ML20203C868
| ML20203C868 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/12/1998 |
| From: | Cruse C BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20203C856 | List: |
| References | |
| NUDOCS 9902120278 | |
| Download: ML20203C868 (74) | |
Text
L 3i QUALITY ASSURANCE POLICY Revision 49 BALTIMORE GAS AND ELECTRIC COMPANY l
7 Quality Assurance Policy for the Calvert Cliffs Nuclear Power Plant
,Y Date_/!/2!98 (1)
Approved
( /
St 4--
V
/
C. H. Cruse
/
Vice President Nuclear Energy Division 9902120278 990208
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DR ADOCK 05000317 p
P DR..
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e QUALITY ASSURANCE POLICY Revision 49 TABLE OF CONTENTS Section Eag!!
1B.1 ORG ANIZATION AND RESPONSIBlLITIES......................................................... 5 1B.2 QU ALITY ASSURAN CE PROGRAM...................................................................... 14 1B.3 DESIGN CONTROL...................................
...... 19 iB.4 PROCUREMENT DOCUMENT CONTROL (5)........................................................... 21 1B.5 INSTRUCTIONS, PROCEDURES, AND DRAWINGS........................................... 24 1B.6 DOCU M ENT CONTRO L...................................................................................................... 2 6 1B.7 CONTROL OF PURCHASED MATERIAL, EQUIPMENT, AND SERVICES (5)............ 28 1B.8 IDENTIFICATION AND CONTROL OF MATERIALS, PARTS, AND CO M PON EN TS (5)......................................................................
.... 31 l
1B.9 CONTROL OF SPECIAL PROCES SES............................................................................ 32 1B.10 INSPECTION..........................................................................................................34 i
IB.11 TESTCONTROL........................................................................................................36 l
1B.12 CONTROL OF MEASURING AND TEST EQUIPMENT........................................... 37 1B.13 HANDLING, STORAGE, AND SHIPPING...........
...... 3 8 1B.14 INSPECTION, TEST, AND OPERATING STATUS....................................................... 39 IB.15 NONCONFORMING MATERIALS, PARTS, OR COMPONENTS (6)..... _ _
. 40 1B.16 CORRECTIVE ACTI ON (6)................................................................................................ 41 1B.17 QU ALITY ASSURANCE RECORDS..................................................................... 42 1B.18 AUDITS...........................................................................
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l QUALITY ASSURANCE POLICY Revision 49 LIST OF TABI FS Table No.
P. age 1B-1 BALTIMORE GAS AND ELECTRIC COMPANY'S POSITION ON........................ 45 GUIDANCE CONTAINED IN INDUSTRY STANDARDS AND REGULATORY GUIDES IISTOF ATTACHMENTS Attachment Letter i
A BASES FOR QA POLICY REVISIONS (1)................................................................... 64 LIST OF FIGURES Figure No.
1B-1 BALTIMORE GAS AND ELECTRIC COMPANY CORPORATE ORG ANIZATION................................................................................. 66 LISTOF ADDENDA Addendum No.
1B-1 REVIEW FUNCTIONS OF THE POSRC, PROCEDURE REVIEW COMMIITEE, QUALIFIED REVIEWERS, AN D OSSRC.
................................................................. 67 Fage 3 of 74 l
QUALITY ASSURANCE POLICY Revision 49 LIST OF EFFECTIVE PAGES Latest revision number is listed for pages revised after revision 38.
Page Last Revision Page Last Revision Page Last Revision 1
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47 28 48 53 47 4
48 29 48 54 48 5
49 30 45-55 41 6
49 31 48 56 41 1
7 48 32 49 57 41 8
49 33 49 58 46 9
49 34 48 59 41 10 49 35 48 60 48 11 49 36 43 61 48 12 49 37 46 62 41 13 49 38 41 63 41 14 48 39 48 64 15 48 40 48 65 47 16 47 41 41 66 48 17 48 42 47 67 49 18 47 43 47 68 49 19 47 44 48 69 47 20 41 45 48 70 47 21 41 46 47 71 47 22 48 47 47 72 47 23 41 48 42 73 48 24 48 49 48 74 47
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,a QUALITY ASSURANCE POLICY Revision 49 1B.1 ORGANIZATION AND RESPONSIBILITIES All levels of organization have definite and unique responsibilities in assuring safe, economical, and i
reliable operation of Calvert Cliffs Nuclear Power Plant (CCNPP). Top level management is responsible i
for ensuring that policies are established, resources are authorized, management philosophy and commitments are communicated to lower levels of the organization, independent verification of management controls are performed, results are reviewed, and appropriate actions taken when aae*===ry.
Middle level management is responsible for translcting management policies, philosophy, commitments, and goals; applicable federal, state, and local rules and regulations; Operating Licenses, Technical i
Specifications (TS), and the Updated Final Safety Analysis Report (UFSAR) into control programs for activities such as design, procurement, construction, testing, operation, refueling, maintenance, repair, 3
modification, training, plant security, fire protecdon, records, independent verification, and corrective i
action. Middle level management is also responsible for defining, measuring, and modifying the overall effectiveness of control programs; taking appropriate action on the results; and keeping top management Informed of the status, adequacy, and effectiveness of control programs, and matters which could have an impact on nuclear safety.
First line craft and non-craft supervisors are individually responsible for ensuring that appropriate procedures are understood and used to implement each activity described in the control programs; identifying problems, seeking solutions, verifying implementation of solutions; investigating root causes of problems and taking preventive actions; ensuring that conditions adverse to plant and personnel safety are promptly identified, reported, and coamed; detecting trends which may not be apparent to a day-to-day observer, recommending generic solutions for adverse trends to management, and,taking appropriate actions, to achieve desired results; ensuring that employees assigned to do a job are properly qualified J
through appropriate training and experience; have properly qualified procedures, tools, equipment, and parts to do the job, and, ensuring that independent inspections of work are conducted in accordance with pre-established requirements. First line non-craft supervisors are responsible to ensure that procedures are written, reviewed, and approved; first line craft supervisors may not have this responsibility. Non-supervisory personnel acting as job directors are responsible for ensuring that properly qualified procedures are understood and used; and ensuring that tools, equipment, and parts are on hand to do the i
job.
Adherence to procedures is vital to the safe and reliable operation of the Calvert Cliffs Nuclear Power Plant. Personnel are responsible for adhering to established procedures, interpreting them conservatively in case of doubt, and recommending changes when necessary. Procedures with the potential to affect nuclear or personnel safety shall be strictly adhered to. When an activity controlled by such procedures cannot be accomplished as described or accomplishment of such activity would result in an undesirable situation, the work shall be stopped and the plant placed in a safe condition. Work shall not resume until the procedure is changed to reflect correct work practices. (1)
Procedures may be deviated from during emergencies to prevent or minimize injury to personnel or damage to plant equipment. Any such deviations should be thoroughly documented. (1)
Coroorate Oromahatian =ad Soecific R*=nancihilities
'!he Corporate Organization Chart of the Baltimore Gas and Electric Company (BGE) is shown in Figure IB-1. Persons responsible for the principal elements of the Company's Quality Assurance (QA) Program are as follows:(1) 1 Chairman of the Board President and Chief Operating Officer i
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I QUALITY ASSURANCE POLICY l
Revision 49 l
Senior Vice President-Oeneration Vice President-Nuclear Energy Division (NED) 1 Plant General Manager-Calvert Cliffs Nuclear Power Plant Department (CCNPPD)
Manager-Nuclear Engineering Department (NED)
Manager-Nuclear Performance Assessment Department (NPAD)
Manager-Nuclear Support Services Department (NSSD) -
Manager-Nuclear Project Management Department (NPMD)
In addition to these individuals, the Vice Presidents of Fossil Energy Division (FED), Electric Interconnection and Transmission Division (EITD), General Services Division (GSD), and the Management Services Division (MSD), as well as the Managers of the System Operation and l
Maintenance Department (SOMD), Purchasing & Materials Management Department (PMMD),
l Information Systems Department (ISD), Facilities and Fleet Services Department (FFSD), Fossil Engineering & Maintenance Department (FEMD),' and the Safety and Medical Services Department (SMSD) are assigned support responsibilities. (1) The thove ivianagers constitute the Nuclear Prog n Managers who are assigned responsibilities within tne QA Program. Other departments performing any maintenance / modification activities at CCNPP are responsible for performing these activities in accordance with applicable QA Program requirements. This can be accomplished by either developing i
I their own QA Program procedures or by working to the QA Program through appropriate Nuclear Energy Division personnel using CCNPP procedures. (15)
Also, two advisory groups perform quality-related functions for plant operations. These are the Plant Operations and Safety Review Committee (POSRC) and the Off-Site Safety Review Committee (OSSRC) whose makeup and responsibilities are described in Addendum IB-1. (19)
Chairman of the Board. Pra=idaat and Chief Oneratina Of&ar.==A Seninr Vice Pra=iAant-Generation l
BGE's QA Program for nuclear power plants is established under the authority of the Chainnan of the Board, President and Chief Operating Officer, and Senior Vice President-Generation, who are l responsible for establishing the overall QA Policy. They assign project responsibilities to the organizations shown in heavy-lined boxes in Figure IB-1. (1)
"Ihe Chairman of the Board assigns authority through the President and Chief Operating Officer and l Senior Vice President-Generation to the Vice President-Nuclear Energy Division.
Primary responsibilities for developing, implementing, and maintaining the QA Program are assigned to Department Managers by the Vice President-Nuclear Energy Division. Managers delegate their authority as required to implement their responsibilities. (1)
Quality assurance matters that cannot be resolved by the Managers or Vice Presidents are brought to the l
attention of the Senior Vice President-Generation, President and Chief Operating Officer, or the l Chairman of the Board for resolution.
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QUALITY ASSURANCE POLICY Revision 49 Vice Pre <ident-Nuclear Enerav Division The Vice President-Nuclear Energy Division, is responsible to the Senior Vice President-Generation for ensuring that the QA Program is developed and implemented. The authority to develop QA Program Documents is assigned to designated Nuclear Program Managers. De Vice President-Nuclear Energy Division, is also responsible for ensuring thet the requirements of the QA Program that relate to the design, operation, and maintenance of the plant are implemented. This responsibility is carried out through Nuclear Program Managers.
Mannomr-Nucimar Performance A==a== ment Danartment ne Manager-NPAD, is responsible for assuring an appropriate QA Program is established and i
effectively executed for CCNPP. He is responsible for the independent assessment of the Nuclear Program, rr: view of industry operating experience, and vendor evaluation functions for CCNPP. These responsibilities include:
1.
Maintaining the QA Policy.
2.
Ensuring that QA compliance reviews are completed for pmgram acceptability of Directives and their revisions before they are approved. (9) 3.
Taking necessary corrective action, which can include the stoppage of work when manufacturing, maintenance, or modification activities fail to comply with approved l
specifications, plans, or procedures.
Such corrective action is arranged through l
appmpriate channels and is delegated when necessary. When a unit is operating, the Manager-NPAD, may recommend to the Plant General Manager that the plant be shut down. The Plant General Manager has the final responsibility for the overall evaluation of all aspects and implications of shutting down an operating unit.
BGE has established that the Manager-NPAD, should have at least six years of responsible experience in engineering, design, manufacturing, construction, quality assurance, or power plant operation, as well as a knowledge of regulations and standards related to nuclear power plants.
The organization of NPAD is shown in Chapter 12 of the UFSAR. He Manager-NPAD, j
delegates responsibilities for accomplishing the following activities:
Planning, scheduling, and performing internal independent assessments (integration of inspections, observations, surveillances, evaluations, and audits) of on-site and off-site functions performed under the nuclear QA Program.
Supporting maintenance and operations activities by providing oversight of other department personnel as they perfonn inspections and surveillances. (11)
Reviewing proposed changes to QA Program documents for compliance with regulations I
and licensing documents.
Directing a program for identifying trends within the corrective action systems.
Directing reviews of the operating experience of other plants of similar design to determine the applicability of significant events with respect to CCNPP. (14)
'i Planning and scheduling evaluations of vendor quality assurance programs. _
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Q', ALIW ASSURANCE POLICY Revision 49 NPAD personnel who i J. ort to the Manager-NPAD, are independent of departments, sections, and employees responsii' i for performing specific activities, and have sufficient authority and organizational freedom t Acntify quality problems; to initiate, recommend, or provide solutions through designated chani. sis; and to verify implementation of solutions. Non-NPAD personnel who are authorized to perform activities under NPAD programs are matrixed to NPAD for the performance of such activities, and possess similar organizational freedom and independence f om the activities.
Plant Ganaral Manmaar-Calvert ClifTn Nuclear Power Plant Denartment The Plant General Manager is responsible for operations, chemistry, outage management, radiation safety, special processes, maintenance, the corrective actions program, industrial safety program development and implementation, fire protection program implementation and systems and performance engineering activities at CCNPP. He must ensure that these activities are conducted in accordance with the plant operating license and TSs, the UFSAR, the QA Program, and procedures. The Plant General Manager fulfills the position and requirements of the Plant Manager, as defined in ANSI N18.1 (1971). He, or one of his derSnated principal alternates, shall have acquired the experience and training normally required kr examination for a senior reactor operator's license.
The Plant General Manager is also responsible for directing investigations of significant events to determine root cause, recommending corrective action, and generating appropriate reports to document the investigation results.
The organization of CCNPPD is shown in Chapter 12 of the UFSAR. The Plant General Manager, delegates responsibilities for accomplishing required activities as follows:
1.
The Superintendent-Nuclear Operations (S-NO) is responsible to the Plant General Manager, for the operation of the plant, including the general supervision of all shift operating personnel and prioritization of maintenance activities to support operations.
This responsibility covers the safety of plant personnel and equipment, all fuel-handling and refueling activities, and adherence to applicable license and regulatory requirements.
i He is additionally responsible for development, implementation and coordination of the industrial safety program; implementing the fire prevention and fire fighting programs for the CCNPP; and planning, scheduling and nonitoring activities directly related to i
safety, fire protection, and fire prevention, ne Superintendent-Nuclear Operations l fulfills the position and requirements of the Operations Manager as defined in ANSI N18.1 (1971) with the exception taken in Table 1B.I.
The Superintendent-Nuclear Operations delegates primary management responsibility to the Shift Supervisor on duty, via the General Supervisor-Nuclear Plant Operations (GS-i l
NPO) to ensure the safe operation of the plant under all conditions. The Shift Supervisor maintains the broadest possible perspective on operational conditions that affect the safety of the plant. As the senior member of plant management on each shift, he exercises the command authority of his position to take whatever steps he deems necessary during emergency situations to place and maintain in a safe configuration any l
umt that may be affected.
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The Superintendent-Nuclear Maintenance (S-NM) is responsible to the Plant General l
Manager for managing and directing activities of the Nuclear Maintenance Se:, tion to l
provide high quality maintenance programs, plans and schedules, and qualified personnel to perform maintenance functions necessary to assure the safe reliable, and 2
economic operation of the plant to generate power within applicable laws, standards, codes, and regulatory requirements.
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i QUALITY ASSURANCE POLICY Revision 49 a.
he General Supervisor-Electrical Maintenance (GS-EM), is responsible to the Superintendent-Nuclear Maintenance, for the conduct of electrical maintenance, repair, and modifications needed to keep the plant and its facilities, systems, and equipment in safe and efficient working condition. He is responsible for planning and supervising or controlling the electrical maintenance ac:ivities conducted by plant maintenance personnel, and for ensuring that work is performed in accordance with applicable Codes and Standards and shat regrbl maintenance records are developed and kept. He is responsible for contioitir.g i
tools and equipment used for electrical maintenance, repair and modifications j
activities.
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De General Supervisor Instrument Maintenance (GS-IM), is responsible to the Superintendent-Nuclear Maintenance, for the conduct of instrument maintenance, repair, and modifications needed to keep the plant and its facilities, systems, and equipment in safe and efficient working condition.
He is i
responsible for planning and supervising or controlling the instrument j
maintenance activities conducted by plant maintenance personnel, and for i
ensuring that work is performed in accordance with applicable Codes and Standards and that required maintenance records are developed and kept. He is 4
responsible for controlling tools and equipment used for instrument l
maintenance, repair and modifications activities.
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He General Supervisor-Mechanical Maintenance (GS-MM), is responsible to the Superintendent-Nuclear Maintenance, for the conduct of mechanical maintenance, repair, welding, and modifications needed to keep the plant and its l
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facilities, systems, and equipment in safe and efficient working condition. He is i
responsible for planning and supervising or controlling the mechanical maintenance activities conducted by plant maintenance personnel, and for
'i ensuring that work is performed in accordance with applicable Codes and Standards and that required maintenance records are developed and kept. He is responsible for controlling tools and equipment used for mechanical main +enme repair, and modifications activities.
s d.
He General Supervisor - Plant Work Control (GS-PWC), is responsible to the Superintenendent-Nuclear Maintenance, for developing, implementing, and maintaining a site integrated schedule for all significant plant related activities at CCNPP.
c.
He General Supervisor - Maintenance Support (GS-MS), is responsible to the Superintendent - Nuclear Maintenance for the administrative and procedural support of the plant maintenance units; responsible for the development, revision and processing of maintenance technical procedures; providing self assessment stpport to the maintenance line General Supervisors to identify performance treads for continuous improvement.
3.
He General Supervisor-Plant Eagineering (GS-PE), is responsible to the Plant General Manager for providing field engineering and technical evaluation of plant systems and to evaluate and coordinate resolution of system and component problems with operations, maintenance, and engineering personnel for the Calvert Cliffs Nuclear Power Plant.
Additionally, the GS-PE is responsible to the Plant General Manager for providing plant reliability / availability testing and evaluation, plant performance improvemer,t, administration of the Surveillance Test Program, administration and p, ogre n development for the welding program, and providing inservice inspection, nondestructive examination, and materials testing and evaluation services for the Calvert Cliffs Nuclear Power Plant.
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QUALITY ASSURANCE POLICY Revision 49 4.
~ he General Supervisor-Chemistry (GS-C) is responsible to the Plant General Manager for the chemistry and radiochemistry of the primary and secondary systems and for maintaining radioactive efiluents within specified limits. Additionally, the GS-C provides program management of the Radiological Environmental Monitoring Program with support from the Manager-FEMD to ensure compliance with the Offsite Dose Calculation Manual (ODCM).
5.
The General Supervisor-Radiation Safety (GS-RS) under the nuclear QA Program, is responsible to the Plant General Manager for:
Ensuring the radiation protection of personnel at CCNPP.
Complying with radioactive material transport regulations.
6.
The Outage Manager is responsible to the Plant General Manager for managing the planning, scheduling and performance of all outages at CCNPP.
M.n.
r-N.mia-Fopa-ing Department ne Manager-NED, is responsible for directing the efforts of personnel and providing resources
=~ - y to support design, mWcation and engineeririg activities covered by the QA Program for CCNPP. Dese activit(s include nuclear, mechanical, civil, reliability, instrument and controls, and electr%i cagineering; nuclear fuel management; configuration management; life cycle management; plant design support; engineering planning; licensing; fire protection program development;and design and drawing.
He organization of NED is shown in Chapter 12 of the UFSAR. The Manager-NED delegates responsibilities for accomplishing the following avivities:
Providing conceptual and detailed cryxing, design and drawing, data base configuration control, and documentation and maintenance of plant design bases for the power and control systems for the Calvert Cliffs Nuclear Power Plant.
Directing and performing safety evaluations, preparation and review of nuclear safety accident and transient analysis, fuel management, nuclear engineering related to core physics, reactor engineering, external fuel cycle management, reliability engineering and development and integration of programs necessary to operate up to and beyond the current licensed lifetime for the Calvert Cliffs Nuclear Power Plant.
Providing plant design support, and engineering planning and scheduling for the power and control systems for the Calvert Cliffs Nuclear Power Plant.
Providing licensing services; coordination and operation of various industry information exchange systems; evaluation of plant events and conditions adverse to quality for reportability to the NRC and other agencies, assisting in the investigation and evaluation of events, and preparation of the reports; coordination of tracking and resolution si company commitments to the NRC; research and pmparation of responses to h%C letters, bulletins, circulars and information notices; UFSAR research and revision control; maintenance and revision of the current licensing basis for nuclear power plants; coordination of all compliance-related communications with external agencies including assistance in ensuring their consistency with existing licensing basis commitments; and coordination of regulatory inspections and visits ankompany presentations to the NRC.
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4 QUALITY ASSURANCE POLICY Revision 49 Maaaaer-Nuclear Proiect Manmoement Decartment The Manager-NPMD is responsible for directing the efforts of personnel and providing resources necessary to support site project management for assigned projects.
The organization of NPMD is shown in Chapter 12 of the UFSAR. The Manager-NPMD delegates responsibilities for providing overall project management for engineering, l
procurement, construction and testing of arranged major maintenance and modification projects j
for CCNPP.
Manager-Nuclear Sunnort Services Denartment The Manager-NSSD is responsible for emergency planning, training, nuclear security, onsite procurement coordination, procurement engineering, receipt inspection and storage / issue of i
items, procedures program support, divisional business planning, information technology l
management, document and records management, staff services and state regulatory matter functions for CCNPP.
The organization of NSSD is shown in Chapter 12 of the UFSAR. The Manager-NSSD delegates responsibilities for accomplishing the following activities:
Directing the efforts of BGE personnel involved in emergency planning activities.
Coordinating investigations concerning state regulatory matters.
Providing support to Managers in the Nuclear Energy Division to ensure their personnel are j
properly trained and qualified to perform their assigned duties, including those duties which implement the nuclear QA Program. Training required by special work forces and l
contractors is performed by the appropriate BGE Department, and/or Host Company l
(vendor).
l Ensurire that the operational maintenance, licensing, and training activities associated with l
plant security are effectively implemented, and that nuclear security provisions provide protection for personnel, equipment, and facilities at CCNPP against potential security
. threats.
Coordinating the efforts of Nuclear Energy Division personnel involved in the procurement e
l of structures, systems, components, parts, and services related to the design, construction, l
fueling, maintenance, and modifications of CCNPP. Performing receipt inspection functions including special receipt inspections and coordinating testing performed to accept commercial grade items, designated NSR items or upgrade NSR items for use in SR applications. (5) Directing the efforts of personnel responsible for the storage and issuance of material for CCNPP. Establishing procedures to assure that SR and DNSR procurement documents identify technical and quality requirements; procurement (SR and DNSR) documents receive independent review and approval for the proper inclusion of technical and quality requirements; ensuring spare and replacement parts are suitable for their intended application (s); specification of critical characteristics and acceptance criteria for dedication of commercial grade items; specification of special storage requirements for age sensitive items.
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QUALITY ASSURANCE POLICY Revision 49 Providing a structured management control system that communicates management expectations and regulatory requirements for conducting activities at or in support of CCNPP. Development of the annual Business Plan for the Nuclear Energy Division.
Establishing procedures to assure adequate information management standards are in place along with effective oversight and self-assessment measures. Distributing, and coordinating the preparation of revisions to the QA Program documents; collecting, storing, maintaining, and retrieving QA records for nuclear power plants; maintaining, controlling, and distributing drawings and technical manuals related to equipment, materials, and services for nuclear power plants.
Individuals supporting the CCNPP QA Program are designated as follows:
Vice President-Fossil Energy Division The Vice President-FED, is responsible to the Senior Vice President-Generation for ensuring that the activities of FED personnel involved in CCNPP maintenance and modifications, and radiological environmental monitoring, meet the requirements of the QA Program. This responsibility is carried out j
through the Manager-FEMD.
Mannger-Fossil Fngineering & Maintenance Denartment 1
The Manager-FEMD, is responsible for directing the efforts of FEMD personnel involved in maintenance and modification activities at CCNPP and maintaining and operating Radiological Environmental Monitoring Program equipment and performing sample collection and analysis.
Vice President-Electric Interconnection and Transmission Division j
ne Vice President-EITD, is responsible for ensuring that the requirements of the QA Program that relate to the calibration of test equipment and the testiar of protective relaying, and metering controls for SR electrical power equipment are implemented. I a responsibility is carried out through the Manager.
SOMD.
Manager-System Ooeration and Maintenance Deoartment ne Manager-SOMD, is responsible for directing the efforts of personnel involved in the testing of electrical power equipment, the calibration of test equipment and the testing of protective relaying and metering controls for the electrical power equipment of CCNPP.
Vice President-General Services Division The Vice President GSD is responsible for ensuring implementation of the QA Program requirements that relate to: the procurement of SR or designated NSR structures, systems, components, and services; the construction, maintenance, and operation of facilities; and support services for computer software and hardware.
These responsibilities are carried out through the Manager-PMMD, Manager-ISD, and Manager-FFSD.
Manager-Purchasing and Materints Management Denartment The Manager-PMMD, is responsible for directing the efforts of personnel involved in the purchasing of items and services for CCNPP and for the issuance of Contracts for Fitness for Duty Activities.
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QUALITY ASSURANCE POLICY l
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1 Manneer Information Systems Denartment The Manager-ISD, is responsible for directing the efforts ofISD personnel involved in acquiring l
and supporting computer software and hardware.
Manneer-Facilities and Fleet Services Denartment l
The Manager-FFSD, is responsible for directing the efforts of FFSD personnel involved in the planning, design, construction, maintenance, and operation of facilities and related systems l
directly supporting or impacting power plant operations.
Vice President-Manneement Services Division
'the Vice President-MSD, is responsible for ensuring that the activities of MSD personnel involved with:
medical examinations for CCNPP operators, Nuclear Security Officers, and respirator users;.
psychological assessments supporting the Access Authorization rule; and the Fitness for Duty rule meet the requirements of the regulatkns. The responsibility is carried out through the Manager-SMSD.
Manneer Safety and Medical Services Denartment l
The Manager-SMSD, is responsible for directing the efforts of SMSD personnel involved with medical examinations for CCNPP operators (10CFR55), Nuclear Security Officers (10CFR73),
respirator users (10CFR20); psychological assessments supporting the Access Authorization rule (10CFR73); and with the Fitness for Duty rule (10CFR26).
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i QUALITY ASSURANCE POLICY Revision 49 1B.2 QUALITY ASSURANCE PROGRAM General Controls De QA Program consists of the QA Policy, certain Nuclear Progmm Directives and their administrative procedures. Revisions to the QA Policy are controlled by QA Program documents which are written to ensure compliance with 10 CFR 50.54(a)(3). QA Policy changes are submitted according to 10 CFR 50.71.
%c QA Policy identifies NRC regulatory requirements, industry standards, and specific codes applicable to the eighteen criteria contained in 10 CFR 50, Appendix B. De QA Policy also indicates action that niil be taken by BGE in response to these documents and to commitments made in the UFSAR and TSs for CCNPP.
Nuclear Program Directives address actions identified in the QA Policy. Directives identify regulatory commitments, management requirements, and assign responsibilities for business activities (i.e., design, maintenance, operations, etc.) within the BGE Nuclear Program.
BGE's QA Program for CCNPP is applied to structures, systems, components, and activities that have been designated SR because they prevent accidents or mitigate the consequences of postulated accidents that could cause undue risk to the health or safety of the public. De QA Program is also applicable to designated NSR structures, systems, components, activities, and services as required by regulations.
Designated NSR program requirements are based on a graded approach to Quality Assurance required to meet applicable regulatory designated requirements and guidance. He level of QA Program controls placed on designated NSR itemt are defined in QA Program documents and/or implementing procedures.
The contiels from other sections of this QA Policy are selected as necessary to meet the particular regulations being implemented.
Controls have been established for specifying on a Quality List (Q-List) all SR structures, systems, components, and activities that are subject to the requirements of the QA Program.
He Statement of Authority, in the Nuclear Pro.i n Policies Manual, signed by the Chairman of the Board, establishes the overall QA Pohey of BGE. This Statement sets the goal of safe and reliable operation of CCNPP; commits the Company to a QA Prograin designed to ensure the plaat's compliance with regulatory requirements, BGE commitments, and established practices for reliable plant operation; and requires every person involved in QA Program activities to comply with the provisions of the Program.
The QA Policy is approved by the Viu President-NED and implemented by Nuclear Program Managers.
(1)
De QA Program has established controls for BGE and its contractors as required to ensure that the criteria of 10 CFR 50, Appendix B, will be met throughout the operations phase of the plant; i.e., during activities of testing, operation, maintenance, repair, modification, and refueling.
The QA Program has :L established controls to ensure that the construction, operational, and decommissioning phases for the Independent Spent Fuel Storage Installation (ISFSI) are cunducted in compliance with 10 CFR 72. Activities associated with the operational and decommissioning phase shall be controlled under the CCNPP 10 CFR 50 Appendix B QA Program; existing policies, programs, directives, and procedures stated as applicable for CCNPP are also applicable for the ISFSt. (16)
Nuclear Program Managers enwre QA Program documents are revised as regulations, standards, results, or experience dictate. (1) ne Mane -r-NPAD evaluates the degree of compliance with the requirements e
. of QA Program documents and procedos. Audits are conducted regularly to ensure compliance with established requirements, and the results of these audits are reporO3 to responsible management pww.al.
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QUALITY ASSURANCE POLICY l
Revision 49
)
The Vice President-NED, ensures that activities of the NPAD are audited regularly by personnel independent of-the Department.
These auditors assess the effectiveness of the Department's implementation of appropriate portions of BGE's QA Program. De Vice President-Nuclear Energy Division, evaluates the report of the independent audit to determine if changes are required to the QA Program. He is responsible for negotiating such changes with the appropriate level of management and for sending to the Chairman of the Board a copy of the audit report and an account of the corrective
- action taken.
If a difference of opinion arises between NPAD personnel and those of other Sections or Departments, the dispute is resolved as follows: ne Supervisor / General Supervisor of the NPAD Unit /Section involved first tries to resolve the matter with the organization responsible for conducting the activity. If a resolution cannot be obtained, the matter is referred up through the following management personnel until it is resolved: (3) 1.
The Manager-NPAD, and the Manager responsible for performing the activity.
NOTE:
If the dispute is with another Unit /Section in NPAD, the issue will be settled by the Vice President-Nuclear Energy Division. (3) 2.
The Vice President-Nuclear Energy Division. (1) 3.
The Senior Vice President-Generation, President and Chief Operating Officer, or the Chairman l i
of the Board.
To ensure that important activities are performed correctly, BGE conducts formal training programs for Company personnel with significant responsibilities. These programs include both initial and continuing training and are conducted in accordance with written procedures or instructions. Department Managers are responsible for ensuring that the training needs of personnel in their Departments are identified, formal trai:ing programs to satisfy those needs are developed, and the training programs are implemented in accordance with the requirements of the QA Program documents.
The QA Program was developed to meet the requirements of the Regulations and Regulatory Guides of the Nuclear Regulatory Commission (NRC), and Indusay Standards listed below. Exceptions taken to guidance contained in these documents and equivalent BGE alternatives are stated in Table IB-1.
REGULATIONS 10 CFR 50.55a - Codes and Standards.
f 10 CFR 50.59 - Changes, Tests, and Experiments.
10 Cr'n 55 - Operators' Licenses.
10 CFR 50, Appendix B - Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.
10 CFR 72, Subpart G - Quality Assurance (ISFSI) 4 4
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QUALITY ASSURANCE POLICY REGULATORY GUIDES
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1.8 - Personnel Selection and Training (September 1975)". His endorses ANSI N18.1 (03/08nt)*".
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.1.16 - Reporting of Operating Information (as specified in Calvert Cliffs Technical Specifications).
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' 1.30 - QA Requirements for lastallaion, inspection, and Testing of Instrumentation and Electnc Equipmei,t (08/l1/72)*. His endorses ANSI N45.2.4 (03/01n2).
l 1.33 - QA Program Requirements (Operation, Rev. 2,02n8)"#. This endorses ANSI N18.7-1976/ANS l
3.2(02/1906)"*.
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1.37 - QA Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled l
Nuclear Power Plants (03/1603)". His endorses ANSI N45.2.1 (02/2603)"*.
1.38 - QA Requirements for Packaging, Shipping, Receiving, Storage, and Handling ofitems for Water-Cooled Nuclear Power Plants (Rev. 2,05n7)**. This endorses ANSI N45.2.2 (12/20n2)"*.
1.39 - Housekeeping Requirements for Water-Cooled Nuclear Power Plants (03/16n3)*, his endorses ANSI N45.2.3 (03/15n3)*".
1.54 - QA Requirements for Protective Coatings Applied to' Water-Cooled Nuclear Power Plants (0603)". This endorses ANSI N101.4 (11/28n2)*".
1.58 - Qualification of Nuclear Power Plant inspection, Examination, and Testing Personnel (09/80)**.
j nis endorses ANSI N45.2.6 (1978)"*.
1.64 - QA Requirements for the Design of Nuclear Power Plants (10,73)*. This endorses ANSI N45.2.11, DraA 3, Rev.1 (07n3).
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.1.68 - Prooperational and Initial Startup Test Programs for Water-Cooled Power Reactors (1103)".
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1.144 - Auditing of Quality Assurance Programs for Nuclear Power Plants, Rev.1 (09/80)". This l
endorses ANSI N45.2.12 (1977).
l 1.146 - Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants (Aug.
l 1980).*. His endorses ANSI N45.2.23 (1978)*".
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INDUSTRY STANDA13D3 l
l ANSI N45.2.5 - Supplementary QA Requirements for Installation, inspection, and Testing of Structural l
Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants; DraA 3, Rev.1 (11/73).
ANSI N45.2.8 - Supplementary QA Requirements for Installation, inspection, and Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants; Draft 3. Rev. 2 (0903).
l ANSI M45.2.9 - Requirements for Collection, Storage, and Maintenance of Quality Assurame Records for Nuclear Power Plants; DraA (1006)*".
1 ANSI N45.2.13 - QA Requirements for Control of Procurement of Equipment, Materials 7and Services for Nuclear Power Plants; DraR 2, Rev. 2, (l 003)"*.
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QUALITY ASSURANCE POLICY Revision 49 NOTATIONS FOR REGULfJORY OUIDES AND INDUSTRY STANDARDS NRC endorses an Industry Standard or draft without reservation.
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NRC takes exception to or provides additional guidance in a regulatory position statement.
BGE takes exception to guidance offered in Industry Standard and states attematives.
BGE takes exception to guidance offerd in Regulatory Guide and states alternatives.
Procedural Controls The QA Policy and revisions thereto are reviewed by Nuclear Program Managers. QA Policy revisions are reviewed by NPAD personnel to detennine if they constitute a reduction in commitments previously made to the NRC. If so, the tuvisions are sent to NRC for approval prior to implementation. The Manager-NPAD reviews revisions to the QA Policy and recommends approval to the Vice President-Nuclear Energy Division. %e Vice President-NED approves the QA Policy and revisions thereto. QA Prsy e documents control the distribution and revision of the QA Policy.
Nuclear Progr.m Directives are prepared under the direction of the Department Manager assigned by the Vice Prrdent-NED as the Program Sponsor. Each directive and revisions thereto are reviewed by affected Dep runent Managers. He Manager-NPAD ensures directive revisions are reviewed by NPAD perso;mel and approval recommended to the Program Sponsor. De Program Sponsor approves the directive and revisions thereto. he Manager-NSSD ensures issuance of all directives and revisions 4
thereto.
l QA Program documents ensure that:
i 1.
De need for special controls, processes, test equipment, tools, and skills is specified when necessary to ensure that required quality is attained in perfonnance of the activity.
2.
Quality is verified by inspections and tests.
3.
Personnel who perform activities affecting quality achieve and maintain suitabk prof %ncy through appropriate training and experience.
Review of Oneratinne Procedures require that CCNPP shall be operated and maintained in accordance with the plant TSs and operating license. The following organizations review plant operations to ensure that these procedures are followed:
i 1.
The Manager-NPAD provides independent verification that the requirements contained in the Plant's operating license, UFSAR, TSs, and plant procedtres are met. This is accomplished through quality assurance audits.
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QUALITY ASSURANCE POLICY Revision 49 l
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The OSSRC provides independent verification by review that CCNPP is operated in accordance l
with established requirements. The OSSRC, which functions under a written Charter approved l
by the Vice President-Nuclear Energy Division, is composed of on-site and off-site personnel knowledgeable of in-plant operations, nuclear er dneering, chemistry and radiochemistry, metallurgy, radiological safety, instrumentation and control systems, mechanical and electrical systems, quality assurance, and environmental factors. The proceedings of all meetings are i
documented and sent to the Vice President-Nuclear Energy Division, Cornmittee members, and i
others designated by the Committee Chairman.
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3.
The on-site POSRC reviews matters pennining to nuclear plant safety. This Committee screens subjects of potential concern to the OSSRC and performs preliminary investigations under the direction of the Plant General Manager. POSRC membership and functions are governed by Addendum IB-1 and written procedures. (19) The results of all meetings are documented and sent to the members of the OSSRC, and others designated by the Committee Chairman.
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The maintenance and repair of systems, structures, and components subject to the QA Program are performed by personnel under the direction of the General Supervisors of Electrical Maintenance, Instrument Maintenance, Radiation Safety, and Mechanical Maintenance, according to written l
procedures and instructions as prepared by the maintenance force and approved as stated in QA Program documents. These Procedures:
1.
Ensure that quality-related activities, such as inspections and tests, are performed with appropriate equipment and under suitable environmental conditions.
2.
Indicate inspections and checks that must be made and records and data that must be kept.
3.
Show where independent verifications ofinspections or checks should be perfonned by specified l
personnel other than those performing the work.
t When necessary, non-plant Company personnel or outside contractors are brought in to supplement the plant work force. In such instances, the approval of work procedures and the tagging of equipment are coordinated by a member of the BGE organization responsible for the performance of the work.
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Controls are established in QA Program documents to ensure that materials and parts used in the repair, maintenance, and modification of SR and designated NSR portions of the plant are appropriate for the service intended. Written procedures are prepared for the storage and identification of materials and parts to ensure that they do not deteriorate in storage and can be correctly identified before installation or i
nse.
Equipment manufacturers and contractors used for the repair, maintenance, and modification of SR and designated NSR structures, systems, and components are required to have quality assurance programs consistent with the importance of the end-product to safety.
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e QUALITY ASSURANCE POLICY Revision 49 1B.3 DESIGN CONTROL Control
- Plant changes which affect the design, function, or method of performing the function of a structure, system, or component described in the UFSAR are controlled by QA Program documents which are written to ensure compliance with Regulatory Guide 1.64 and 10 CFR 50.59.
J Controls for changes, tests, and experiments conducted at CCNPP vary according to the following:
1.
As the item or activity affected is or is not described in the UFSAR.
' 2.
As the item or activity affected has been classified SR or NSR.
3.
As the item or activity affects or does not affect nuclear safety.
4.
As the proposed change, test, or experiment does or does not constitute an Unreviewed Safety Question or require a change to the TSs.
To ensure compliance with 10 CFR 50.59, the process for controlling changes, tests, or experiments has been divided into classifications. Procedures required by QA Program documents describe and control the method for determining the appropriate process classification. %c process classifications control the preparation and reporting of safety evaluations. nree methods of treatment are allowable:
1.
Implementing the change, test, or experiment in accordance with Company practice for operating power plants, or in accordance with Procedures required by QA Program documents.
2.
Implementing the change, test, or experiment in accordance with Procedures required by QA Program documents but controlling the change, test, or experiment with a process classification.
3.
Controlling the change, test, or experiment with'a process classification and not allowing the implementing activity to begin until the review requirements of 10 CFR 50.59 and 10 CFR 50, Appendix B, have been met.
Changes, tests, or experiments which require approval by the NRC are reviewed by the POSRC and by the OSSRC.
Controls have been established to ensure that design changes to SR structures, systems, and components are reviewed either by the organization that made the original design or by a Responsible Design Organization (RDO) that meets requirements specified in ANSI N45.2.l l, Section 8.0.
Re==annihte Danign Organi>=tians RDOs, either on contract or within BGE, ensure that:
1.
Applicable regulatory requirements and design bases requirements are correctly translated into specifications, drawings, written procedures, and instructions.
2.
Appropriate standards for quality are specified in design documents, and deviations and changes from such standards are controlled.
3.
Suitable design controls are used in applying principles of reactor physics; making seismic, stress, thermal, hydraulic, radiation, and accident analyses; ensuring compatibility ~of materials; and providing accessibility for in-service inspection.
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QUALITY ASSURANCE POLICY Revision 49 4.
Designs are reviewed to ensure that design characteristics can be controlled, inspected, and tested, and that inspection and test criteria are identified.
5.
Interfaces, both external and internal, are controlled for the activities of all participating organizations.
6.
Methods for verifying or checking, such as design reviews, attemative calculations, and qualification testing are properly chosen and followed; the most adverse design conditions are specified for test programs used to verify the adequacy of designs.
7.
Individuals or groups responsible for design verification are other than the original designer and the designer's immediate supervisor.
8.
Design and specification changes are subject to design controls and approvals applicable to the original design.
9.
Design documents and revisions thereto are distributed to responsible individuals and controlled to prevent inadvertent use of superseded material.
10.
Design errors and deficiencies that adversely affect SR structures, systems, and components are documented, and appropriate corrective action is taken.
11.
Design documents and reviews, records, and changes thereto are collected, stored, maintained, and controlled systematically.
12.
Standard off-the-shelf commercial or previously approved materials, parts, and equipment essential to the SR functions of structures, systems, and components are reviewed for suitability of application before they are selected.
13.
'Ihe persons or groups responsible for design reviews and other design verification activities and their authority and responsibilities are identified.
l 14.
Design changes to NSR items initiated and approved at the plant are controlled to ensure l
compliance with 10 CFR 50.59, 15.
Processes used to select suitable materials, parts, equipment, and processes for SR structures, systems, and components includes the application of pertinent industry standards and specifications, material and prototype hardware testing programs, and design reviews.
16.
Computer programs used in design are subject to design controls and program verification.
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l' QUALITY ASSURANCE POLICY Revision 49 1B.4 PROCUREMENT DOCUMENT CONTROL (5) i Controls have been established to specify the requirements and sequence of actions for: requesting items l
or services; review of the requested item or service to establish the necessary technical and quality requirements; pmparation, review and control of procurement documents; evaluation and selection of i
vendors and; control of deviations from the procurement document requirements, The degree to which these controls are imposed on the purchase of items and services by BGE for t
CCF~'P depends on:
1.
The functional (safety) classification of each item or service as SR or NSR according to controls established by the RDO and j-2.
. He Procurement Category of the item within it's functional classification as a basic component, commercial grade item, designated non-safety related item (DNSR) or NSR item l
a.
Commercial Grade - An item satisfying all three of the following criteria:
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1.
Not subject to design or specification requirements that are unique to nuclear
' facilities; and i
2.
Used in applications other than nuclear facilities; and 3.
Is to be ordered from the manufacturer / vendor on the basis of specifications set forth in the vendor's published product description (for example, a catalog).
b.
Basic Component - An item either procured as a safety related item or a a commercial grade item which has been accepted and dedicated for safety related application. His term is synonymous with " Safety-Related Component".
Designated Non-Safety Related - A NSR item which BGE has made a regulatory or design c.
basis commitment; or, for plant availability reasons, BGE has implemented special controls to assure reliability. These NSR items are included within the quality assurance process.
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d.
Non-Safety Related - An item that does not perform a safety related function.
3.
The procurement method to be used for the item or service:
)
Purchase Orders placed by BGE personnel for items or services intended for safety related applications and DNSR items and services fall into two categories, Nuclear Grade Method procurement and Commercial Grade Method procurement.
a.
Nuclear Grade - Purchases that are designated to be placed with vendors that maintain a 10CFR50 Appendix B quality program and supply items that meet the definition of Basic Component. The requirements of 10CFR21 will be invoked on the vendor under this method.
b.
Commercial Grade - Purchases that are designated to be placed with commercial grade vendors that supply items or services that meet the definition of Commercial Grade. These items must be dedicated for SR use by BGE.
l Items and/or services classified as DNSR will be purchased using the Commercial Grade Method with technical requirements established by an RDO.
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QUALITY ASSURANCE POLICY Revision 49 n
Qualified NSSD/NED personnel trained in quality assurance program requirements with RDO authority review safety-related and designated non-safety related procurement documents for proper inclusion of l-technical and quality requirements. Personnel in NSSD/NED review safety-related and designated non-safety related procurement documents to ensure that the requirements stated tigrein are correct, inspectable, controllable, contain adequate acceptance and rejection criter', J7d comply with the requirements of the procurement program. Dese reviews and approvals w documented prior to i
placement of the purchase order.
I All changes made to procurement documents, including specifications and other technical attachments, are subject to the same levels of review, approval and control that were applied in preparing and processing the original documents.
Bids submitted to supply safety-related items or services receive the same review and approval cycle as used for safety-related procurement requisitions.
Vendor Selection Personnel in NPAD evaluate vendors who provide SR and designated NSR items and services to verify they can provide acceptable items and services.
Cnntrols for Nuclear Grade Purch==>=
l Controls have been established to ensure that, before placement of a purchase order under the Nuclear Grade method of purchase, there is evidence of the following:
1.
The vendor has been evaluated as stated in Section IB.7 of this policy and found to have a satisfactory QA program.
2.
De item to be purchased is manufactured under the requirements of the evaluated and approved program.
Controls for Commercimi Gr=A Purch==,<
Controls have been established to ensure that items or services available to general industry will be sufficiently controlled to perform their SR and designated NSR function. NSSD/NED personnel will specify the acceptance methods to be used to verify the critical characteristics identified in the procurement document (s).
Prm a =nt Document Reauirements Procedures require that procurement documents shall:
1.
Reference part numbers or descriptions, and additional requirements to ensure that items ordered can be identified and verification can be made that each item received is the item ordered.
2.
Contain/ reference technical requirements for the basis of design, by including the applicable regulatory requirements, component and material identification, RDO approved drawing and specification, codes, industrial standards, test and inspection requirements, and special process instructions such as welding, heat treating, nondestructive testing, and cleaning.
3.
Identify the requirements of 10 CFR 50, Appendix B, which must be complied with and described in the vendor's QA program, for Nuclear Grade Purchases.
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QUALITY ASSURANCE POLICY Revision 49 4.
Require that major' contractors designated as BGE agents to purchase SR and designated NSR items or services must have procurement controls to ensure they purchase or acquire these items or services in compliance with the necessary sections of ANSI N45.2.13.
5Property "ANSI code" (as page type) with input value "ANSI N45.2.13.</br></br>5" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..'
identify required documentation (i.e., drawings, specifications, procedures, inspection and fabrication plans, inspection and test records, personnel and procedure qualifications, and material chemical and physical test results) to be prepared, maintained, and submitted to BGE or the purchaser for review and approval.
6.
Identify records which must be retained, controlled, maintained, or delivered to BGE or the purchaser before use or installation of hardware.
7.
Specify BGE or its agent's right of access to vendor facilities and records for source inspection, surveillance, verification and audits.
8.
Identify requirements of the vendor's quality control process which must be implemented when providing a commercial grade item.
9.
Reference or specify the critical characteristics that a commercial grade item must possess to ensure that the item received is the item specified.
10.
Incorporate the requirements of 10 CFR 21 for Nuclear Grade procurements.
11.
- Include requirements for QA program elements to be passed on to sub-vendors.
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1 QUALITY ASSURANCE POLICY Revision 49 1B.5 INSTRUCTION
S. PROCEDURE
S. AND DRAWINGS Controls delineate the sequence of actions to be performed in the preparation, review, approval, and control of instructions, procedures, and drawings.
]
Controls require that:
1.
Methods for complying with each of the applicable criteria of 10 CFR 50, Appendix B, must be specified in instructions, procedures, and drawings.
2.
Instructions, procedures, and drawings must specify appropriate quantitative (such as dimensions, tolerances, and operating limits) and qualitative (such as workmanship samples) acceptance criteria for verifying that important activities have been satisfactorily accomplished.
Controls ensure that:
1.
The QA Policy is approved by the Vice Pre %nt-Nuclear Energy Division. (1) 2.
Nuclear Program Directives are prerared urder the direction of the Department Manager assigned as the Program Sponsor. Af'ected Department Managers review directives and their revisions. The Manager-NPAD enstees directives are reviewed by NPAD personnel and approval recommended to the Program Jponsor. The responsible Program Sponsor approves directives and their revisions. Directives ne prepared, reviewed, and approved according to an appendix to the Nuclear Program Directives Mcnual. (19) 3.
Procedures are prepared, approved, and controlled sccording to the Control Procedures. Control Procedures establish review, approval, revision, chwge, and periodic review requirements for applicable procedures. If format and content requirements are not contained in Control Procedures, they shall specify the document to be n'ed to determine format and content requirements. Control Procedures are reviewed by NPAD personnel to ensure compliance with regulatory requirements and industry standards. Other prc,edures are reviewed by NPAD on a requested basis.
4.
Basis items added during procedure revisions or changes will be recorded. (1)
The Plant General Manager may designate specific procedures or classes of procedures in writing to be reviewed by the Procedure Review Committee or by Qualified Reviewers in lieu of review by the POSRC. Review by the Procedure Review Committee and by Qualified Reviewers shall be in accordance with Addendum IB-1. (19)
Procedures listed in Technical Specification 6.4 shall be approved by the Plant General Manager or by cognizant Managers, Superintendents, or General Supervisors (or Directors) that report directly to a Manager prior to implementation as specified by administrative requirements. The approval authority for specific procedures or classes of procedures shall be designated in writing by the Plant General Manager and shall be a different individual from the Qualified Reviewer. (19)
Temporary changes to procedures of Technical Specification 6.4 may be made provided:
a.
The intent of the original procedures is not altered.
l b.
The change is approved by two members of the plant management staff knowledgeable in the areas affected by the procedures, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
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i QUALITY ASSURANCE POLICY Revision 49 The change is documented, reviewed by the POSRC, the Procedure Review Committee, or by a c.
Qualified Reviewer and approved by the designated approval authority within 14 days of implementation. (19) i l
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l QUALITY ASSURANCE POLICY.
Revision 49 1B.6 DOCUMENT CONTROL Requirements have been established to control the documentation of activities controlled by the'QA Program. QA Program controlled documents include the UFSAR; Operating License, including the Technical Specifications; Emergency Responso Plan; Security Plan;- QA Policy; the ISFSI updated Safety Analysis Report (SAR) and Materials License, including Technical Specifications; procedures; specifications; and drawings.
Revisions to the QA Policy are controlled by QA Program documents which are written to ensure compliance with 10 CFR 50.54(a)(3).
Altentions to the' UFSAR are controlled by QA Program documents which are written to ensure compliance with 10 CFR 50.71.
L Alterations to the ISFSI updated SAR are controlled by QA Program documents which are written to ensure compliance with 10 CFR 72.70.
i Alterations to the Operating License, including the Technical Specifications, are controlled by QA l
Program documents which are written to ensure compliance with 10 CFR 50.59(c),10 CFR 50.90 and 10 CFR 50.92.
Alterations to the ISFSI Materials License, including the technical specifications, are controlled by QA Program documents which are written to ensure compliance with 10 CFR 72.48(c),10 CFR 72.56, and 10 CFR 72.58.
1 Alterations to the Emergency Response Plan are controlled by QA Program documents which are written to ensure compliance with 10 CFR 50.54(q), and with 10 CFR 72.44(f) for the ISFSI.
Alterations to the Security Plan are controlled by QA Program documents which are written to ensure compliance with 10 CFR 50.54 (p), and with 10 CFR 72.44(e) for the ISFSt.
l Directives are required to:
1.
Establish controls to ensure that regulatory requiremen's and BGE commitments will be t
p implemented.
2.
Establish controls to ensure that management requirements will be implemented.
3.
Assign responsibilities and interfaces within the program.
1 4.
Be prepared and controlled in accordance with an appendix to the Nuclear Program Directives
[
Manual that describes the format, contents, review and approval, and revision requirements. (19)
Nuclear Program Directives are prepared and technically reviewed under the direction of the Department l
Manager assigned as the Program Sponsor. Each directive is reviewed by affected Department i
. Managers. Each directive is given a compliance review by a member of NPAD. Nuclear Program 1
Directives are approved by the sponsoring Manager after ensuring resolution and incorporation of QA compliance review comments. (9) The Manager-NSSD ensures issuance of each directive.
Administrative and Technical Procedures are prepared when needed to implement QA Program t
(
document requirements according to a Control Procedure. Individual organizations are responsible for j
preparing, revising, issuing, and controlling procedures. ' Each procedure is given a technical review under the direction of the sponsoring organization. NPAD performs QA compliance reviews on Control Procedures. Other procedures are reviewed by NPAD on a requested basis.
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QUALITY ASSURANCE POLICY Revision 49 Administrative procedures are required to:
1.
Describe interdepartmenta' interfaces and establish controls for interdepartmental activities.
' 2.
Specify how important activities, such as plant maintenance or in-service inspection, are to be I
performed, and give sufficient detail to control the performance of the activity or to ensure that l
requirements for !cwcr. level procedures are clearly specified.
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3.
Be prepared and controlled in accordance with QA Program documents that describe the format, sequence of topics, contents, review and approval, issue and distribution, and requirements for l
revision and record retention.
During the review of each administrative procedure, compliance with applicable regulatory requirements l
and indurtn dsrds is verified and documented.
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Organizations mat issue instructions, procedures, specifications, or drawings are required to establish controls tint ensure the following:
l 1.
Changes to a document are reviewed and approved by the organization that performed the original review and approval unless the control procedure designates another qualified responsible organization.
2.
Approved changes are promptly incorporated into instructions, procedures, drawings, and other documents associated with the change.
3.
Obsolete or superseded documents are controlled to reduce the possibility of inadvertent use.
Supersedod documents retained for reference are marked and stored in separate files. Other superseded documents are removed from the files.
When changes to drawings or specifications are required, change requests are prepared by the organization that desires the change. Requests are reviewed and approved by BGE RDOs.
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QUALITY ASSURANCE POLICY Revision 49 l
IB.7 CONTROI OF PURCIIASED MATERIAL EOUIPMENT. AND SERVICES (5) l NPAD, NSSD, NED,'and PMMD personnel are responsible for the control of purchased items and l
l services for SR and designated NSR applications at CCNPP.
I The controlsinclude:
l Accepting items or services only from vendors who have been evaluated and selected in accordance with this policy.
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Procurement documents for spare or replacement parts of structures, systems, and components as designated under the QA Program subject to controls at least equivalent to those applied to the original equipment, or an evaluation / justification shall be documented when less stringent controls are involved.
Vendor surveillance, verification and audit activities, and receipt verification are conducted to l
ensure the vendors comply with specified technical and quality requirements, and ensure items t
are identified,- stored, handled and shipped in accordance with procurement document requisements.
Vendor Evaluation l
'Ihe vendor evaluation is conducted to determine acceptability of a vendor to provide the requested item or service, to determine what vendor programs, procedures and documents need to be invoked by the 7
procurement document, determining the vendor's performance history for supplying items to CCNPP and i
assessing the need to impose source surveillances and/or verifications during the manufacture ofitems or performance of services for BGE. Vendor evaluations depend on the procurement classification of the item (s)being supplied.
The National Institute of Standards'and Technology (NIST), by virtue of its bdr.a me nationally recognized standard, is an acceptable provider of calibration masters, standards or services. Utilities holding an NRC Construction Pennit or Operating License are acceptable suppliers of all items except l
for those items to be used in an ASME Boiler and Pressure Vessel Code Section III application. Neither
'i of the above are required to be listed on the Approved Vendors List (AVL).
Nuclear Grade NPAD performs evaluations and audits to verify that the vendor has developed and implemented i
l an acceptable quality assurance program that complies with the requirements specified in the l
procurement specification or proposed procurement specification. These evaluations and audits are conducted and documented using written pr cdures or checklists that identify the QA requirements applicable to the items supplied.
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Coansaerelal Grade l
Since BGE accepts the responsibility of verifying the conformance of commercial grade items and/or service, they may be procured from vendors with no fonnal quality assurance program.
In this instance, BGE dedicates the commercial grade item and/or service for SR use.
A survey may be performed of commercial vendors to assess what, if any documented controls l
are implemented in the manufacture ofitems or performance of services for BGE.
Vendor controls evaluated to be satisfactory may be invoked as requirements within the purchase order and may be used as part of the basis for acceptance of the item.
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QUALITY ASSURANCE POLICY Revision 49 i
The depth of vendor evaluation varies according to the complexity and function of the item involved and to the role of the vendor in acceptance of the item.
. Vendor Anoroval Upon completion of the evalurtion, satisfactory vendors are added to BGE's AVL. The vendors on this list are evaluated on an annual basis and subject to re-audit or commercial grade survey on a triennial basis to verify continued compliance with BGE's requirements.
An auditing organization such as NUPIC, another utility, a contractor to BGE, etc., may be used to verify that the vendor has developed and implemented a QA program that complies with 10 CFR 50, Appendix
)
B or a commercial grade program that complies with the requirements of BGE's procurement requirements or similar requirements.
When required by operational considerations, an order may be placed with a vendor prior to completion of the evaluation and approval process only after obtaining the Manager-NSSD's approval. BGE's acceptance of basic component items or services provided by an unapproved vendor is contingent on the subsequent NPAD evaluation and approval of the vendor as stated above.
Verificatinn of Vendar Activities Vendor surveillance, and source verification activities are conducted by qualified NPAD personnel in acconlance with written procedures or checklists. These procedures or checklists, along with the procurement documents, specify the characteristics or processes to be witnessed, inspected or verified.
Personnel performing these activities are qualified to establish whether or not a vendor is capable of providing products of acceptable quality.
The depth and frequency of vendor surveillances, verifications and audits is commensurste with the complexity and function of the item or service and the ability of the vendor to provide the necessary assurance of acceptability.
When a vendor's certificates of conformance are used as part of the acceptance of an stem or service, the validity of these documents is periodically evaluated and documented by the above mentioned processes.
Receipt NSSD is responsible for receiving and storing materials, parts, and components.
Additionally, NSSD is responsible for performing standard and special receipt inspections and coordinating testing necessary to accept SR items, designated NSR items and commercial grade items for SR use.
Standard receiving inspection ofitems is performed to assure the following:
1.
The item is properly identified and that this identification corresponds with the documentation received.
2.
Stated packaging, shipping and handling requirements have been maintained.
3.
Items have not been damaged, workmanship is of adequate quality, and the items are adequately clean in accordance with procurement document requirements.
4.
Documentation required by the Purchase Order has been received and is reviewed o assure that the item conforms to the purchase order requirements.
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i QUALITY ASSURANCE POLICY Revision 49 Special receiving inspection may be required if the item was not inspected at the source; when requested by the RDO or; as part of the acceptance basis for commercial grade items.
1 A written record of the results of the NSSD receipt inspection and the disposition of received items is maintained as part of permanent plant records.
l All SR and designated NSR items accepted and released for issue to a controlled storage area or released for installation or further work bear an acceptance tag and have documentation to support their acceptability. If traceability is lost or the documentation review is unsatisfactory, an item becomes subject to the controls established for non-conforming items.
Non-conforming items are identified and handled in accordance with Section IB.15 of this policy and, when practicable, are placed in a segregated area to prevent inadvertent installation or use until proper disposition is made.
Documentation BGE procurement documents require vendors to provide documentation identifying the purchased item and the specific procurement requirements that are met by the item.
Vendor inspection records or certificates of conformance attesting to acceptance must be in the possession of BGE before the item may be released for installation or use. However, an unacceptable item may be given a " Conditional Release" if there is reasonable assurance that it can be made acceptable after installation but before the system that contains it is considered operational. Items released under " Conditional Release" must be controlled under a non confonnance report system.
Vendor requested deviations from procurement document requirements, including nonconformances dispositioned "use-as-is" or " repair" must be submitted to BGE for evaluation and appmval of the deviation or a recommended disposition prior to shipment.
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,e QUALITY ASSURANCE POLICY Revision 49 1 B.8 IDENTIFICATION AND CONTROL OF MATERIALS. PARTS. AND COMPONENTS (5)
NSSD/NED personnel ensure that procurement documents require that SR and designated NSR items, including partially fabricated sub-assemblies, are identified and controlled to prevent the use of incorrect or defective material.
Requirements for identification by use of heat number, part number, or serial number, or by other means, are referenced or stated in procurement documents. These documents require the identification to be placed on the item or in records traceable to the item so that the function and quality of the item are not affected. This identification is required to be maintained throughout fabrication, storage, erection, installation, and use. NSSD personnel ensure traceability information is correctly transferred to subdivided materials stored in the Warehouse. User organizations ensure traceability information is correctly transferred to subdivided materials after issuance from the Warehouse. NPAD is responsible for performing periodic inspections or surveillances to verify program adherence.
Assigned NSSD personnel purchase identify, store, and issue items as specified by procurement controls and provide for maintaining the integrity of items and their traceability to associated documents during storage and issue.
BGE contractors and their sub-contractors (who are approved to work on-site under their own QA J
program) are responsible for establishing and implementing programs in accordance with specified requirements for identifying and controlling materials, parts, and components under theirjurisdiction.
Identification of items important to the function of SR and designated NSR structures, systems, and components can be traced to appropriate documentation such as drawings, specifications, purchase orders, manufacturing and inspection documents, deviation reports, and physical and chemical mill-test reports.
Receipt SR and designated NSR items received at CCNPP are receipt inspected to verify that all requirements of the procurement documents have been met. If a discrepancy is observed, such as damage or missing documentation, information to the effect is recorded on the receiving inspection report, and the discrepant item is identified as such and placed in a separate " hold" area when practicable. If the item is acceptable, it is identified to indicate acceptance and that it is approved for storage or installation and use. When groups ofitems in storage are subdivided, each subgroup is separately identified.
]
If an item is found to be or is made discrepant during processing, it is identified as such and placed in a separate area when practicable.
Acceptance documentation is required to be traceable to a purchase order, drawing, specification, requisition number, or assembly. As individual items are assembled, installed, and inspected, their acceptance-tag numbers are recorded in plant maintenance or operation records.
After completion of tests and inspections, records that document test results and traceability are kept as part of the plant records.
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Revision 49 -
- 1B.9 ' CONTROL OF SPECIAL PROCESSES Controls
' Controls have been established for writing, qualifying, approving, and issuing procedures to control such special processes as welding, heat treating, and nondestructive testing used during the operation of CCNPP. Special Process Procedures:
1.
Are prepared in accordance with applicable codes, standards, specifications, criteria, and other l
special requirements.
2.
Ensure that special processes are performed by qualified ' personnel according to qualified 1
procedures that comply with applicable regulatory sequirements.
3.
Specify requirements for control, parameters to be considered, acceptable methods of -
documentation, and the codes, standards, specifications, or criteria which govern the qualification.
4.
Define the necessary qualification of personnel, procedures, or-equipment when special processes are not covered by existing codes or standards or when quality requirements for an item exceed the requirements of established codes or standards.
l BGE contractors and their sub-contructors are responsible for controlling special processes used by them and for maintaining socords to verify that special processes are performed in accordance with requirements established by the portions of their QA programs that apply to special processes.
Qualification of Methods Procedures, equipment, and personnel connected with special processes are qualified in accordance with applicable codes, standards, specifications, or supplementary requirements as follows:
1.
Welding activities conducted by BGE are perfonned according-to welding procedure specifications qualified in accordance with applicable welding requirements of the ASME Code.
Each welding procedure specification is written, qualified, and approved in accordance with a L
controlling documented procedure. Copies of welding procedure specifications are made available to welders and, when required, to Authorized laspectors. Before contracting for welding, non-BGE welding procedure specifications and procedure qualification records are reviewed and approved in accordance with a written procedure.
2.
Heat-treating requirements included in welding procedure specifications are established in l
conformance with heat-treating requirements of the applicable ASME Code.
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3.
Nondestructive Examinations are performed to written procedures proved by actual demonstration, when practicable, to the satisfaction of the Principal Engineer-Materials l
Engineering and Inspection and, when required, the Authorized Inspector.
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i QUALITY ASSURANCE POLICY Revision 49 These procedures are prepared according to appropriate sections of the ASME Code for particular examination methods. Procedures, personnel qualifications, and the records that verify the Performance of Nondestructive Examinations are kept as nuclear plant records. Nondestructive Examination j
Procedures describing methods not described in the ASME Code and/or SNT-TC-1 A and its Supplements are at least equivalent to those recognized by the American Society of Mechanical Engineers and the American Society for Non-destructive Testing. Training programs acceptable to the Principal Engineer-Materials Engineering and Inspection are developed to complement these alternative methods and to establish the capability of personnel to perform the required examination according to BGE procedures and to the level of performance to which the individual will be certified.
Methods of Nondestructive Examination include, but are not restricted to, radiographic, j
ultrasonic, thuid-penetrant, magnetic-particle, eddy-current, visual, and leak-testing examinations. Procedures are prepared to cover these examinations in accordance with a QA Program document that details the specific examination, requirements for approval, and content of the procedure, such as cenification level, accept / reject criteria, examination coverage and sequence, surface preparation, test equipment, records required, permissible marking, cleanup l
requirements, and reference to applicable sections of the ASME Code.
Qualification of Personnel Special processes are performed by certified personnel using written process sheets, shop procedures, checklists, and travelers (or equivalent), with recorded evidence of verification as follows:
1.
BGE welders, and welders under contract to BGE, are qualified and certified in accordance with the applicable requirements of the ASME Code.
Records of the welding procedure specifications are maintained, including essential variables under which the welders are examined, and the results of the examinations. A welder is not permitted to weld SR and designated NSR items until an appropriate performance qualification record or a letter of certification is on file at CCNPP. Each welder is required to be requalified as specified in the applicable code.
2.
Non-BGE welders are not permitted to weld SR and designated NSR items until they are qualified and certified in accordance with the applicable requirements of the ASME Code.
3.
Nondestructive Examination personnel employed by or responsible to BGE are certified according to applicable sections of the ASME Code and/or SNT-TC-1A and its Supplements.
BGE employees are trained and certified in accordance with a written procedure. Non-BGE personnel are qualified to procedures approved by BGE, and their qualifications and certifications of personnel are verified according to written procedures.
Qualification records of procedures, equipment, and personnel associated with special processes conducted by BGE are filed and kept current.
The Manager-NPAD provides independent verification that special processes are performed by qualified personnel.
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QUALITY ASSURANCE POLICY IB.10 INSPECTION l
Activities that affect the quality of SR and designated NSR items are inspected as specified in approved instructions, procedures, and plans which set forth requirements and acceptance criteria to ensure that work is done in conformance with particular requirements.
Controls exercised during inspections ensure that:
1.
Personnel who perform quality verification inspections are independent of the personnel who performed the activity being inspected.
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2.
Inspection procedures or instructions, with necessary drawings and specifications for use, are l
available before inspection operations are performed.
3.
In the case of special processes, inspectors are qualified, and their qualifications comply with applicable codes and standards.
4.
Test and measuring equipment is calibrated within required limits.
5.
Inspection procedures, as applicable, specify objective acceptance criteria, prerequisites for performing inspections, limiting conditions, requirements for special equipment and quality verification inspection hold-points at which inspections are to be witnessed.
6.
Appropriate inspection requirements are established for modification, repair, and replacement.
7.
Personnel who perform quality verification inspections are qualified in accordance with appropriate codes, standards, and Company training programs, and their qualifications and certifications are kept current.
8.
Procedures for maintenance and modification are avviewed by NPAD-Maintenance Assessment personnel, or others authorized by Maintenance Assessment, to determine the need for independent inspection and the degree and method if such an inspection is required, and to ensure the identification ofinspection personnel and the documentation ofinspection results.
9.
Procedures for Nondestructive Examination, including procedures for nuclear fuel inspection and I
visual examination on nuclear fuel, are reviewed by qualified personnel in NED. Review is to determine the adequacy of procedural controls and of inspection criteria, the aced for independent inspection, and the degree and method, if such inspection is required; and to ensure the identification of qualified inspection personnel and the documentation of inspection results.
10.
Inspection results are recorded, evaluated, and retained.
inspection procedures, instructions, and checklists used by inspection personnel provide the following:
i 1.
Identification of characteristics to be inspected.
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Acceptance and rejection criteria.
3.
Description of the method ofinspection.
i 4.
Identification of required procedures, drawings and specifications.
j S.
Identification of inspector or data recorder.
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j QUALITY ASSURANCE POLICY Revision 49 l
l Verification of completion and certification ofinspection.
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- 6.
7.
- Record ofresults ofinspection.
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Pmvision for. identifying mandatory inspection hold-points for witness for an authorized inspector or BGE inapection personnel.
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. Provision for indirect control by monitoring processing methods, equipment, and personnel if direct inspection is not possible.
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' 10.
Specification of necessary measuring and test equipment including requirements for accuracy.
l The General Supervisor-Maintenance Assessment is responsible for the preparation and implementation -
of procedures for inspection and surveillance activities performed by or for Maintenance Assessment.
j (11)
Other inspections are conducted randomly to verify that overall plant operations are being conducted according to approved procedures and to ensure that the use ofjumpers is properly documented; that l
' equipment is returned to operating status after test, modification, or repair; tint instruments are properly l
l calibrated; and that personnel who perform tests am properly trained and qualified.
^
In-service inspections are performed'on pressure-containing components within the reactor coolant j
system boundary according to requirements of the TSs.
l In-service inspections and examinations on components designated Class I or Class II by the ASME l
~ Code are witnessed or otherwise verified by an authorized Code Inspector who is responsible for l
ensuring that the work is performed by qualified personnel according to written qualified procedures.
l Records of in-service inspections, results, corrective action required and taken, inspection standards i
i required for repair, and results of inspection of repairs are maintained and compared with the results of 5
j subsequent examination.
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QUALITY ASSURANCE POLICY Revision 49 1B.11 IEST CONTROL a
To demonstrate the ability of SR and designated NSR structures, systems, and components to function as designed, they are subjected to a program of surveillance and operational testing. Procedures specify the systematic development, review, approval, and conduct of tests and review of test results. Conditions such as failures, malfunctions, deficiencies, deviations, and non-conformances discovered during testing are documented and evaluated.
i Whenever testing is required to demonstrate that SR and designed NSR material, parts, components, or systems will perform satisfactorily in service, a test program is established and procedures are used that i
have been written and approved in accordance with basic requirements.
i Nuclear Engineering Department, and CCNPPD conduct tests to verify that plant behavior conforms to design criteria, ensure that failure and substandard performance are identified and controlled, and demonstrate satisfactory performance after plant modification and maintenance activities.
Written test procedures are developed, reviewed, and approved befom testing is performed. They specify instructions for testing, methods of test, test equipment, and instrumentation; and for the following as applicable-1.
Adequate and appropriate equipment.
2.
Preparation, condition, and completeness ofitem to be tested.
3.
Suitable and controlled environmental conditions.
l 4.
Mandatory inspection hold-points for witness by BGE inspection or authorized inspector personnel.
5.
' Provision for data collection and storage.
6.
Acceptance and rejection criteria.
7.
Methods of documenting or recording test data and results.
8.
Provision for ensuring that test prerequisites have been met.
Test resuhs are documented and evaluated; they are accepted or rejected by a qualified, responsible individual or group.
Results of completed tests on SR and designated NSR structures, systems and components 9er Q-List) that identify a malfunction or were out of specification are reviewed and evaluated by the F.PLC and accepted and approved by the Plant General Manager. Test records are kept in sufficient detail to make possible an evaluation of test resuhs and to show how individual tests demonstrate that SR and designated NSR structures, systems, and components and the plant as a unit can operate safely and as designed. SR and designated NSR test records are retained as plant history records.
Results of testing performed as part of receipt inspection are evaluated, accepted and approved by qualified NSSD personnel. (5)
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i QUALITY ASSURANCE POLICY Revision 49 l
1B.12 CONTROL OF MEASURING AND TEST EOUIPMENT Calibration controls have been established to prescribe the technique and frequency of calibration, maintenance, and control of measuring and test instruments, tools, gauges, fixtures, reference and
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transfer standards, and nondestructive test equipment used in measuring, inspecting, and monitoring SR and designated NSR components, systems, and structures during the operations phase of CCNPP.
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Calibration controls require each responsible group to identify measuring and test equipment and i
calibration test data related to it.
Written procedures are prepared and implemented to ensure that tools, gauges, instruments, and related test and measuring devices are of proper accuracy to verify conformance to established requirements.
l Manufacturer's Procedures are used for calibration or a procedure is prepared for each category of measuring and test equipment as necessary. 'Ihese Calibration Procedures contain the following information:
1.
Identification of the item to be calibrated and its period of calibration.
2.
Standards to be used, specific test-points, and checks, tests, and measurements to be made.
i 3.
Acceptance criteria to be used and special precautions to be taken when necessary.
i Measuring and test equipment that require calibration are assigned an identifying serial number, Instruments are calibrated at specified intervals according to the required accuracy, purpose, degree of usage, stability characteristics, and other conditions that affect the measurement.
When equipment is found out of calibration, an evaluation is made by the supervisor responsible for that equipment to determine any adverse effe:t on items previously accepted on the basis of using that i
equipment.
Test and measuring equipment that cannot be adjusted to required tolerances during calibration is identified and placed in a designated segregated area; if the equipment can be used in limited applications, the limitations are identified.
The status of each item controlled under the calibration system is recorded and maintained. Equipment is marked or records of calibrations are maintained to indicate calibration status. An interval of calibration is established for each item of measuring and test equipment and recorded on a master record of calibrations pged as a calibration schedule.
Measuring and test equipment is controlled to prevent the use of uncalibrated or defective equipment, the spread of radioactive c ontamination, the introduction of impurities into high-purity systems, and damage to or loss of equipmeat. Identification tags are placed on measuring and test equipment to indicate such special conditions as radioactive cleanliness, special limitations, or failure to meet established calibration requirements.
Measuring and test equipment is calibrated and adjusted at specified intervals, or before use, against certified standards. Reference and transfer standards are traceable to nationally recognized standards; or, where national standards do not exist, provisions are established to document the basis for calibration.
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QUALITY M;SI RANCE POLICY l
Revision 49 1B.13 HANDLING. STORAGE. AND SHIP).E j
Appropriate and special requirements for he.ndling, preservation, storage, cleaning, packaging, and shipping of SR and designated NSR items are specified in procurement documents.
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Procedures have been established to ensure that the handling, preservation, storage, cleaning, packaging, i
and shipping of SR and designated NSR items are performed in accordance with specified requirements to reduce the likelihood of d. mage, loss, or deterioration by such environmental conditions as temperature or humidity.
l Special handling, preservation, storage, cleaning, packaging, and shipping activities associated with SR and designated NSR items are performed by suitably trained personnel in accordance with specific written procedures.
l Controls have been established for the safe storage of hazardous materials. Items with a limited shelf-life are controlled to ensure that they will not be used in SR and designated NSR applications after j
expiration of designated shelf-life periods.
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QUALITY ASSURANCE POLICY Revision 49 l
1B.14 INSPECTION. TEST. AND OPERATING STATUS I
Controls have been established for the application and removal of status indicators such as tags, markings, labels, and stamps to ensure that the inspection, test, and operating status of SR and designated NSR structures, systems, and components is clearly indicated at all times.
Procedures / instructions are prepared to identify and control inspection, testing, and operating status by l
the use of logs, forms, and tags that identify the inspection, test, and operating status of structures, systems, and components; control the use ofindicators, including the authority for their application and removal; control bypassing operations, such as jumping or temporary removal of electrical leads; and identify non-conforming, inoperative, or malfunctioning structures, systems, or components.
Senior shift personnel are responsible for aligning, isolating, and appropriately tagging installed equipment and systems so that activities affecting quality can be performed.
l The Manager-NPAD is responsible for the performance of assessments to verify that the inspection, ]
I testing, and operating status of structures, systems, and components are properly identified and controlled during operation, maintenance, and testing of the plant.
l The bypassing of required inspections, tests, and other critical operations is controlled to ensure that I
bypassed inspections or tests are properly documented and that the effect of bypassing the inspection or test is evaluated by the organization responsible for specifying the inspection or test. Controls have been established to ensure that the status of non-conforming, inoperative, or malfunctioning SR and designated NSR structures, systems, or components is identified to prevent inadvertent use.
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QUALITY ASSURANCE POLICY Revision 49 IB.15 NONCONFORMING MATERIALS. PARTS. OR COMPONENTS (6)
Controls have been established for identifying, documenting, segregating, reviewing, dispositioning, and notifying affected organizations ofIssues affecting materials, parts, or components (i.e., items).
Issues affecting nuclear plant items are referred to as nonconformances. Nonconfonnances are hardware deficiencies which render the quality of an item unacceptable or indeterminate.
Any individual identifying an actual or suspected nonconforming item is responsible for documenting and reporting such nonconforming item promptly to supervisory or NPAD personnel.
Nonconforming items are controlled by documentation, marking, logging, tagging, or physical segregation to prevent inadvertent installation or use.
Nonconformance control documents are submitted to responsible departments for resolutiort. Designated personnel have the responsibility and authority for approving the resolution of nonconformances.
Nonconformance control documents are not closed until corrective actions have been completed.
Nonconforming items are dispositioned as rework, repair, reject, or accept-as-is. The disposition of a repair or accept-as-is nonconformance is treated as a design change and is evaluated and approved or rejected by the RDO.
Reworked, repaired, and replacement items are inspected and/or tested in accordance with the original inspection and/or test requirements or acceptable alternatives to ensure that critical characteristics possibly affected by the nonconformance remain acceptable.
Nonconforming items may be conditionally released for installation, test, energization, pressurization, or use if the conditional release will not adversely affect nor preclude identification and correction of the nonconfonnance. Nonconforming. items required for Technical Specification operability may be released for use following verification that the nonconforming item meets all operability requirements specific to its function and is approved for use by authorized Operations personnel. Conditionally released items will be resolved in accordance with this Section. Conditional release evaluations are i
documented, reviewed, and approved prior to implementation.
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QUALITY ASSURANCE POLICY Revision 49 iB.16 CORRECUVE ACTION (6)
Controls have been established to ensure that Issues are identified, documented, reviewed, and conected.
'These controls are applied to deficiencies associated with the programmatic content, r ocess, and implementation of the Quality Assurance Program as well as nonconformances (ref Section 1B.15).
Corrective actions are implemented by responsible personnel and may include immediate actions, remedial actions and/or actions to prevent recurrence, based on the significance and extent of the Issue.
Issues identified as potentially impacting the safe production of nuclear power are evaluated for Technical Specification Operability, NRC Reportability, Nuclear Safety Significance, and if the activity should be stopped. The VP-NED, or designated alternate, is informed of Issues which require NRC notification.
Corrective action verification is performed for Significant Issues prior to the close-out of the corrective -
action document. Verification is performed and documented by individuals not dimctly involved with implementing the conective action (s). Unacceptable conective action (s) are reported to supervisory or management personnel dimetly responsible for resolving the Issue and to progressively higher levels of management until the Issue is resolved.
Significant Issues require a root cause analysis and the implementation of corrective actions to prevent recurrence and are reported to management for review and assessment.
Issues are periodically analyzed for the identification of adverse quality trends. The existence of an adverse quality trend is resolved in accordance with this section. A Trend Report is issued to miagement at intervals specified in approved procedures.
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QUALITY ASSURANCE POLICY l
Revision 49 l
IB.17 OUALITY ASSURANCE RECORDS I
Controls have been established to ensure that quality assurance records are maintained to provide documentary evidence of the quality of SR and designated NSR items and activities. Applicable design l
specifications, procurement documents, test procedures, operational procedures, TSs, and other documents specify records that should be generated, supplied, or maintained by and for BGE.
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Quality assurance records are classified as lifetime or non-pu.nanent.
Lifetime records, maintained for particular items for the life of CCNPP, for particular items have significant value in relation to demonstrating capability for safe operation; maintaining, reworking, repairing, replacing, or modifying an item; determining the cause of an accident or malfunction of an l
item; and providing required baseline data for in-service inrpection.
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The following records shall be retained for the duration of the Facility Operating License:
a.
Records and drawing changes reflecting facility design modifications made to sy:;tems and equipment described in the Final Safety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of facility radiation and contaminadon surveys.
- d. Records of radiation exposure for all individuals entering radiation control areas.
Records of gaseous and liquid radioactive material released to the environs.
e.
f.
Records of transient or operational cycles for those facility components identified in Design Authority Program procedures.
g.
Records of training and qualification fcr current members of the plant staff.
- h. Records ofin-service inspections performed pursuant to the Technical Specifications.
I.
Records of Quality Assurance activities identified in this NRC approved QA Policy as lifetime records.
J. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuut to 10 CFR 50.59.
- k. Records of meetings of the POSRC, the Procedure Review Committee, and the OSSRC.
1.
Records of the service lives of all safety related snub'oers including the date at which the service life commences and associated installation and maintenance records.
Non-permanent records, which show evidence that a SR and designated NSR activity was performed in accordance with applicable requirements, are retained for periods sufficient to ensure BGE's ability to reconstruct significant events and to satisfy applicable regulatory requirements. Retention periods are based on requirements specified in QA Program documents. Retention periods shall be documented.
The following records si.all be retained for at least five years:
Recordr, and logs of facility operation covering time interval at each power leve5 a.
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QUALITY ASSURANCE POLICY Revision 49
- b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
All Reportable Events.
- d. Records of surveillance activities, inspections and calibrations required by the Technical Specifications.
c.
Records of reactor tests and experiments.
i f.
Records of changes made to Operating Procedures.
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- g. Records of radioactive shipments.
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- h. Records of scaled source and fission detector leak tests and results.
- i. Records of annual physical inventory of all sealed source material of record.
Procurement documents specify vendor responsibilities for the generation, retention, and submission to BGE of quality assurance documentation related to the fabrication, inspection, and test of SR and designated NSR items and services.
Inspection and test records contain the following as appropriate; 1.
Description of the type of observation.
2.
Date and results ofinspection or test.
3.
Information related to noted discrepancies, including action taken to resolve them.
4.
Identification of inspector or recorder of data.
5.
Statement as to acceptability of results.
Controls have been provided to ensure that records are protected from possible destruction.
Within established time intervals, completed lifetime records are transmitted to the Records Management Unit for incorporation into the Long Term Records Storage and Retrieval System.
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QUALITY A"SURANCE POLICY Revision 49 IB.18 AUDITS Ir.ternal audits are performed by BGE's NPAD to ensure that activities and procedures established to implement the requirements of 10 CFR 50, Appendix B, comply with BGE's overall QA Program. These audits are performed under the cognizance of the OSSRC and provide a comprehensive independent verification and evaluation of quality-related activities and procewres. Audits ensure the effective and proper implementation of BGE's QA Program._ Audits of selected aspects of operational phase activitics are performed with a frequency commensurate with their strength of performance and safety significance and in such a manner as to assure that an audit of all safety-related functions is completed within a period j
of two years. (Audits specified in regulations are performed at the frequencies noted therein.) 'In addition to the audit subjects specified in Regulatory Guide 1.33 Revision 2 and ANSI N18.7-1976/ANS-3.2, audits performed within a period of two years shall also encompass: the Facility Fire Pmtection
- program and implementing procedures; an independent fire protection and loss prevention program inspection and audit utilizing either qualified offsite licensee personnel or an outside fire protection firm; the radiological environmental monitoring program and the results thereof; the Offsite Dose Calculation Manual and implementing procedures; the Process Control Program and implementing procedures for processing and packaging of radioactive wastes; the performance of activities required by tM QA Program for effluent and environmental monitoring; and the performance of activities required by the QA Program to meet the criteria of 10 CFR 50, Appendix B. Audits shall also encompass any other area of facility operation considered appropriate by the OSSRC or the VP-NED. An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant
- at least once per 36 months. (19)
Vendor audits are performed to evaluate QA programs, procedures, and activities. Audits of major vendors are made early enough to ensure compliance with all aspects of BGE's procurement documents.
Additional audits are performed as required to ensure that all requirements of BGE's QA Program are properly implemented according to procurement documents.
Audits are performed in accordance with pre-established written procedures or checklists by qualified NPAD personnel who have no direct responsibility for the work being audited. Technical specialists from other BGE departments and outside consultants may assist as necessary in performing audits.
Audits include objective evaluation of quality-related practices, procedures, instructions, activities, and items, as well as review of doc :ments and records.
Reports of audits are analyzed and documented. Results that indicate the QA Program to be inadequate, ineffective, or improperly implemented, including the need for re-audit of deficient areas, are reported to the Manager and Supervisor of the audited activity. Controls have been established for verifying that
(
conective action is taken promptly to correct noted deficiencies.
To ensure that BGE's NPAD complies with the requirements of BGE's QA Program, an independent management audit of NPAD activities is performed annually by a Joint Utility Management Audit j
(JUMA) Team.
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e QUALITY ASSURANCEPOLICY Rsvision 49 TABLE IB-1 BALTIMORE GAS AND ELECTRIC COMPANY'S POSITION ON GUIDANCE CONTAINED IN INDUSTRY STANDARDS AND REGULATORY GUIDES Revision ofIndnetrv Standards Anoticable to the I
Raltienare Gas and Electric Onnlity d==urance Pronram Requirement Some of the Industry Standards listed in Section IB.2 identify other Standards that are required, and some Regulatory Guides define the revisions of those Standards that are acceptable to the NRC.
p.ennne BGE's QA Program was developed to respond to the specific revision of the documents listed in Section IB.2 and is not necessarily responsive to other documents listed in the referenced Industry Standards.
ANSI N18/7\\ANS 3.2 - 1976 fe== 1 (19)
Requirement Section 5.2.15 requires that plant procedures shall be reviewed by an individual knowledgeable in the area affected by the procedure no less frequently than every two years to determine if changes are necessary or desirable.
Response
Routine plant procedures do not receive biennial reviews, but are subject to programmatic controls which continually identify needed procedure revisions.
Routine plant procedures that have not been used for two years are reviewed consistent with pre-evolution briefing requirements. Additionally, precedure use and adherence requirements state clear procedure compliance expectations and the need '.o stop the job if a procedure cannot be performed as written.
j Non-routine plant procedures whose usage may be dictated by an event (such as Emergency Operating Procedures, Abnormal Operating Procedures, and Emergency Response Plan Implementing Procedures) receive biennial reviews according to administrative procedures.
Applicable plant procedures are reviewed following an unusual incident and following any modification to a system.
The biennial audit of the Procedures Program includes a representative sample of plant procedures. The audit helps ensure the acceptability of the procedures and verify that the Procedures Program is being implemented effectively.
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QUALITY ASSURANCE POLICY Revision 49 Reason Programmatic controls meet the intent of the biennial review process from both a technical and practical standpoint because they constitute dynamic, rather than static, procedure review methodology. 'Ihus, the biennial review process is redundant to the established programmatic controls and is unnecessary.
Item 2 (10)
Requirement Section 5.2.2 specifies that temporary procedure changes that clearly do not change the intent of the approved procedure shall as a minimum be approved by two members of the plant staff knowledgeable in the areas affected by the procedure; and at least one of these individuals shall be the supervisor in charge of the shift and hold a senior operators' license on the unit affected.
i
Response
BGE does not require the Shift Supervisor to be the Senior Reactor Operator (SRO) approving temporary changes to procedures; any active SRO (either on-shift or on-staff) may provide the SRO approval for procedure changes.
Esanon Many proposed temporary procedure changes do not require the Shift Supervison's immediate attention or knowledge of the change since they do not affect plant safety. Other SROs are available and qualified to perform this task since the Shift Supervisor's detailed miew of the proposed change is not necessary to ensure plant safety.
Requiring the Shift Supervisor to review all changes is burdensome and contrary to plant safety in light of the total number of procedures that exist and the time the Shift Supervisor must dedicate to ensuring the plant is safely operated and maintained. Additionally, our Technical Specification requires this approval be from someone holding an SRO license (not necessarily the Shift Supervisor).
REGULATORY GUIDE 1.33-197Q Renirement Section C., Regulatory Position, item 4, states:
Section 4.5, " Audit Peipain," of ANSI N18.7-1976/ANS 3.2 states that audits of selected aspects of operational phase activitics shall be performed with a frequency conamensurate with their safety significance and in such a manner as to ensure that an audit of all safety-related functions is completed within a period of 2 years. In amplification of this requirement, the following program elements should be audited at the indicated frequencies:
- a. The results of actions taken to correct deficiencies that affect nuclear safety and occur in facility equipment, structures, systems, or method of operation - at least once per 6 months.
i s
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QUALITY ASSURANCE POLICY Rsvision 49
- b. The conformance of facility operation to provisions contained within the L
technical specifications and applicable license conditions - at least once l
per 12 months.
He performance, training, and gaalifications of the facility staff c.
-- at least once per 12 months.
Response
The audit frequency for all safety-mlated functions is at least once every two years (except as otherwise required in regulations).
Reason The more frequent audit intervals do not allow BGE management the flexibility to devote auditing resources consistent with the strength of performance and safety significance of an activity. Experience has shown that some audits are performed more frequently than deemed appropriate for the function.
ANRI N18.1 3/R/71 Ite m 1 Requirement Paragraph 4.2.2 states that at the time of initial core loading or appointment to the active position, the Operations Manager shall hold a Senior Reactor Operator's (SRO) License.
Paragraph 3.2.1 states that positions at the #metional level of Manager are those to which are assigned broad responsibilities for directicm cf ma 3r aspects of a nuclear power plant. His functional level generally includes the plant manager (plant superintendent, or other title), his line assistants, if any, and the principal members of the operating organization reporting directly to the plant manager and having overall responsibility for operation of the plant or for its maintenance or technical service activities.
Response
Baltimore Gas & Electric has two positions in its organization, Superintendent-Nuclear Operations and General Supervisor-Nuclear Plant Operations. Neither of these positions needs to individually meet all of the requicements of both paragraphs 3.2.1 and 4.2.2. The Superintendent-Nuclear Operations will satisfy paragraph 3.2.1 and most of 4.2.2 except that he will not maintain an SRO license. Instead, the Superintendent-Nuclear Operations will hold or have held an SRO license. The GS-NPO will hold and maintain an SRO license. The GS-NPO satisfies paragraph 4.2.2, but he does not satisfy 3.2.1 because r
he does not report directly to the plant manager.
)tenson
- The Superintendent Nuclear Operations will hold or have held an SRO license, as opposed to having a license at the time of appointment to the position. He will have an excellent understanding of plant operations. The GS-NPO will not only hold an SRO license at the time of appointment to the position, but he will maintain the license. De GS-NPO directly supervises the operating shift organization, whereas the Superintendent-Nuclear Operations is also responsible for operations procedure development, modifications acceptance, and operations / maintenance coordinations. The Superintendent-Nuclear Operation's level of supervision does not require current in-depth and plant specige knowledge L
which results from maintaining an SRO license.
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i t.
a.
QUALITY ASSURANCE POLICY-Revision 49 Itean 2 (17).
p.m.im.
i Paragraph 3.2.2 states that supervisors are persons principally responsible for directing the actions of l-operators, technicians, or repairmen. Those positions usually designated as intermediate and first line l
. supervisors are included in this category, j
l
. Paragraph 4.3.2 states that supervisors not requiring Atomic Energy Commission (AEC) licenses shall j
i have a high school diploma or equivalent and a minimum of four years of experience in the craft or i
~ iscipline he supervises.
d
Response
i
. Baltimore Gas and Electric has three supervisory positions in its organization - Supervisors, and in some cases Assistant General Supervisors and General Supervisors - which are organizationally equivalent (when supervising technicians / repairmen) to the positions described in paragraph 3.2.2 of ANSI N18.1-I 3/8/71.' All these individuals need not possess the four years of craft / discipline experience required by paragraph 4.3.2. Instead, at least the first line supervisor shall possess four years experience in the i
craft / discipline he supervises while other supervisors in the organization may be selected to fill supervisory positions based on possessing a minimum of an Associate's Degree, with four years of related technical experience, and demonstrated supervisory ability. (18) Additionally, all first line and intermediate supervisors shall have at least a high school diploma or equivalent.
Reason To provide a balanced and broad base of supervisory ability within the site organizations made up of technicians / repairmen, it is desirable to include as supervisors both individuals with extensive craft / discipline experience accrued through field work and individuals with related education and i
experience who have demonstrated the ability to effectively supervise.
Requirement Subsection 3.2 outlines requirements for domineralized water.
Response
BGE specifications for demineralized water are different than the specifications outlined in the standard.
j i
Essaon BGE specifications for demineralized water are consistent with guidelines provided by the Nuclear Steam Supply System supplier. BGE specifications are generally more restrictive than those specified by ANSI N45.2.1.
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i QUALITY ASSURANCE POLICY i
Revision 49 j-ANSI N45.2.2 - 1972 l
l i
Requirei y j
6 Subsecdon 2.4 could be interpreted to mean that on-site and off-site personnel who perform any I
inspecton, exunination, or testing activities related to the packing, shipping, receiving, storage, and handling ofiteras for nuclear power plants shall be qualified in accordance with ANSI N45.2.6.
Response
i i
BGE requires that only persons who are responsible for approving items for acceptance shall be qualified
- in accordre.cc with Regulatory Guide 1.58 (which endorses ANSI N45.2.6) and that personnel who verify that storage areas meet requirements will be qualified to either Regulatory Guide 1.58 (which endorses ANSI N45.2.6) or ANSI N45.2.23.
Reason Our receipt inspection procedures requim persons who approve items for' acceptance to be qualified m accordance with Regulatory Guide 1.58 (which endorses ANSI N45.2.6). NPAD assessors verify that storage areas meet requirements. ~ All other inspection, examination, and testing activities are subject to review by persons qualified to Regulatory Guide 1.58 (which endorses ANSI N45.2.6).
Item 2 Requirement The second sentence of Subsection 2.4 requires that:
Off-site inspection, examination, or testing shall be audited and monitored by personnel who are qualified in accordance with ANSI N43.2.6.
Response
BGE uses personnel qualified in accordance with ANSI N45.2.23 to perform auditing and monitoring functions.
Brason The qualification requirements for auditos cannot always be met by persons qualified to Regulatory Guide 1.58 (which endorses ANSI N45.2.6).
l.
Ite m 3
~
Requirement Subsection 2.7 requires that activities covered by the Standard shall be divided into four levels, though recognizing that within the scope of each level there may be a range of controls depending on the importance of the item to safety and reliability.
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QUALITY ASSURANCE POLICY Revision 49 Resnonse 1.
The level of protective measures defined by Subsection 2.7 are applied to Basic Component purchases.
2.
Personnel of BGE's Nuclear Engineering Department (NED) will determine the level of protective measures to be applied to Commercial Grade purchases.
Reason BGE's position is as follows:
1.
For Commercial Grade items, it is not always possible to assign a level of classification in accordance with ANSI N45.2.2, as many items are purchased after they have been packaged by the manufacturer and shipped to his local agent, the wholesaler.
2.
Experience has shown that the level of protection assigned to Commercial Grade items by vendors is adequate.
Item 4 Reauirement Subsection 3.0 specifies detailed requirements for packing items for each level defined in Subsection 2.7.
Rnnonse BGE has arplaced Section 3.0 with the following:
1.
Packaging for Shipment to BGE Personnel of BGE's NED or NSSD shall ensure that procurement documents for Basic Component and Commercial Grade item purchases either indicate that the normal methods of packaging and shipment used by industry in general are acceptable for the items being procured or specify the level of protection assigned to the item and the requirement that the vendor conform to applicable requirements for items in that classification defined in Regulatory Guide 1.38, Rev. 2 - March 1977.
2.
The normal methods of packaging used by the industry in general are acceptable for items being procured as Commercial Grade.
3.
Packaging for Storage by BGE In general the packaging used by the vendor to ship items for all types of purchases to BGE need not be retained after the item is received by BGE, provided that the item is stored in an area that meets the requirements for a storage area for the level of protection assigned to the item. Special or unique items, however, may require special protective measures. For such unusual items, the Department that initiated the purchase, together with NED, or NSSD shall identify if any of the requirements of Section 6.4.2 of ANSI N45.2.2 1972 apply.
Reason l
1.
This substitution will ensure that the item will receive adequate protection during shipment and l
storage, thus eliminating unnecessary restrictions and enabling BGE to use commercial sources to the utmost.
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QUALITY ASSURANCE POLICY I
Revision 49 l
2.
Experience shows that industrial practices for packaging Commercial Grue items nre adequate for most applications.
Item 5 Reauirement Section 4.0 defines shipping requirements related to the protection levels assigned to items.
Response
. BGE has replaced Section 4.0 with the following:
1.
Shipping to Baltimore Gas and Electric BGE will invoke the requirements for shipping specifid in Section 4.0 of ANSI N45.2.2 - 1972 on Basic Component purchases only when NED or FEMD personnel have specified in procurement documents that the item shall be packaged in conformance with ANSI N45.2.2, Section 3.8.
BGE will not invoke the requirements of ANSI N45.2.2 -1972, Section 4.0, on Commercial Grade item purchases.
j 2.
. Shipping from Baltimore Gas and Electric Items shipped from BGE need not conform to any of the requirements of ANSI N45.2.2, but the organization that packs and handles the item shall provide roughly the same level of protection that the item was given during shipment to BGE.
Reason If engineering personnel have determined that the vendor's methods of packaging are acceptable, they have already determined that the supplier's methods of shipping are adequate. As items are shipped from BGE only for repair, the detailed requirements specified in Section 4.0 of ANSI N45.2.2 are not necessary.
Item 6 l
Reanirement Subsection 6.4 gives detailed requirements for care ofitems in storage, according to the protection levels assigned to the items.
Response
l BGE does not require items to be stored in the packing used for shipment if the storage level in the area provides the same protection as the level oipacking assigned to the items. Caps, covers, etc., will be l
required only if specified by NED or NSSD personnel during the procurement process. If an item is taken from one storage area to another, however, the persons who move it are responsible for ensuring, as applicable, that additional packing is supplied to give adequate protection during transportation.
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QUALITY ASSURANCE POLICY -
Revision 49 Raasan The degree of protection given an item during storage should be tailored to the importance of the item to safety and the probability of deterioration during storage; to base storage requirements purely on the ategories in Subsection 2.7 of ANSI N45.2.2 - 1972 is impractical. BGE requires NED or NSSD personnel to specify requirements more closely related to the actual function of items and to storage conditions.
Item 7 Requirement Subsection 7.3.3 requires compliance with a series of ANSI documents.
Response
BGE controls for the use of hoisting equipment are compatible with the Standards listed in Subsection 7.33 of ANSI N45.2.2, although at the discretion of the Plant General Manager, they need not be compatible with documents referred to in these documents.
Reason Lower-level documents refermd to in the documents listed in Subparagraph 7.3.3 will not necessarily affect the ability of BGE personnel to properly handle SR items and could lead to confusion.
ANSI N4M111 - 1973 188m.1 Requirement Subsection 2.1 outlines housekeeping cleanliness requirements for five designated zones.
R = nonce BGE has established three classes for cleanliness requirements. There is no class equivalent to the ANSI Zone 1. Requirements of ANSI Zones 4 and 5 have been consolidated into BGE's class 3.
Reason 1.
ANSI Zone I level of cleanliness applies to new construction activities.
2.
Where required, smoking restrictions are posted for BGE's class 3 areas.
llanL2 Requirement Subsection 2.1 requires for Zones I, II, and III, that a written record of the entry and exit of all personnel and material shall be established and maintained.
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QUALITY ASSURANCE POLICY l
L Revision 49
Response
l BGE has established the following methods for personnel and material accountabilityi 1.
Written accountability.
2.
Where possible tethering of tools and materials to permanent plant structures or persons.
3.
Post-maintenance close-out l'nspections.
Reason BGE's three methods of accountability offer the same level of control as that required by the standard.-
h Requirement The last paragraph of Subsection 6.2.1 (Equipment Tests) states:
Items requiring calibration shall be tagged or labeled on completion indicating date of calibration and identity of person that performed the calibration.
I i
Response
i The new calibration program at Calvert Cliffs does not use calibration stickers that contain date of calibration and identity of person that performed the calibration. The new calibration stickers indicate that the instrument is periodically calibrated according to the calibration program. The sticker, a green
}
"C," means the instrument is in the program.
Ecanon l
In the past, the date of calibration noted on the instrument was important because the calibration history of preventive maintenance was not kept on computer.
Computer tracking systems and trending programs did not exist. In the new system, the date of calibration being on the sticker is not necessary because the date of calibration and the identity of the person that performed the calibration is retnevable
)
in the PM history in Nucicis according to equipment ID. Calibrations of instruments are scheduled and i
tracked by computer. We are going into a real predictive and preventive maintenance calibration program.
Calibration frequencies will be shifted based on calibration history, PRAs, vendor's recommendations, and instrument use.
A database exists which controls what instruments are added to or deleted from the program. By maintaining the database, we ensure that no instruments are identified as calibrated that are not. In the new program instruments identified as calibrated are kept up to date and specific information is kept on computer with no need for that information to be on the sticker.
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I QUALITY ASSURANCE POLICY Revision 49 i
Item 1 Requirement Subsection 1.2 states in part, he requirements of this standard apply to personnel who perform inspection, examination, and tests during fabrication prior to and during receipt of items at the construction site, during construction, during pre-operational and startup testing, and during operational phases of nuclear power plants.
Rennonne-A Personnel of BGE's NPAD who perform independent verification through inspections, examinations, or tests at the plant site during operational phases of the nuclear power plant are required to be qualified in accordance with Regulatory Guide 1.58 (which endorses ANSI N45.2.6) or to ANSI N18.1,1971. All l
other BGE personnel who perfonn inspection, examination, and testing functions associated with normal operations of the plant are qualified either to Regulatory Guide 1.58 (which endorses ANSI N45.2.6) or to ANSI N18.1 - 1971.
R eason-A 1.
'Ihe indiviJuals who perform inspection, examination, and testing functions associated with normal operation of the plant, such as maintenartce and certain technical reviews, are normally qualified to ANSI N18.1 - 1971.
2Property "ANSI code" (as page type) with input value "ANSI N18.1 - 1971.</br></br>2" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..
Some testing activities conducted during normal operation of the plant, such as surveillance testing, do not require that test personnel meet the requirements specified in Paragraph 4.5.2 of ANSI N18.1 for technicians. Personnel qua';ted to Regulatory Guide 1.58 (which endorses ANSI N45.2.6) are adequately qualified to cow *cct smh testing.
Resnonse-B j
BGE does not always require vendor personnel perfonning inspection or test activities to comply with the requirements of Regulatory Guide 1.58 (which endorses ANSI N45.2.6) but evaluates the need for invoking Regulatory Guide 1.58 (which endorses ANSI N45.2.6) on the vendor during the review of procurement documents. The requirements are not applied to procurement classified as Commercial Grade.
Reason-B 4
BGE's position is as follows:
1.
For replacement items purchased as Commercial Grade Items, the purchaser may not impose nuclear unique requirements on the vendor. Additionally, items may be manufactured before placement of the purchase order and the vendor may not be required to maintain records of the performance of inspections or tests.
l 2.
For Basic Component Purchases, the qualification requirements for inspection, examination, and test personnel are determined by:
a.
Item status (new or replacement).
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QUALITY ASSURANCE POLICY Revision 49 b.
Complexity and impodance ofitem.
c.
Manufacturer's QA program approval level (Appendix B, ANSI N45.2, etc.).
Rennonu-C t
BGE does not require personnel who perform specific limited and repetitious inspection functions, such i
as inspection for removal or replacement of snubbers, to be trained as required by Regulatory Guide 1.58 (which endorses ANSI N45.2.6).
Reason-C inspections, examinations, or tests that are repetitious or of limited scope need not be performed by
' individuals qualified to the requirements of Regulatory Guide 1.58 (which endorses ANSI N45.2.6) provided that they receive instruction in the following:
1.
Activities to be verified.
2.
Acceptance criteria.
3.
Method of documenting results.
4.
Method of reporting deficiencies.
The person responsible for the inspection activity ensures that such instruction is given to inspectors before they perform specific inspection functions, and that both this training and the acceptability of the results of the inspection are documented.
R eenonse-D When it is necessary to monitor the avivities of a vendor, BGE uses personnel qualified as auditors in accordance with ANSI N45.2.23 or inspectors in accordance with Regulatory Guide 1.58 (which endorses ANSI N45.2.6).
Reason-D Both Regulatory Guide 1.58 (which endorses ANSI N45.2.6) and ANSI N45.2.23 establish training requirements suitable for monitoring vendor activities.
Item 2 Requirement Table I specifies that Level 111 personnel shall be capable of qualifying Level 111 personnel.
Response
When there is only one level til position or when a new Level til position is created, BGE personnel with the title General Supervisor, or higher, qualify Level 111 personnel.
Reason BGE personnel in these grades are capable of certifying Level III personnel without being trained as Level 111 inspectors.
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QUALITY ASSURANCE POLICY Revision 49 NOTE:
Regulatory Guide 1.58 (which endorses ANSI N45.2.6-1978) states in part, under item 6 of Regulatory Position, that..."In addition to the recommendations listed under Section 3.5 (of ANSI M45.2.61978) for Level I, II, and III personnel, the candidate should be a high school graduate or have earned the General Education Development equivalent of a high school diploma....". Based on the NRC letter dated January 17, 1985 from nomas T. Martin to A. E. Lundvall, Jr., the above educational requirements will be~ implemented for inspection, l
examination, and testing personnel hind or assigned after November 27, 1984, in addition to the present conimitment to ANSI N45.2.6-1978 for the qualification of such personnel.
11A51 Reauiramant Section 4.0 titled " Receipt" gives instructions for mceipt controls.
p m onne BGE applies these requirements only to the receipt of records by the Plant History File.
Reason Most records received by such organizations as Receiving Inspection, Engineering, etc., are not shipped in a manner that makes these requirements applicable. Dese requirements are applicable, however, when the records are finally turned over to the Plant History File.
Item 2 Requirement Subsection 5.6.1 reads as follows, " Design and construction of a single record storage facility shall meet the following criteria:" Items a) and b) of the subsection state that:
"a)
Reinforced concrete, concrete block, masonry, or equal construction."
"b)
A floor and roof with drainage control. If a floor drain is provided, a check valve (or equal) shall be included."
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QUALITY ASSURANCE POLICY Revision 49 i
Raennnte>Rmmenn j
Item a-l l
l The intent of this requirement is both structural integrity and fire resistance, This vault is entirely l
enveloped by a structurally sound, fire resistive building. Second, the vault rests on a reinforced slab on grade and its walls extend fully to the underside of the stmetural deck. Third, the walls of the vault are constructed of gypsum wallboard on metal studs per Underwriters Laboratory Test Number U412, assuring the equivalent of 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> fire resistive construction. This is equal construction to concrete block l
in terms of fire protection. The walls carr integrity to that needed ofconcate block.' y no structural load; hence, they provide equival (See footnote).
Response / Reason l
Item b Again, the vault is contained within an environmentally protected building. As such, it has no roof, or need for floor drain.1 (See footnote).
Item 3 Esquirement Subsection 5.6 allows only the dual facility defined in Subsection 5.6.2 as an alternative to the single facility defined in Subsection 5.6.1.
Remance BGE allows the following alternative storage requirements for organizations other than the Records i
Management Unit:
Organizations that originate records and do not transfer them to the Records Management Unit within 30 days of completion shall establish one of the following three controls as alternatives to the requirements specified for the Records Management Unit:
1.
Duplicate Storage Either A or B.
A.
Within 30 days of completion of a record, a duplicate record file shall be established.
'Ihis activity shall be controlled by procedures which provide for the following:
1.
Assignment of responsibility for records.
]
2.
Description of storage area.
3.
Description of filing system.
l l
l These responses have been forwarded to the NRC by the BGE letter dated 02/11/83 from Robert G. Nicitets, Sr. Facilities Project Administrator, Real Estate and Office Services Department, to Terry L. Harpster, Chief QA Branch, Division of QA, Safeguards and Inspection Programs, IE. USNRC. These responses have also been accepted by the NRC in their letter dated 04/22/83 from Waher P. Hanss, Deputy Chief, QA Branch, Division of Quality Assurance, Safeguards, and Inspections Programs, Office of laspection and Enforcement.
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l QUALITY ASSURANCE POLICY Revision 49 4.
An index of the filing system.
5.
Rules governing access to and control of files.
6.
Methoo, nr maintaining control of and accountability for records removed from the file.
7.
Method for filing supplemental information and disposing of superseded or obsolete records.
8.
Method for preserving records to prevent deterioration.
9.
Method for maintaining specially processed records that are sensitive to light, pressure, or temperature.
10.
Transfer of duplicates to the Records Management Unit within two years of completion ofrecords.
B.
Make arrangements with at least one other department that receives a copy of each document to subject this other copy to the controls specified above.
2.
Fire-resistant Building Storage Records shall be stored in steel cabinets located in a fire-resistant building or a non-combustible building with a fire suppression system.
The procedural controls defined for duplicate storage shall be applied.
3.
Non-fire-resistant Building Storage Within non-fire-resistant facilities, records shall be stored in UL one-hour-minimum fire-rated storage cabinets and be subject to the procedural controls defined for duplicate storage.
BGE defines a Fire-resistant Building as follows:
A facility constructed to resist the initiation or spreading of fire; non-combustible and/or fire-suppressive materials used; building certified as fire-resistant by the Risk Management Unit of BGE's Finance Department.
Reason Although these alternatives are compatible with standard methods of handling records, they do not materially decrease the level of protection afforded to the records.
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QUALITY ASSURANCE POLICY Revision 49 ANSI N45.2.23 - 1978
{
i hem 1 Reanir-ne
}
2.3 Qualification of Lead Auditors Section 2.3.1 requires prospective Lead Auditors to obtain a minimum of ten credits under the scoring system defined in paragraphs 2.3.1.1-2.3.1.4.
Response
BGE has revised the scoring system as follows:
1 Education and Experience J
The prospective Lead Auditor shall have accumulated a minimum of ten credits under the i
following scoring system:
1.0 Education (4 credits maximum) 1.1 For the Associate degree for an accredited institution, score one credit, if the degree is in engineering, physical sciences, mathematics, or quality assurance, score two credits. Or, for the Bachelor degree from an accredited institution, score two credits; if the degree is in engineering, physical sciences, mathematics, or quality assurance, score three credits.
1.2 For the Master degree in engineering, physical sciences, business management, or quality assurance from an accredited institution, score one credit.
1.3 For the successful completion of part of the required curriculum for an Associate, Bachelor, or Master degree, score a corresponding percentage of the credits specified above for the degree.
1.4 For the successful completion of Navy Nuclear Training, its equivalent in another armed service, or the training required for becoming a licensed operator in a commercial nucicar power plant, score two credits.
2.0 Experience (9 credits maximum) 2.1 Technical Experience (5 credits maxinmm)
For experience in engineering, manufacturing, construction, operation, or maintenance, score one credit for each full year.
2.2 Nuclear Experience if two years of technical experience have been in the nuclear field, score one additional credit.
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o QUALITY ASSURANCE POLICY Revision 49 2.3 Quality Assurance Experience if two or more years of the technical experience have been in quality assurance or quality control, score two additional credits. Persons whose work activities are controlled by the QA Program but who are not full-time members of NPAD may be awarded half the credits that would be given to a person with specific quality assurance experience.
2.4 Audit Experience if two or more years of the technical experience have been in auditing, score one additional credit.
2.5 Supplemental Experience i
Persons who have a proportion of the experience specified in 2.1-2.4 may be awarded a corresponding percentage of the credits specified.
2.6 Time exclusively spent in training does not apply as credit toward experience requirements for lead auditors.
3.0 Training (2 credits maximum)
Persons who have successfully completed the training requirements of ANSI N45.2.23 may be given two credits.
4.0 Rights of Management (2 credits maximum)
The Manager-NPAD, may grant additional credits for other performance factors applicable i
to auditing as follows:
4.1 For certification of competence in engineering or science related to nuclear power plants, or in quality assurance specialties, issued and approved by a State Agency or National Professional or Technical Society, score two credits.
4.2 For nuclear experience in excess of 2 years, score one credit for each two years j
experience.
43 For practical experience that can be related to power plants, in excess of 5 years, score one credit for each two years of experience.
Panson BGE is in agreement with the basic purpose of ANSI N45.2.23-that is, to establish minimum educational or experience requirements for Lead Auditors. We think, however, that the system of credits outlined in ANSI N45.2.23 tends to reduce the size of the pool of potential replacement auditors without making redeeming improvement in the capabilities of persons selected.
We calculated the credit score of 11 of our present Lead Auditors at the time they were appointed Lead Auditors. Six had completed Navy Nuclear Training and spent several years in the Navy Nuclear Program. Four of these scored only 8 credits total, including 2 credits allowed by paragraph 2.3.1.4 of ANSI N45.2.23 for rights of management based on their having completed the BGE,_QA training programs for Lead Auditors.
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1 QUALITY ASSURANCE POLICY Revision 49 l
One of our auditors, with neither nuclear nor power plant experience, had a credit score of 12 because he held a Bachelor's degree in engineering and was a professional engineer with over 5 years design i
experience.
Because all of these individuals have acted as Lead Auditors satisfactorily for several years, it appears that the credit system should be revised slightly to allow for the differences in education and expenence 1
of prospective Lead Auditor candidates.
4 We consider the flaw in the current system to be the emphasis on educational requirements that will l
allow a person with a Master's degree and no nuclear or power plant experience to become a Lead l
Auditor, but will exclude a person who has no degree, even though he may have 20 years' experience in operating or maintaining nuclear or power plant systems.
The practical balance between education and experience will vary with individuals and particular work assignments. Any anempt to establish rigid requirements is likely to allow some unsuitable candidates to meet the qualification requirements while excluding some acceptable candidates.
For these reasons, we think that the supervision of prospective Audit Team leaders should be given more flexibility in determining whether, for a particular individual, educational or professional qualifications are more significant and valuable than past experience.
t The present credit system, while recognizing the Associate degree, gives no credit for completion of the nuclear training programs. We think that someone who has taken Navy Nuclear Training or its equivalent in another armed service, or someone who has completed the training required to become a licensed operator in a commercial nuclear power plant, should receive the same credit as a person who has an Associate degree from an accredited institution in engineering, physical sciences, mathematics, or quality assurance.
He points now awarded for education are related to the effect that formal courses might have on the ability ofindividuals to comprehend the regulations or the technical aspects of activities being audited.
The point system makes no allowance for the fact that such knowledge comes gradually and net upon receipt of a degree. Persons who have completed part of a degree course should receive a percentage of the credits allowed for that course.
De requirements for training specified in ANSI N45.2.23, paragraph 2.3.2, would seem to ensure that prospective Lead Auditors will meet the requirements of paragraph 2.3.1.4 dealing with the rights of management. We think, therefore, that all prospective Lead Auditors should qualify for these two credits.
Similarly, the present system recognizes the effect that working in a QA Program will have on the ability of a person to comprehend regulations and technical requirements. Persons who are not assigned as full-time members of the NPAD, however, receive similar exposure if they perform activities controlled by a QA Program. We therefore allow such persons half the credits specified for quality assurance expenence.
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s QUALITY ASSURANCE POLICY Revision 49 Ite m 2 Remiirement 33 Requalification Lead Auditors who fail to maintain their proficiency for a period of two years or more shall be required to requalify.- Requalification shall include retraining in accordance with the requirements of paragraph 233, reexamination in accordance with paragraph 23.5, and participation as an Auditor in at least one nuclear quality assurance audit.
Response
BGE requalifies Lead Auditors on the basis of the satisfactory performance of one audit, as observed by a qualified Lead Auditor.
Romaan The purpose of the training specified in paragraph 233 of the Standard is to ensure that candidates understand the fundamentals of auditing and the requirements for activities to be audited. The fact that persons have not maintained their proficiency does not mean that they need complete re-training; it means only that they have not been able to review and study the applicable Codes, Standards, Procedures, instmetions, and other documents mlated to QA Programs and program auditing. BGE considers that the satisfactory performance of an audit under the observation and guidance of a qualified Lead Auditor should ensure that persons with lapsed centification will review and understand the pertinent documents.
ANSI N101.4 - 1972 Requirement Section 1.2 specifies applicability requirements for the Standard.
Response
BGE requires that only activities performed inside containment structures and related to protective coatings applied to ferritic steels, aluminum, stainless steel, zinc-coated (galvanized) steel, concrete, or masonry surfaces shall conform to applicable Sections of ANSI N101.4.
Reason Deterioration of protective coatings applied to surfaces outside containment structures would have no detrimental effects on the safe operation of the plant.
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l ANSI N45.2.13 could be interpreted to mean that all requirements of this standard are applicable to all safety-related items or services.
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o QUALITY ASSURANCE POLICY Revision 49
Response
BGE has two approaches for safety-related and designated non-safety related procurement as described in Sections,1B.4 and 18.7. Controls established for Basic Component Purchases correspond to the requirements of ANSI N45.2.13. The extent to which the individual requirements of ANSI N45.2.13 are applied to Commercial Grade Purchases depends on the nature and scope of the work to be performed and the importance to nuclear safety and the items or services purchased. This approach is consistent with the introductory discussion in Section 1.3 of ANSI N45.2.13 - 1973.
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l QUALITY ASSURANCE POLICY Revision 49 ATTACHMENT A-1 1
l BASES FOR QA POLICY REVISIONS (1)
Entry PRF-Q l
No..
No.
Bases for Revision (s) 1.
771 Procedure Uperade Action Plan (PUAP). ner L. B. Ruccell letter 1-20-89.
2.
783 10 CFR Part 21 reaniramanta 3.
797 NRC Insnection #89-16/89-17 (Letter from R. E. Denton to R. P. Heibel dated i
July 13.1989.)
I 4.
824 NRC letter from M. W. Hadges to G. C. Creel dated March 13.1990. This letter aporoved a one-time avam ntinn to b periodic review reautremente for prncaAures scheduled to be uparadaA by the Procedures Uparada Pro _ lect. This examation was discontinuad and removed by PRF-0 954.
5.
844 Procumisent Program Project upgrade. Performance Improvement Plan (PIP)
Action Plan #5.3.1 and OAU Audit Finding 87-13 01 6.
844 18.15 and 1H.16 revised to cleariv e=tahlish program anolicability and controls.
consistent terminoloav. oraanivatinnal resnonsibilities and focused noproach towards develoning and imnlamenting an integrated Management System.
7.
891 PIP Action Plan 5.3.1 Follow-On Activity.
8.
894 1B.15 and I B.16 revised to clarify reauirements which will nermit imnlementation of the Issues Management System - PIP item 4.10.0.
9.
854/907 G. C. Creel letter to the NRC dated 7/26/91 which discussed modifications to.
and accantance of changes to the OA Policy involving OA comoliance reviews of OAPs and Directives.
10.
815 G. C. Creel letter to the NRC datad 10/3/90 discussing temnorary changes mg affecting "Anoroved Procedure Intent" and the relieving of the Administratiyg Burden on Shift Supervisors.
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_e QUALITY ASSURANCE POLICY Revision 49 ATTACHMENT A-2 BASES FOR QA POLICY REVISIONS (1)
Entry PRF-Q h
A Raman for Reviainn(s) 11.
R87 Audit Findine No. 9026-01 (Imnlamantatinn of Surveillance Reauirements).
12.
954 G. C. Creel letter to the NRC Antad 7/3/91 dieenntinuinn the one-time temnorarv ekanoe to the nerindie review interval manroved in Basic (4) above.
13.
957 PIP Action Plan follow-on activity (5.3.11.
14.
953 PIP Actinn Plan 4.1==A NUREG-0737 (TMI Actinn Plan Reanirements) d Item I.C.S. "Prneada c for Faadhack of Oneratine hnariance to Plant Staff" 15, 990 OAU Surveillanca 5-92-28 "Interrae, Between Facilities Manmoement Denartmm and Nuclamr Encrav Diviainn on Proiaete at Calvert Cliffs." Recommendatid 16.
998 OA Audit Racamma=Amtinn 92-04-R03 (ISFSI onerational nha=>).
17.
93-06 NOAD Audit Findina 92-10-01. Facility StaffTrainina.
18, 93-06 Latigr from M. C. Modes of the NRC to R. E. Dentnn dataA June 21.1994.
19.
95-02 Lice==a Amendment Reauest dated March 15.1995 (Admin Controls Saetion 6.0 Unar=Aa and OA Policy Chaa-eh and Sunnlement dated May 1.1996.
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- i QUALITY ASSURANCE POLICY-Revision 49 ADDENDUM IB-1 (19)
REVIEW FUNCTIONS OF THE POSRC, PROCEDURE REVIEW COMMITTEE, QUALIFIED REVIEWERS, AND OSSRC 1.0 PLANTOPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC) 1.1 FUNCTION ne POSRC shall function to advise the Plant General Manager on all matters related to nuclear safety.
1.2 COMPOSITION The POSRC shall be composed of at least seven members, including the Chairman. Members l shall collectively have experience in the following areas:
Nuclear Operations Electrical and Controls Maintenance Chemistry Mechanical Maintenance Nuclear Engineering Radiation Safety Plant Engineering Design Engineering Members shall be appointed in writing by the Plant General Manager. Members shall have a minimum of eight years power plant experience of which a minimum of three years shall be nuclear power experience. At least one member shall have an SRO license on Calvert Cliffs Units 1 and 2.
1.3 CHAIRMAN ne Chairman and alternate Chairmen of the POSRC shall be appointed in writing by the Plant General Manager. Chairmen shall have a minimum of 10 years power plant experience of which a minimum of three years shall be nuclear power experience.
1.4.
ALTERNATES All alternate members shall be appointed in writing by the Plant Geiwid Manager. Alternate members shall have a minimum of eight years power plant experience of which a minimum of three years shall be nuclear power experience.
1.5 MEETING FREQUENCY The POSRC shall meet at least once per calendar month and as convened by the POSRC Chairman or one of the designated alternates.
1.6 QUORUM A quorum of the POSRC shall include the Chairr;.
of the designated alternate chairmen and shall consist of a majority of the members,ir.
'rernates. No more than half of the quorum shall be alternates, including an alternate chau rr.
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QUALITY ASSURANCE POLICY Revision 49 1.7 RESPONSIBILITIES The POSRC shall be responsible for the following except for those items designated for review by the Procedure Review Committee or Qualified Reviewer in accordance with Addendum sections 2 and 3, respectively:
Review of 1) all procedures required by Technical Specification 6.4 and changes thereto, a.
and 2) any other proposed procedures or changes thereto as determined by the Plant General Manager to affect nuclear safety.
Cross-disciplinary reviews of these procedures are conducted in accordance with administrative procedures in addiion to the reviews conducted by POSRC, the t
Procedure Review Committee, or Qualified Reviewer.
b.
Review of all proposed tests and experiments that affect nuclear safety.
c.
Review of all proposed changes to Appendix A Technical Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
e.
Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Off-Site Safety Review Committee, f.
Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Off-Site Safety Review Committee.
g.
Review of changes to the Process Control Program and the Offsite Dose Calculation Manual.
h.
Review of all 10 CFR 50.59 Safety Evaluations that support procedures in 1.7.a and changes or modifications in 1.7.d above.
i.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Plant General Manager, the Vice President - Nuclear Energy and to the Chairman of the Off-Site Safety Review Committee.
j.
Review of all Reportable Events. The results of this review shall be submitted to the OSSRC and the Vice President - Nuclear Energy.
k.
Review of facility operations to detect potential safety hazards.
1.
Review of any accidental, unplanned or uncontrolled radioactive release that exceeds 25% of the limits of Offsite Dose Calculation Manual (ODCM) 3.11.1.2, 3.11.2.2 or l 3.11.2.3, including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and for forwarding of these reports to the Plant General Manager and the Off Site Safety Review Committee.
- POSRC is only required to review Fire Protection procedures and changes thereto which affect nuclear safety.
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. _ _ _I QUALITY ASSURANCE POLICY Revision 49 l
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Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Off-Site Safety Review Committee.
Review of Safety Limit Violation Reports.
n.
j 1.8 AUTHORITY l
The Plant Operations and Safety Review Committee shall:
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a.
Recommend to the approval authority approval or disapproval of procedures considered l
under 1.7.a above.
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b.
Recommend to the Plant General Manager approval or disapproval of items considered
(
under 1.7.b through h above.
c.
Render determinations in writing with regard to whether or not each item considered under 1.7.a through h above constitutes an unreviewed safety question.
d.
Evaluate root causes and recommended actions to prevent recurrence for items considered under 1.7.i through I above.
j Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President - Nuclear Energy and e.
the Chairman of the Off-Site Safety Review Committee of disagreement between the j
POSRC and the responsible approval authority in the case of item 1.7.a above or i
between the POSRC and the Plant General Manager; however, the Plant General Manager shall have responsibility for resolution of such disagreements pursuant to Technical Specification 6.1.1.
l 1.9 RECORDS The POSRC shall maintain written minutes of each meeting and copies shall be provided to the Vice President - Nuclear Energy, Chairman of the Off-Site Safety Review Committee, and the l
Plant General Manager.
2.0 PROCEDUIE REVIEW COMMI'ITEE 2.1 FUNCTION
'Ihe Procedure Review Committee may function to review items listed in 1.7.a above in lieu of review by POSRC or Qualified Reviewer as directed by the Plant General Manager.
2.2 COMPOSITION The Procedure Review Committee shall be composed of a Chairman and eight individuals who shall collectively have expertise in the areas contained in 1.2 above.
Members shall be appointed in writing by the Plant General Manager. Members shall have a minimum of eight years power plant experience of which a minimum of three years shall be i
nuclear power experience. At least one member shall be a POSRC member or alternate. The charter for the Procedure Review Committee shall include a description of membership, qualifications, functions, and reports and shall be described in plant administrative procedures.
The Procedure Review Committee may be dissolved at the discretion of the Plant General 7
I Manager.
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t QUALITY ASSURANCE POLICY Revision 49 l
2.3 CHAIRMAN.
i ne Chairman and alte nate Chairmen of the Procedure Review Committee shall be appointed in l
writing by the Plant General Manager. Chairmen shall have a minimum of eight years power plant experience of which a minimum of three years shall be nuclear power experience.
2.4 ALTERNATES All alternate members shall be appointed ia writing by the Plant General Manager. Alternate members shall have a minimum of eight years power plant experience of which a minimum of three years shall be nuclear power experience.
2.5 MEETING FREQUENCY The Procedure Review Committee shall meet at least once per calendar month and as convened by the Chairman or his designated alternates.
2.6 QUORUM A quorum for the Procedure Review Committee shall consist of the Chairman or one of the designated alternate Chrirmen and three primary or alternate members provided at least four disciplines are represented.
2.7 AUTHORITY he Procedure Review Committee shall:
Recommend to the Approval Authority approval or disapproval of procedures a.
considered under 1.7 a above.
j b.
Render determinations in writing with regard to whether or not each procedure under 1.7.a above constitutes an unreviewed safety question.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President - Nuclear Energy and c.
the Chairman of the Off-Site Safety Review Committee of disagreements between the Procedure Review Committee and the responsible approval authority. The Plant General Manager shall have responsibility for resolution of such disagreements pursuant to Technical Specification 6.1.1.
2.8 RECORDS The Procedure Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Plant General Manager.
3.0 QUALIFIED REVIEWERS 3.1 FUNCTION l
De Plant General Manager may designate specific procedures or classes of procedures described l
in 1.7.a above to be reviewed by Qualified Reviewers in lieu of review by POSRC or the j
Procedure Review Committee.
a I
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QUALITY ASSURANCE POLICY Revision 49 3.2 AUTHORITY Qualified Reviewers shall:
Recommend to the approval authority approval or disapproval of designated procedures a.
and changes considered under 1.7.a above and b.
Render determination in writing with regard to whether or not each procedure under 1.7.a above constitutes an unreviewed safety question.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President - Nuclear Energy and c.
the Chairman of the Off-Site Safety Review Committee of disagreements between the Qualified Reviewer and the approval authority. The Plant General Manager shall have responsibility for resolution of such disagreements pursuant to Technical Specification 6.1.1.
3.3 CERTIFICATION Qualified Reviewers shall be nominated, trained, and certified in accordance with administrative procedures. Certification shall be by a department manager.
3.4 CERTIFICATION REQUIREMENTS Certification requirements of personnel designated as Qualified Reviewers shall be in accordance with administrative procedures.
Qualified Reviewers shall have:
A Bachelor's degree in engineering, related science, or technical discipline, and two a.
years of nuclear power plaat experience; OR b.
Six years nuclear power plant experience OR 1
Equivalent combination of education and experience as approved by a Department c.
Manager.
3.5 RECORDS Review of procedures by Qualified Reviewc.s shall be documented in axordance with administrative procedures.
4.0 OFF-SITE SAFETY REVIEW COMMITTEE (OSSRC) 4.1 FUNCTION The Off-Site Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of:
a.
nuclear power plant operations Page 71 of 74 l
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QUALITY ASSURANCE POLICY Revision 49 1
b.
nuclear engineering c.
chemistry and radiochemistry d.
metallurgy and non-destructive examination c.
instrumentation and control f.
radiological safety g.
mechanical and electrical eagineering l
h.
c iality assurance practices 4.2 COMPOSITION He Off-Site Safety Review Committee shall be composed of at least seven members, including the Chairman. Members of the Off-Site Safety Review Committee may be from the Nuclear Energy Division or other BGE organization or from organizations external to BGE and shall collectively have expertise in all of the areas of 4.1 above.
4.3 QUALIFICATIONS 1
The Chairman, members and alternate members of the Off-Site Safety Review Committee shall be appointed in writing by the Vice President - Nuclear Energy and shall have an academic degree in engineering or a physical science, or the equivalent, and in addition shall have a minimum of five years technical experience in one or more areas given in 4.1 above. No more than two alternates shall participate as voting members in Off-Site Safety Review Committee activities at any one time.
4.4 CONSULTANTS 1
Consultants shall be utilized as determined by the Off-Site Safety Review Committee Chairman to provide expert advice to the Off-Site Safety Review Committee.
4.5 MEETING FREQUENCY i
The Off Site Safety Review Committee shall meet at least once per six months.
4.6 QUORUM The quorum of the Off-Site Safety Review Committee necessary for the performance of the Off-Site Safety Review Committee review and audit functions shall consist of more than half the Off-Site Safety Review Committee membership or at least four members, whichever is greater.
This quorum shall include the Chairman or his appointed alternate and the Off-Site Safety Review Committee members, including appointed alternates, meeting the requirements of 4.3 above. No more than a minority of the quorum shall have line responsibility for operation of the plant.
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QUALITY ASSURANCE POLICY Revision 49 4.7 SUBCOMMITTEES I
The Chairman may establish subcommittees to perform reviews of selected items enumerated in 4.8 and 4.9 below. Each subcommittee shall be chanered in writing, have at least three members / alternates, and provide reports to the full committee on the results ofits reviews with any appropriate recommendations.
4.8 REVIEW 1
j The Off Site Safety Review Committee shall review:
1 The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests a.
or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.
c.
Proposed tests or experiments which involve an unreviewed =fcty question as defined in 10 CFR 50.59.
d.
Proposed changes in Technical Specifications or the Operatir.g License.
i Violation of codes, regulations, orders, Technical Specifications, license requirements, e.
or ofinternal procedures or instructions having nuclear safety significance.
f.
Significant operating abnormalities or deviations from normal and expected perfonnance of plant equipment that affect nuclear safety.
g.
All Reportable Events.
h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.
4 i.
Repons and meetings minutes of the POSRC.
4.9 AUDITS Audits of facility activities shall be performed under the cognizance of the Off-Site Safety Review Committee. These internal audits are discussed in Section IB.18 of the QA Policy.
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4.10 AUTHORITY The Off-Site Safety Review Committee shall report to and advise the Vice President - Nuclear Energy on those areas of responsibility specified in 4.8 and 4.9 above.
4.11 RECORDS Records of Off-Site Safety Review Committee activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each Off-Site Safety Review Committee meeting shall be prepared, approved ard fo: warded to the Vice President - Nuclear Energy within 14 days foHowing each j.
meeting.
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QUALITY ASSURANCE POLICY Revision 49 b.
Reports of reviews encompassed by 4.8 above, shall be prepared, approved and forwarded to the Vice President - Nuclear Energy within 14 days following completion of the review.
c.
Audit reports encompassed by 4.9 above, shall be forwarded to the Vice President -
Nuclear Energy and to the management positions responsible for the areas audited within 30 days after completion of the audit.
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