions for modifications, changes, replacement or addition of safety-related structures, systems or components at Rancho Seco.
1
' NUMBER:.RSQM-SECTION III RANCHO SEC0 QUALITY MANUAL REVISION: -2 4
PAGE 2._QF 5 4.0 KN_ERAL RE0VIREMENTS Procedures shall be established.an'd executed to control design activities. ' Procedures covering design control activities shall-include the following-requirements::
t 4.1 Applicable design inputs such as design' bases, regulatory o
requirements, codes and standards, methodology and'.all!
assumptions with appropriate justifications are identified, documented and correctly translated;into' design output documents such'as specifications,' drawings, procedures or instructions.
' 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 j
suitable materials, ~ parts, equipment,- and processes ufied in.
meeting applicable safety-related requirements for structures, systems and components shall be described.
Materials, parts, components and equipment which areistandard,:
commercial (off-the-shelf),or which require envir'onmental i
qualification,'er which hav,e been previously approved for other similar applications are reviewed for suitability and.
y appropriately classified; Systematicmethbdsareestablishedfor.communicatingand 4.4 c.ontrolling the flow of related design information.across the external and internal design interfaces, including any changes to the design?information as the work progresses.-
4.5 Interfaces between the Nuclear Engineering Department 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.
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NUMBER:
RSQM-SECTION III RkkCHOSECOQUALITYMANUAL REVISION: 2
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PAGE 3 0F 5 m
4.7 Verifying or c6ecfikg the adequacy of design for modifications or changes performed. Acceptable verification methods include, but ard not limited to design reviews, alternate calculations or qualification testing.
If a tat 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, j
4.8 Computer program codes used for deign calculations are certified j
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
/
'strformed by the originator's supervisor provided the suptrvisor ib the only technically qualified individual available and meets t'M appropriate clarification provisions of Ref. 2.4.
The lt results of the design verification efforts must be documented y
with the identification of the verifier clearly provided.
4.10 Provisions are specified for the control of de' sign analyses such as reactor physics, stress, thermal, hydraulic, and accident; l
l compatibility of materials; accessibility for inservice i
inspection, maintenance, and repair; and delineation of j
acceptance criteria for inspections and tests.
i 4.11 Design problems which are identified during field installation or testing activities shall be documented and forwarded to the Nuclear Engineering Department for evaluation and resolution.
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4.)2 Design and specification changes, including, field changes.
l receive the same degree of control andc approval as the original 1
design unless another qualified, responsibic organization is spe.cifically designated.
4.13 Errors and deficiencies in the design process, including corputer programs. that could adversely affect safety-related structures, systems or components are documented and corrective action,is taken to preclude repetition.
(
e 4.14 Proposed modifications or design thanges which involve an unreviewed safety question or a change to the Rancho Seco l
/
Technical Specifications are handled in accordance with the I
requirements of 10CFR50.59.
2-4.15 Modifications are reviewed by plant personnel for effect on plant operation prior to making the modification operational.
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i HUMBER: USQM-SECTION III R$UCHOSECOQUALITYMANUAL REVISION: (2 L
PAGE 4 OL5, l
t A J ti Design documents are reviewed for accessibility of equipment and i i components for inservice inspection, tests, maintenance or modi fications.
t 2-4.17 Design and/or test documentation must be obtained fron all M
seppliers on procurement of safety-related ASME code components used for replacement or modification to Rancho.Seco.
5.0 RESPONSIBILITIES Genercl organizational responsibilities are describe in Section I, ORGANIZATION.
e 2-5.1 Manager, Nuclear Engineering is responsible for implementing a design control process per this section and tu?
3 a.
Provide and control design ch a ge packages.
b.
Optimize nuclear fuel value and reactor safety by managing fuels management and core analysis, c.
Ensure Integrity and regulatory conformance of configuration control.
d.
Provide plant configuration control including establishing and maintaining baseline documents.
Provide computer engineering support for plant' computers, 3
e.
IDADs, training simulator, etc.
J f.
Perform probabilistic analysis in support of plant des 31n.
g.
Provide engineering support to huclear Power Productio[.
i b.
Provide and maintain engineering procedures, standards and 2--
specifications and drawings.
t
- 1.
Provide technical support to maintaitithe: training simulator operable and within plant co fig'uration.
2-j.
Preparation / Maintenance of Master Equipment List described in Section II.
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NUMBER:
RSQM-SECTION III RANCHO SECO QUALITY MANUAL REVISION: 2 PAGE 5 of 5 2-~
5.2 The Director, Nuclear Quality is responsible for:
a,
' Review and concurrence of design control procedures, i
b.
Monitoring implementation of the Design Control Program.
' 2 -+ -
c.
Auditing the Design Control. Program per Section XVIII of this manual.
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NUMBER:
RSQM-SECTION IV RANCHO SEC0 QUALITY MANUAL REVISION: 2 l
PAGE 1 0F 4 IV.
PROCUREMENT DOCUMENT CONTROL l'. 0 EUREQSEf R
This section describes the Quality Program measures established to control procurement documents for safety-related material, I
equipment and services at the Rancho Seco Nuclear Generating Station.
l 2.0 REI.1RENCE DOCUMENTS l
2.1 10CFR50, Appendix 8, Criterion IV, Procurement Document 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 l
Nuclear Power Plants 3.0 POLICY i
Procurement documents for Rancho Seco safety-related 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 REQUIREMENTS 4.1 Procedures shall be established and implemented to control the preparation, review, approval and issuance of procurement documents.
l
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l NUMBER:
RSQM-SECTION IV RANCHO SECO QUALITY MANUAL-
. REVISION:' 2 PAGE 2 0F 4 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 thereto, that describe the.
items.or services to be furnished.
c.
Identification:of test, inspection and acceptance
'l l
requirements,'and any special instructions and requirements for such activities' as design,l fabrication, identification,-
)
i cleaning, erecting, packaging, handling, shipping and extended storage, d.
Identification of applicable QA Program criteria, r
e.
Applicability of 10CFR21.
q f.
Identification of'the d' documentation, such as drawings, specifications, procedures,. fabrication and inspections.
plans, inspection and test records, personnel and procedure qualifications, and chemical and physical test reports to be prepared and maintaine'd 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.
Extension of applicable requirements to lower tier subcontractors and suppliers, including SMUD's r,1ght of i
access to facilities and records, j.
Supplier submittal of nonconforming items and SMUD approval for " Accept-as-is" or " Repair" dispositions of nonconformances.
- _ = _ _ _ _
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NUMBER:
RSQM-SECTION IV l
RANC110 SEC0 QUALITY MANUAL REVISION: 2 PAGE 3 0F 4 4.2 (Continued) 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 I
documented and available for verification.
I 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; I
that there are adequate acceptance and rejection criteria; that i
l the procurement documents have been prepared,' reviewed and 1
approved in accordance with the requirements of the established; i
procedures.
I l
4.5 Purchasing Department shall verify that the supplier is on the j
Approved Suppliers List (ASL).
l 4.6 Revisions to procurement documents shall receive an equivalent i
review and approval as the original documents.
Exceptions to this include changes in quantity, estimated price, cost co' des, taxes, format or editorial changes that do not affect the quality of the item or service.
4.7 Procurement documents for spare or replacement parts for safety-related structures or systems shall specify procurement controls l
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 RE_SPONSIBILITIES General organizational responsi'ilities are described in Section I, ORGANIZATION.
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NUMBER:
RSQM-SECTION IV RANCHO SECO QUALITY MANUAL REVISION: 2 PAGE 4 0F 4 5.1 Hanager, Material Control Department is responsible to:
a.
Purchase items in conformance to procurement documents.
b.
Pur# chase safety-related items from approved suppliers.
c.
Arrange for suppliers to be placed on the Approved Suppliers List.
d.
Arrange for source inspection when specified on the
{
2- -
5.2 The Director, Nuclear Quality is responsible for:.
a.
Review and concurrence of material management procedures.
I b.
Review and concurrence of procurement documents.for.
f safety-related items.
l c.
Auditing the procurement program per Section XVIII of this manual.
d.
Developing and maintainirq an Approved Suppliers List.
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NUMBER:
RSQM-SECTION V RANCHO SECO QUALITY MANUAL REVISION:
2 PAGE 1 0F 2 V.
INSTRUCTIONS, PROCEDURES AND DRAHINGS 1.0 PURPOSE f This section describes the Quality 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 DOCUMENIS 2.1 10CFR50, Appendix B, Criterion V, Instructions, Procedures and Drawings i
2.2 ANSI N45.2-1971, Section 6, Instructions, Procedures and Drawings 2-2.3 Reg Guide 1.33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants.
I l
3.0 E0LI_QC l
1 Activities affecting the operational safety or quality l
performance at Rancho Seco shall be described by and implemented l
in accordance with documented instructions, procedures, and drawings.
1 4.0 GENERAL RE0VIREMENTS 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.
1 1
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NUMBER:
RSQM-SECTION V RANCHO SEC0 QUALITY MANUAL REVISION:
2 PAGE 2 0F 2 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.
5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
5.1 The managers of each department are responsible to assure that activities affecting quality performed by their departments are described in instructions, procedures and drawings.
2-~
5.2 The Director, Nuclear Quality is res'ponsible to perform 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.
1.
i NUMBER: :RSQM-SECTION VI RANCHO SECO QUALITY HANUAL-REVISION:
2-PAGE 1 0F 3-VI, DOCUMENT CONTROL-.
l 1.0 PURPOSE p This section_ describes the Quality Program measures established for the issuance and c~ontrol of documents that control: activities affecting quality at the Rancho Seco Nuclear Generating Station.
l.
2.0 REFERENCE DOCUMENTS 2.1 10CFR50, Appendix. 8, Criterion VI, Document Control 2.2.
ANSI N45.2-1971, Section 7, Document Control 3.0 POLICY I
Applicabledocuments,includingchanges'th'ereto,thatLprescribe activities affecting the quality-operation at Rancho Seco~shall be issued and controlled in a manner: that precludes the use of inappropriate or outdated documents.
4.0 GENERAL REQUIREMENTS 4.1 Procedures shall be established for review',' approval,' issue,
~
change and use of documents in the following categories:
a.
Design documents (e.g., calculations, drawings, specifications, analyses) including documents related to computer codes; b.
As-built drawings, procedures and related documents; c.
Instructions and procedures for activities such as:
fabrication, construction, modification.. installation,.
inspection, test and station maintenance and operation; e.
ProceduresthatimplementthequalityLassurance' program; a
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I NUMBER:
RSQM-SECTION VI I
RANCHO SEC0 QUALITY MANUAL REVISION:
2 l
PAGE 2 0F 3 4.1 (Continued) f.
Final Safety Analysis Report; j
i i
g.
Updated Safety Analysis Report; h.
Reports of nonconformances; l
i.
Technical Specifications; 2- -
j.
Master Equipment List j
4.2 Procedures which establish the review, approval, issue, change and use of documents shall include as appropriate:
l Criteria to ensure that adequate technical and quality i
t a.
requirements are incorporated prior to implementation; l
t b.
Organizations responsible for review, approval, issue and revision; Provisions for a review for concurrence with quality c.
assurance-related aspects by the Quality Department; I
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 i
procedures.
4.3 Controlled documents, including changes, are issued and distributed to the organizations identified on the applicable distribution list so that:
The documents are available as required at the work location a.
prior to commencing work; and b.
Obsolete or superseded documents are removed from work areas and replaced by applicable revisions in a timely manner.
4.4 Master lists or equivalent means are used to identify the current revision of controlled document. When master lists are used, they are updated and distributed to designated personnel who are responsible for maintaining current copies of the lists.
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RSQM-SECTION VI I
RANCHO SEC0 QUALITY MANUAL REVISION: 2 PAGE 3 0F 3 3
1 5.0 RESPONSIBILITIES j
u General organizational responsibilities are described in Section I, ORGAN,IZATION.
5.1 Hanager, Cost Control and Office Services Department is i
responsible to develop and implement a document control program 2-in accordance with this section.
1 5.2 The Director, Nuclear Quality is responsible for-a.
Review and concurrence of document control procedures.
i 2-b.
Review and concur with procedures, instructions or documents that implement the Nuclear Quality Program to ass *Jre compliance with the applicable provisions of this manual.
c.
Auditing the document control program per Section XVIII of j
this manual.
4
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NUMBER:
RSQM-SECTION VII-RANCHO SEC0 QUALITY MANUAL l REVISION:
2-PAGE 1 0F 4 VII.
CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES o.
1.0 PURPOSE f
-This section describes'the Quall'ty Program measures established =
l to assure that safety-related material, equipment and. services i
purchased for the Rancho Seco Nuclear: Generating Station conforms to the procurement documents.
2.0 REFERENCE DOCUMENTS-2.1 10CFR50, Appendix B, Criterion VII, Control of Purchased Material, Equipment, and Services 2.2 ANSI ~N45.2-1971, Section 8, Control of Purchased Material, l
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
'l Power Plants q
3.0 POLICY Measures shall be established to assure that' safety-related material, equipment and services conform to the specified.
j requirements of the related procurement documents.
]
4.0 GENERAL REQUIREMENTS 4.1 Control of purchased material, equipment and services shall include the following, as appropriate:
a.
Source evaluation and selection of suppliers.
l b.
Objective evidence of quality furnished by the supplier.
c.
Source inspection, a~udit, and/or surveillance activities.-
I d.
Examination of items or services upon delivery or completion.
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R$QM-SECTION VII RANCHO SECO QUALITY MANUAL REVISION: 2 PAGE 2 0F 4 4.2 Source evaluation and selection of suppliers shall be based on one or more of the following criteria:
a.
An pvaluation of the Supplier's QA Program / Manual / Procedures, b.
Review and evaluation of historical quality performance data.
1 c.
Supplier audits by SMUD or by utility groups to which SMUD 3
- belongs, j
d.
Coordinating Agency for Supplier Evaluation (CASE) Registry e.
Utilities holding Nuclear Plant Operating Licenses I
f.
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 the Quality Assurance Department.
4.3 Procedures for control of materials, equipment and services shall address the following:
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 organization responsible for implementing the inspection.
I 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 reports or l
2-other means specified by the Director, Nuclear Quality.
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NUMBER:
RSQM-SECTION VII RANCHO SEC0 QUALITY MANUAL REVISION:
2 PAGE 3 0F 4 4.3 (Continued) d.
Receipt inspection of supplier furnished items to assure:
(1)f the proper identification of items on the receiving l
documentation, (2) that the items are inspected and judged i
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-a prior to installation or use of i:he items, and (4) that items accepted and released are identified as to their I
inspection status prior to storage or use.
]
4 e.
Review, acceptance, and maintenance of records to assure
. l adequacy of documentation that identifies the purchased item, and that specific procurement requirements (e.g.,
codes, standards, specifications) have been met or satisfied, f.
Review and approval of documentation required to be submitted by the procurement documents (CMTR's, C of C, y
Procedures, Specifications, etc.).
1 g.
Procurement control of spare or replacement parts for safety-related systems to assure compliance with 1
i requirements that are equivalent to the.. original item, or those specified by a properly reviewed and approved revision f
to the original requirements.
l l
i 5.0 RES_PQRSIDIJJ_ TIES General organizational responsibilities are ' described in Section I, ORGANIZATION.
5.1 Manager, Material control is responsible to:
i a.
Ensure quality and qualifications of parts and materials by l
managing definition of quality specifications, and storage l
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.
9
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NUMBER: RSQM-SECTION VII RANCHO SECO QUALITY MANUAL REVISION: 2 j
PAGE 4 0F 4 l
l 2--
5.2 The Director, Nuclear Quality. is responsible for:
a.
Developing and maintaining an Approved Suppliers List.
-l b.
Performance of required inspections, evaluations, and audits.
c.
Review and concurrence with material control procedures.
d.
Auditing the Material Control Program in accordance with Section XVIII of this manual.
i
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1 NUMBER: RSQM-SECTION VIII RANCHO SEC0 QUALITY MANUAL REVISION: 2 PAGE 1 0F 3 VIII.
IDENTIFICATION AND CONTROL OF MATERIALS, PARTS & COMPONENTS 1.0 PURPOSE f This section describes the Quality Program measures established to provide for the identification and control of safety-related material, parts and components for the Rancho Seco Nuclear
-l Generating Station.
l 2.0 REFEREN.CE DOCUMENTS 2.1 10CFR50, Appendix B, Criterion VIII, Identification and Control of Materials, Parts and Components 2.2 ANSI N45.2-1971, Section 9, Identification and Control of l
Materials, Parts and Components j
l i
3.0 E011CX j
t 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 1
items.
i 4.0 GENERAL RE0UIREMENTS 4.1 Safety-related materials, parts or components, including I
partially fabricated subassemblies and consumables, shall be identified such that they can be related to their applicable i
drawing, specification, purchase document and inspection records at any stage from initial receipt through fabrication / construction, installation, repair, modification or j
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.
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NUMBER:
RSQM-SECTION VIII RANCHO SECO QUALITY MANUAL REVISION:
2 PAGE 2 0F 3 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.
4.5 When specified by codes, standards, procurement documants, or other requirements, identification is required 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.
I 4.7 Markings shall be transferred to each part of an item, if l
subdivided. The markings'shall not be obliterated or hidden by i
surface treatment or coatings unless other means of l
identification are substituted, j
4.8 Procedures are required to provide for the verification and
-l documentation of correct' identification of items prior to release r
for use.
Items may be conditionally released under adequate l
procedural controls.
4.9 Bulk consumables (such as weld rod, chemicals, reagents, 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 handled in accordance with Section XV of this manual.
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NUMBER:
RSQM-SECTION VIII RANCHO SEC0 QUALITY MANUAL REVISION:
2 PAGE 3 QF 3 l
RESP 0NSIBILITIES P
5.0 General organizational responsibilities are described in Section I, ORGANIZATION.
j 5.1 Manager, Material Control is. responsible for maintaining I
identification and control from procurement of items through i
storage and issuance for installation.
{
5.2 Manager, Maintenance Department is responsible to assure that identification and control of items from warehouse withdrawal 1
through installation is maintained.
{
5.3 Manager, Modifications Department is responsible to assure that identification and control of material, parts, and components is maintained during modification activities.
2- -
5.4 The Director, Nuclear Quality is responsible for:
a.
Review and concurrence of procedures for controlling material, parts and components from procurement through storage, issuance and installation.
1 b.
Auditing the process for identification and control of materials, parts and components in accordance with Section XVIII of this manual.
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NUMBER: RSQM-SECTION IX
'l RANCFIO SECO QUALITY MANUAL :
. REVISION:
2~
PAGE 1 0F 2 IX.
CONTROL OF SPECIAL PROCESSES 1.0 PURPOSE /
This:section describes the Quality.Pyogram measures established to govern special. processes used.at the Rancho Seco. Nuclear
- Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10CFR50, Appendix B,' Criterion IX, Control of.Special Processes 2.2 ANSI N45.2-1977, Section 10, Control of Special Processes' 2.3 ASME Section IX 3.0 EQLLCX Procedures shall be established and implemented to assure that-special processes,;and. equipment are controlled and that.the j
activities.are accomplished by qualified. personnel and procedures.
i 4.0 GENERAL REQUIREMENTS 4.1
- Procedures shall be prepared to provide for proper control of special processes, which include welding, heat treating, chemical l
cleaning, application of protective coatings and nondestructive examination (NDE).
i 4.2 Controls shall be es'tablished to assure that only approved materials and equipment are used to perform special processes.
j 4.3 Personnel who perform special-processes shall be trained and qualified in accordance with industry _ standards.
4.4 Special process requirements shall be prescribed in 'the l
controlling specifications, drawings, procurement documents or i
procedures.
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____1_
NUMBER: RSQM-SECTION IX RANCHO SEC0 QU^LITY MANUAL REVISION: 2 PAGE 2 0F 2 5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
5.1 Hanager, Nuclear Engineering is responsible for specifying the
{
special processes on design documents governing maintenance / modifications activities.
5.2 The Manager, Maintenance Department is responsible for:
Developing, qualifying, and maintaining special process a.
procedures other than HDE procedures.
b.
Qualifying personnel to perform special processes other than NDE.
2-5.3 The Director, Nuclear Quality is responsible for:
[
Developing, qualifying and maintaining NDE Procedures.
a.
b.
Review and concurrence of other special process procedures.
c.
Qualifying personnel to perform NDE.
d.
Performing NDE.
Auditing the special process program in accordance with e.
Section XVIII of this manual.
i 5.4 The Manager, Modifications Department is responsible for:
Developing, qualifying, and maintaining special process a.
procedures other than NDE procedures.
b.
Qualifying personnel to perform special processes other than l
NDE.
)
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e NUMBER: RSQM-SECTION X l
RANCHO SEC0 QUALITY MANUAL REVISION: 2 l
PAGE 1 0F 4 l
I X.
INSPECTION 1
1.0 EUREQSE f This section describes the Quality Program measures established to provide for the inspection of safety-related material, parts and components for the Rancho Seco Nuclear Generating Station.
I 2.0 REFERENCE DOCUMENTS j
2.1 10CFR50, Appendix 8, 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.
2-2.4 Reg Guide 1.33/ ANSI N18.7, Administrative Controls for Nuclear i
Power Plants 2.5 ASME Code,Section XI
)
l 1
3.0 E0LICY Procedures shall be established and implemented to assure that inspections are performed to verify compliance with specified requirements at Rancho Seco.
4.0 GENERAL REQUIREMENTS 4.1 Inspections shall be applied to receiving, maintenance, and modifications to verify that items and activities conform to specified requirements.
In addition, a program for required inservice inspection of completed systems, structure and components shall be established and implemented.
. NUMBER:
RSQM-SECTION X-RANCHO SECO QUALITY MANUAL REVISION: PAGE 2 0F 4 '
4.2 Inspection planning documents shall.be prepared or reviewed byj the Quality Assurance Department in accordance with; established-procedures.
Inspection planning documents.shall identify the.
followingeas 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; 1
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 inspection alone,is impractical or inadequate.
Both-inspection and. process monitoring are performed when control is inadequate without both.
4.4 Training and qualification of personnel who perform inspections, including NDE, shall be performed in accordance with. approved i
procedures.
I 4.5 Hold points are designated as mandatory inspection points when l
confirmation'is needed that the work at the. point is acceptable j
before additional work can proceed.. Hold point inspections are
{
performed, and; work is released for further processing or use,' by J
authorized personnel.
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 acceptability of the
]
item or work, i
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NUMBER: RSQM-SECTION X.
RANCHO SECO QUALITY MANUAL REVISION: 2 i
PAGE 3 0F 4 4.7 Inservice inspection and testing is performed and documented in accordance with a program of examinations, tests, and inspections-of plant components and systems. An Authorized Nuclear Inservice-Inspector, (ANII) is employed to verify that the program is conducted in accordance with ASME code requirements.
4.8-Inspections are performed by Quality Assurance Department personnel.
4.9 Inspection records shall contain the following where applicable:
a.
Item inspected; b.
The date of the inspection; c.
Inspector or data recorder identification; d.
Identification of M&TE used to perform inspections;
-i e.
Type of observation;
.l f.
Results or acceptability; g.
Reference to information on action taken on nonconformances to resolve any discrepancies noted.
5.0 Ef1 POSSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
2-5.1 The Director, Nuclear Quality is responsible for:
a.
Qualifying Quality Control Inspectors, b.
Developing inspection planning for modification / maintenance activities.
c.
Performing inspections per inspection plans.
L
NUMBER:
RSQM-SECTION X RANCHO SEC0 QUALITY MANUAL REVISION:
2 PAGE 4 0F 4 5.2 The Manager, Maintenance Department is responsible for assuring:
a.
Inspections are performed as required by inspections pl an.ni ng.
b.
Work does not proceed beyond inspector signoffs for hold points.
2-5.3 The managers of each department are responsible for:
a.
Supporting inspection activities.
b.
Providing prompt corrective action to any deficiencies found during the inspection.
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NUMBER:
RSQM-SECTION XI J
RANCHO SECO QUALITY MANUAL REVISION: 2 PASE 1 0F 3 XI.
TEST CONTROL l
l 1.0 EU_BPRSE i This section describes the Quality Program measures established to provide for acceptance and surveillance testing at the Rancho Seco Nuclear Generating Station.
2.0 REFERENCE DOCUMERIS 2.1 10CFR50, Appendix B, Criterion XI, Test Control 2.2 ANSI N45.2-1971, Section 12, Test Control
(
2-2.3 Reg. Guide 1.33/ ANSI N18.7, Administrative Controls for Nuclear l
Power Plants 3.0 EQLLCY Procedures shall be established and implemented to assure that I
required testing to demonstrate that structures, systems and components will perform satisfactorily in service is identified, j
performed and documented.
i 4.0 GENERAL REQUIREMENTS 1
4.1 Tests shall be performed in accordance with procedures and i
criteria that designate when tests are required and how they are i
to be performed. Such testing includes the following:
Qualification tests, as applicable, to verify design a.
i adequacy.
b.
Tests of equipment and components to assure their proper operation prior to delivery or pre-operational tests; Pre-operational tests to assure proper and safe operation of i
l c.
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systems and equipment prior to start-up tests or operations; J
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NUMBER:
RSQM-SECTION XI RANCHO SECO QUALITY MANUAL REVISION: 2 PAGE 2 0F 3 4.1 (Continued) 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.
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; 2--
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.
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NUMBER:
RSQM-SECTION XI
'I RANCHO SEC0 QUALITY HANUAL.
REVISION:
2 PAGE 3 Of 3 4.5 Test recoras 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; e.
Evidence as to the acceptability of the results; and
{
f.
Action taken to resolve any deviations and nonconformances i
]
l noted.
.fq t
5.0 RESSPONS_ISILITI.15 General organizational responsibilities are described in Section
)
I, ORGANIZATION.
i
}
2-5.1 The Director, Nuclear Quality is responsible for:
1 a.
Performance of audits to assure conformance to testing
]
requirements appilcable to safety-related items per Section
{
XVIII of this manual.
]
5.2 Th.e Manager, Plant Performance is resp ~onsible for:
a.
Establishing the procedure for acceptance and surveillance testing.
i b.
Providing personnel to perform the testing and acceptance evaluations.
5.3 The Plant Review Committee is responsible for:
i a.
Review and recommendation of approval / disapproval of the acceptance and surveillance testing.
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NUMBER:. RSQM-SECTION XII-
-r RANCHO SEC0 QUALITY, MANUAL REVISION: 2
).
PAGE 1 0F 3-
'I XII.
CONTROL OF MEASURING'AND TEST EQUIPMENT y
EUkP_0SE/
P v
L 1.0 This section describes.the Quality ' Program measures established to provide for the control of measuring and' test equipment at the
\\M-Rancho Soco Nuclear Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10CFR50, Appendix B, Criterion XII, Control of Measuring 'and Test p
Equipment I
2.2 ANSI.N45.2-1971, Section 13, Control of Measuring and Test C
Equipment 2-2.3 Reg. Guide 1.33/ ANSI N18.7, Administrative Controls for Nuclear Power Plants.
< q' 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 i.ntervals to maintain. the desired accuracy.
4.0 (
ftf1ERAL RE0UIREMEHJS C
4.1 Procedures shall be established for calibrtition, maintenance and control of measuring and test equipment' utilized in the operation, measurement, inspection or monitoring of items.
4.2 Measuring and te:t equipment shall be uniquely identified and
-' shall be traceable to its calibration test datJ..
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i NUMBER:
RSQM-SECTION XII RANCHO SEC0 QUALITY MANUAL 2
REVISION:
2 PAGE 2 0F 3 4.3 L$belsshallbeattachedtomeasuringandtestequipmentto 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.
4.4 Heasuring and test equipment dhall bcecalibrited at specified intervals.
These intervals are tMed on the amount of use, stability, chetacteristics and othes' conditions that could adversely affect the required neasdrement 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 f
document the basis for calibration.
?
4.5 M&TE shall be calibrated from reference standards with an accuracy ratio of at least four-to-one (referer1ce standard to i
M&TE). Calibration accuracy ratios of less than 4.0 but equal to or better than 1.0,(Reference standard to M&TEhshall be acceptable when equ4 dent to meet specified rqfirements is not I
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 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 documentet.
47 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 reinspection 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 it found to be out of calibration.
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NUMBER:
RSQM-SECTION XII RANCHO SEC0 QUALITY MANUAL REVISION: 2 PAGE 3 0F 3 5.0 RESEQHSIBILITIIS 1
General organizational. responsibilities'are described in Section I, ORGANIZATION.
5.1 The Manager, Maintenance is responsible for:
a.
Establishing methods for control of test measuring equipment.
b.
Determination of the need for calibrated instruments and l
measuring devices in Rancho Seco activities.
l c.
Providing administrative procedures that address the requirements for calibration.
d.
Control of measurement devices to ensure their use and accuracy.
2-~
5.2 The Director, 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.
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1 NUMBER:
RSQM-SECTION XIII RANCHO SECO OVALITY MANUAL REVISION:
2' PAGE 1 0F 2 I
XIII.
HANDLING, STORAGE AND SHIPPING
.'i l
l 1.0 PURPOSE /
This section describes.the Quality Program measures established to provide for the handling. storage, cleaning and preservation of material and equipment at the Rancho-Seco Nuclear' Generating l
Station.
2.0 REFERENCE'DOCUliMIS.
2.1 10CFR50, Appendix B. Criterion XIII, Handling, Storage and Shipping
?.2 ANSI N45.2-1971, Section 14, Handling,' Storage and Shippingi 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.
l 3.0 L9LLCl Procedures shall be established and implemented to assure _that i
I materials.and equipment'are properly handled, stored, shipped,.
cleaned and preserved to prevent damage or deterioration.
4.0 GMERAL RE0VIRE.BMIS 4.1 Procedures shall be este.blished for assuring that proper handling, storage, shipping and preservation instructions are included in design disclosure documents.
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 decertification for extension of shelf-life.
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NUMBER:
RSQM-SECTION XIll RANCHO SEC0 QUALITY MANUAL REVISION: 2 PAGE 2 0F 2 4.4 Special material handling and preservation instructions shall be developed when required by applicable drawings and/or specifications.
4.6 Marking and labeling of materials for packaging, shipment and storage with the potential for causing contamination or radiation exposure must indicate.the need for special environmental and control.
5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
1 5.1 The Manager, Nuclear Engineering is responsible for:
g l
Establishing methods and procedures to ensure that design a.
documents include handling, storage, shipping, and i
preservation requirements.
5.2 1he Manager, Maintenance is responsible for:
1 a.
Establishing methods for special handling, storage, and preservation during maintenance activities, l
b.
Providing administrative procedures which specify the required controls.
5.3 The Manager, Material Control is responsible for:
a.
Maintaining material control / warehousing control of items and equipment which require special handling and storage.
b.
Providing administrative procedures which specify the required controls.
2-5.4 The Director, 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.
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1 NUMBER:
RSQM-SECTION XIV l
RANCHO SEC0 QUALITY MANUAL REVISION: 2 PAGE 1 0F 2 l
XIV.
INSPECTION, TEST AND OPERATING STATUS i
1.0 LNEEO.SE i l
This section describes the Quality Program measures established to provide for a system to identify the inspection, test and operating status of individual items at the Rancho Seco Nuclear l
Generating Station.
2.0 REFERENCE DOCUMENTS 2.1 10CFR50, Appendix B, Criterion XIV, Inspection, Test and Operati' 3tatus l
2.2 ANSI N45.2-1971, Section 15, Inspection, Test and Operating Status
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3.0 EQLLCX Procedures shall be established and implemented to assure that measures are provided to indicate the status of inspections, tests and operations.
4.0 GMMALREQ!)LR.MMIS 4.1 Procedures shall be written to control nonconforming material, parts and components to prevent their 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.
2-~
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 2-nonconforming items, inoperable systems and components by tags, markings, labels, etc. to prevent inadvertent use.
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NUMBER:
RSQM-SECTION XIV RANCHO SEC0 QUALITY MANUAL REVISION:
2-PAGE 2 0F 2 5.0 RESPONS.IBILITIES i
General organizational responsibilities are described in Section I, ORGANIZATION.
5.1 The Manager, Operations is responsible for:
a.
Control of physical operation of the plant.
b.
Establishing the system for standardized deactivation of l
systems or components.
c.
Clearance procedures to ensure safety of personnel and equipment during maintenance and testing activities.
2-d.
Installation and removal of test and operating status indicators.
5.2 The Director, Nuclear Quality is responsible for:
a.
Identifying the quality status of material, parts, and components.
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O NUMBER:
RSQM-SECTION XV RANCHO SECO QUALITY MANUAL REVISION:
2
- l PAGE 1 0F 2 XV.
NONCONFORMING MATERIALS, PARTS OR COMPONENTS ~
l
.i 1.0 PURPOSE f-
'l
- 1 This section describes the Quality 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.
2.0 REFERENCED DOCUMENTS 2.1 10CFR50, Appendix 8,' Criterion XV, Nonconforming Materials, Parts or Components.
2.2-ANSI N45.2-1971, Section 16, Nonconforming Items 3.0 EQLICY
-l Procedures shall be established and implemented to assure that control of materials, parts or components which do not conform to i
specified requirements are controlled to prevent their l
inadvertent use'or installation.
3 4.0 GENERAL RE0VIREMENTS 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.
.j 4.3 Nonconformances shall be documented, processed. controlled and l
retained to provide records of the action whi.ch was-taken to l
resolve the nonconforming condition.
4.4 Appropriate. levels of management will approve'the' disposition'and 2*
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.
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HUMBER:
RSQM-SECTI0tl XV-rat 1CHO SECO QUALITY MANUAL REVISION: 2 PAGE 2 0F 2 4.6 Trending shall be used as a mechanism for providing management information on the status of nonconforming conditions.
4.7 Honconformances shall be reviewed to determine if they are potentially reportable per 10CFR21.
5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION.
2-5.1 The Director, Nuclear Quality is responsible for:
l l
a.
Establishing methods for controlling and documenting nonconformances.
b.
Serving on the Engineering Review Board.
5.2 The Manager, Nuclear Engineering is responsible for:
a.
Ensuring engineering expertise is available to disposition nonconformances.
b.
Developing safety analyses that. address the nonconforming condition.
c.
Serving on the Engineering Review Board.
5.3 The Director, Nuclear Operations and Maintenance is responsible for:
a.
Taking appropriate action to ensure operation of the program 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.
c.
Ensure prompt closure of nonconformances.
d.
Serving on the Engineering Review Board.
T NUMBER:
RSQM-SECTION XVI RANCHO SECO QUALITY MANUAL REVISION:
2 PAGE 10F 2 XVI.
CORRECTIVE ACTION 1.0 ElLRPOSE f This section describes the Quality 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.
l 2.0 REFERENCE DOCUMENTS l
2.1 10CFR50, Appendix B, Criterion XVI, Corrective Action 2.2 ANSI N45.2-1971, Section 17, Corrective Action 3.0 E01LCY Procedures shall be established and implemented to assure that significant conditions adverse to quality are identified and that corrective action is taken to preclude repetition.
.j 4.0 GMEBAL REQUIREMENTS 4.1 Controls shall assure conditions adverse to quality such as malfunctions, errors, deficiencies or nonconformances are J
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 actior, to remedy the condition and taking action to prevent recurrence.
These actions shall be reported to management personnel for review and assessment.
4.3 Conditions adverse to quality are evaluated to determine if they are potentially reportable per 10CFR21 or 10CFR50.73.
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IlUMBER:
RSQM-SECTION XVI RAtlCHO SEC0 QUALITY MANUAL REVISION: 2 PAGE 2 0F 2 5.0 RESE0.RSlRIllTIES General organizational responsibilities are described in Section I, ORGAN,JZATION.
5.1 The Managers, of each department are responsible for:
a.
Formulation of appropriate corrective actions as they apply to their departments.
b.
Implementation of proposed corrective action.
Assuring that proposed corrective acH on is effective.
c.
2-~
5.2 The Director, Nuclear Quality is responsible for:
J l
a.
Establishing a viable corrective action program.
2--
b.
Verifying the effectiveness of corrective actions.
c.
Providing information to management which describes the effectiveness of the Quality Program.
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NUMBER: RSOM-SECTION XVII RANCHO SEC0 QUALITY MANUAL REVISION:
2 PAGE 1 0F 3 XVII.
QUALITY ASSURANCE RECORDS 1.0 PSEEQSE i This section describes the Quality 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 REIIRENCE DOCUMENTS
-2,1 10CFR50, Appendix B, Criterion XVII, Quality Assurance Records 2.2 ANSI N45.2-1971, Section 18, Quality Assurance Records i
l 2--
2.3 Reg. Guide 1.33/ ANSI N18.7, Administrative Control for Nuclear 1
Power Plants, para 5.2 2--
2.4 RG1.28/ ANSI /ASME, NQA-1-1983, Supplement 17S-1, Supplementary Requirements for Quality Assurance Records with exceptions noted in Section II of this manual.
1 l
3.0 EDLLCX l
1 Procedures shall be established and implemented to assure storage 2-and maintenance of records including those required by Technical 1
Specifications that represent the objective evidence of the quality related activities performed at Rancho Seco.
l 4.0 EENMALRERJREHERIS l
l 4.1 Quality Assurance records shall be retained in a facility that meets the requirements of Ref. 2.4.
4.2 Quality Assurance Records shall be prctected by interim (not to exceed 120 days) storage in NFPA Class C one hour file cabinets rated by Underwriter's Laboratory or equivalent until they are transferred to the Records Information Center for permanent storage.
NUMBER:
RSQM-SECTION XVII RANCHO SECO QUALITY MANUAL REVISION:
2 PAGE 2 0F 3 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 and dated by authorized personnel or.
i 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 (Lifetime or Nonpermanent), retention time, storage location and personnel assigned responsibility for retention and retrievability.
4.6 The conditions of storage shall be established to provide assurance that the records will be useable for the designated period of retention.
4.7 A master documentation system plan shall be established which addresses the requirements of Ref. 2.4 and the of the Technical Speci fications.
5.0 RESPONSIBILITIES General organizational responsibilities are described in Section I, ORGANIZATION 5.1 The Manager, Cost Control & Office Services 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.
5.2 The Managers of each department are responsible for:
Transmitting completed records to Records Management a.
Department.
NUMCER:
RSQM-SECTION XVII RANCHO SEC0 QUALITY MANUAL REVISION:
2 PAGE 3 0F 3 2*
5.3 The Director, 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..
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l NUMBER: RSQM-SECTION XVIII I
RANCHO SECO QUALITY MANUAL REVISION: 2
(
PAGE 1 0F 3 XVIII.
AUDITS J
1.0 EUREQSE f This section describes the Quality Program raeasures established for a comprehensive system of planned and peciodic audits to l
determine the effectiveness of the Quality Program at the Rancho Seco Nuclear Generating Station, I
i 2.0 REFERENCE DOCUMENTS 2.1 10CFR50, Appendix B, Criterion XVIII, Audits
-l 1
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2.2 Reg. Guide 1.33/ ANSI N18.7, Administrative Controls for Nuclear i
i Power Plants 2.3 Reg. Guide 1.144/ ANSI N45.2.12-1977, Requirements for Auditing of l
Quality Assurance Programs for Nuclear Power Plants i
2.4 Reg Guide 1.146/ ANSI N45.2.23-1978, Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants
'2. 5 Technical Specifications, Section 6.0-3.0 EQLLCX 1
Procedures shall be established and implemented to assure that i
planned and periodic audits are conducted-to verify compliance with all aspects of the Rancho Seco Quality Program and Technical Specifications.
4.0 MENE_RAL_ REQ 1IRDiENIS 2- -
4.1 The Director, 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.
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'I NUMBER: RSQM-SECTION XVIII l
RANCHO SECO QUALITY MANUAL REVISION.: 2 l
'PAGE 2 0F-3 l
J 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, proc'urement, modification, maintenance and operational activities at Rancho Seco.
4.4 Audit plans shall be developed which-identify the audit scope,-
the requirements, activities to be audited,. organizations 'to be i
notified, the. applicable documents, the audit schedule, and the
)
audit checklists.
4.5 Audit reports shall be issued which identify the activity whii.h
/
was audited, personnel contacted during the audit, any: findings f
or observations. noted during the ' audit, the organizations.
3 l
responsible for providing the response to audit findings, and the scheduled date for receiving replies to findings identified.
1 4.6 Response to audit findings shall. be prompt, pertinent to the area of concern, and shall address corrective action to prevent i
q i
recurrence.
4.7 Followup action to assure implementation and assess the 1
effectiveness of corrective action shall be taken.. Appropriate 1
followup action shall include review of objective evidence or J
reaudit of deficient areas.
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.
i audits when conditions which may warrant special audits exist.
'l The conditions include:
a.
Significant changes are made in the. quality assurance
- program, b.-
When it is suspected that quality has-been adversely affected.
c.
When an independent assessment of program effectiveness is cor.sidered appropriate.
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1 NUMBER:
RSQM-SECTION XVIII l
RANCHO SECO QUALITY MANUAL REVISION:
2 l
PAGE 3 0F 3 j
l 5.0 RESP _QRSIBILITIES General organizational responsibilities are described in Section
.I, ORGANIZATION.
I 2-~
5.1 The Director, Nuclear Quality'is responsible for:
a.
Establishing a schedule for performance of required audfts.
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.
Tracking of audits to assure prompt response and timely closure of audit findings f.
Preparation of trend analysis data.
2-5.2 The manager of each department are responsible for:
a.
Supporting the audit activities.
l b.
Providing prompt response to any audit deficiencies identified in the audit.
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