ML18092A744

Rev 4 to QA Program Description,Constituting Chapter 17 of FSAR

ML18092A744
Person / Time
Site:	Salem
Issue date:	07/22/1985
From:	Public Service Enterprise Group
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ML18092A743	List: ML18092A742 ML18092A744
References
NUDOCS 8508280280
Download: ML18092A744 (42)

Text

ATTACHMENT l 17.2 QUALITY ASSURANCE DURING THE OPERATIONS PHASE OVERALL APPROACH AND SCOPE Public Service Electric and Gas Company (PSE&G) is responsible for assuring that the operation, maintenance, refueling and modification of the Salem Generating Station is accomplished in a manner which protects public health and safety and which is in compliance with applicable regulatory requirements. To carry out this responsibility, PSE&G developed and implemented a comprehensive Operational Quality Assurance Program which was applicable to the design, construction, and testing phases, and is now applied to th~ operation phase of the Salem Generating Station.

This Operational Quality Assurance Program, hereafter also referred to as 11 the QA Program, 11 is maintained by Nuclear Operations Quality Assurance (NQA), and is documented in the Vice President Nuclear - Procedure Man~al.

The Program provides the measures essential for controlling the quality of safety related structures, systems, components, materials, and services.

The Quality Assurance Program encompasses fire protection of safety-related areas and other activities enumerated in Regulatory Guide 1.33. A planned monitoring and audit program assures that specified requirements of the Operational Quality Assurance Program are met. The Program provides coordinated and centralized quality assurance direction, control, and documentation as required by the NRC criteria set forth in 10CFR50, Appendix B. In addition, the Operational Quality Assurance Program is based upon the policy statements of PSE&G Management. It is implemented through Procedures, Instructions, Standards, Specifications, and Forms which provide the details of how that policy is implemented for 10CFR50, Appendix B. Applicable NRC Regulatory Guides, codes and standards, and the policy statements contained i~*the Nuclear Department Manual are used by PSE&G organizations performing safety-related activities to prepare appropriate implementing procedures. To assess the effectiveness of the Operational Quality Assurance Program, independent auditors from outside the company audit the program every two years for compliance with 10CFR50 Appendix B and other regulatory commitments. Reports of such audits are made directly to upper management.

( 8508280280 850819

-PDR ADOCK 05000272 p PDR SGS/UFSAR 17.2-1 Revision 4 July 22, 1985

PSE&G requires its suppliers and contractor to assume responsibility for establishing and implementing QA/QC programs, as applicable, to meet 10CFRSO, Appendix b. NQA reviews those programs and conducts appropriate monitoring and auditing as required to assure that suppliers properly implement their QA/QC programs. The Operational QA Program verifies that requirements necessary to assure quality are properly included or referenced in procurement documents. In addition, PSE&G suppliers are required to extend applicable PSE&G QA requirements to sub-suppliers, as documented in the suppliers' procurement documents.

17.2.l ORGANIZATION 17 .2.1.1 General The Operational QA Program, referred to hereafter as the QA Program, assures that adequate administrative and management controls are established for the safe operation of Salem Generating Station.

Implementation is assured by ongoing review, monitoring and audit under the direction of the Manager - Nuclear Operations Quality Assurance (NQA) who reports to the Vice President - Nuclear.

Company organization is shown in Figures 17.2-1 through 17.2-4.

Responsibilities for quality assurance related activities are described in the following sections.

17.2.1.2 Nuclear Department The Vice President - Nuclear reports to the Senior Vice President - Energy Supply and Engineering and is ~esponsible for managing and directing the 1

nuclear activities of the Comp-any. Reporting to the Vice President -

Nuclear are the General Manager - Nuclear Services, General Manager -

Nuclear Support, General Manager - Salem Operations, and General Manager -

Hope Creek Operations and Manager - NQA. Also reporting to the Senior Vice President - Energy Supply and Engineering is the General Manager - Nuclear Assurance and Regulation. The Manager - Corporate Quality Assurance reports to the General Manager - Nuclear Assurance and Regulation.

SGS/UFSAR 17.2-2 Revision 4 July 22, 1985 L

The General Managers are responsible for the implementation of quality assurance requirements by their staff. These QA requirements are contained in the station administrative procedures and in other department manuals.

17 .2.1.2.1 Nuclear Department - Nuclear Services The General Manager - Nuclear Services is responsible for providing technical support to Station organization in the areas of radiation protection, site protection, (including fire, security, and emergency preparedness) planning and scheduling of plant bettennent and maintenance work, in-service inspection, nuclear procurements and materials control, and station personnel training.

17.2.1.2.2 Nuclear Department - Nuclear Support

• The General Manager - Nuclear Support is responsible for providing support to the station in the areas of reactor engineering, engineering and design, fuel management, licensing and regulatory activity, nuclear safety, and risk assessment analysis.

17 .2.1.2.3 Nuclear Department - Salem Operations The General Manager - Salem Operations is responsible for the safe and efficient operation of the plant, and for the general direction of the station Operating, Maintenance, Radiation Protection, ~nd Technical Support Departments. The General Manager - Salem Operations directs the activities of the Station Operations Review Committee (SORC) and is responsible for assuring that plant positions are staffed by fully qualified and trained personnel.

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17.2.1.2.4 Nuclear Operations Quality Assurance The Manager NQA is responsible for the approval and coordination of nuclear-related QA programs established and implemented by Company SGS/UFSAR 17.2-3 Revision 4 July 2.2, 1985

departments. He is responsible for conducting independent audits, with his staff or consultants, or quality related activities of Company departments, suppliers~ and contractors.

The Manager NQA has the authority and responsibility to:

1. Establis_h and implement a Quality Assurance Program in conformance with the requirements of 10CFR50, Appendix B.

2. Majntain the Operational QA Program as defined and documented in the Vice President Nuclear - Procedure Manual.

3. Provide centralized coordination of Quality Assurance functions regarding Nuclear Operations.

4. Review. and approve PSE&G procedures which implement the QA Program to the extent necessary to verify compliance with applicable quality-related Regulatory Guides and standards as committed to in the Updated Final Safety Analysis Report (UFSAR).

5. Establish and interpret quality assurance requirements and policies for other departments.

6. Interpret quality assurance requirements of regulatory commitments and assist upper management in establishing policies needed to meet those commitments.

7. Assure compliance with PSE&G Quality Assurance policies and applicable government regulations including Regulatory Guides, Standards, Codes, etc., as committed in the UFSAR and licenses.

8. Provide top management with visibility into the status and adequacy of 1 implementation of the QA Program by reporting significant quality problems and their solutions, and recommending preventive or corrective action to prevent their recurrence.

SGS/UFSAR 17.2-4 Revision 4 July 22, 1985

9. Provide support to other PSE&G departments in order to assure that nuclear facilities are designed, fabricated, constructed, tested, operated, maintained, and modified in a manner which protects public health and safety.

10. Represent the PSE&G Nuclear Operations Quality Assurance at regulatory agency public hearings and other meetings, on matters affecting the Operational QA Program.

11. Stop work when significant conditions adverse to quality require such action.

The PSE&G policies and organization structure assure that the Manager -

Nuclear Operations Quality Assurance has sufficient organizational freedom and independence to carry out his responsibilities.

17.2.1.2.4.1 Nuclear Operations Quality Assurance (NQA) Personnel Qualifications Qualification requirements for NQA positions are a bachelor's degree and/or a high school diploma or equivalent, plus two years experience and demonstrated technical ability which*may be as an inspector, test engineer, or by special study of quality control techniques, testing and inspection methods, and/or by having acquired working kn owl edge of and familiarity with the requirements of the applicable Codes and Standards for accomplishing quality activities performed in the nuclear power industry.

The Manager - NQA shall fulfill the above qualifications with the addition of the following:

1. Knowledge and experience~in Quality Assurance.

2. High level of leadership with the ability to command the respect and cooperation of company personnel, vendors, and operations forces.

3. Initiative and judgement to establish related policies to attain high achievements and economy of operations.

SGS/UFSAR 17.2-5 Revision 4 July 22, 1985

The Managers and engineers reporting directly to the Manager, Nuclear \*

\

Operations Quality Assurance must each have a combination of six years experience in the fields of quality assurance and operations. At least one of these six years experience must be nuclear power plant experience in the overall implementation of a quality assurance program. A minimum of one year and a maximum of fo~r years of this six years experience may be fulfilled by related technical or academic training. Personnel performing inspections, examinations and test activities are certified as Level I, Level II or Level III as appropriate to their responsibilities, also in accordance with Regulatory Guide 1.58 as noted. -

17.2.1.2.5 Independent Review Groups Two advisory groups are responsible for reviewing and evaluating activities affecting nuclear safety. The onsite advisory group is designated the Station Operations Review Committee (SORC)". Composed of key station personnel, its responsibilities include review of p1ant operations, reportable occurrences, investigation of Technical Specification violations (with recommendation to preclude recurrence), and procedure reviews for safety-related activities or plant modifications. Recommendations of this advisory group are forwarded to the General Manager - Salem Operations, with copies to the Chairman of the Nuclear Review Board. The SQAE is invited to all SORC meetings and attends them periodically as part of the planned surveillance program. He receives minutes of all the meetings.

The off-site advisory group is the Nuclear Review Board (NRB), which advises the Vice President - Nuclear in matters affecting nuclear safety or relating to plant operation or modification to the plant design. The NRB is responsible for performing an independent review of plant activities.

I~ addition, NRB is responsib}e for selected planned, independent audits of plant operations in accordance with Technical Specification requirements.

These audits are generally conducted by NQA under NRB cognizance. The Manager, NQA is a member of the Nuclear Review Board.

SORC and NRB organization and responsibilities are delineated in the Technical Specifications.

SGS/UFSAR 17.2-6 Revision 4 July 22, 1985

. I In addition to these two groups, the onsite Safety Review Group also provides independent review of activities affecting the safe operation of the station. See Section 13.4.4.

17.2.1.3 Research & Testing Laboratory The Research and Testing Laboratory is a part of the PSE&G Research Corporation which is a subsidiary.

The Research &Testing Laboratory performs calibrations, analyses and evaluations of systems, equipment, and materials as requested by PSE&G departments, and maintains compliance with its own QA program.

17.2.1.4 Fuel Supply Department The General Manager - Fuel Supply reports to the Vice President - Fuel Supply. The Vice President - Fuel Supply reports to the Senior Vice President - Energy Supply and Engineering. The Fuel Supply Department is responsible for arranging the procurement of uranium ore, conversion and enrichment services and fuel assembly fabrication services to satisfy Nuclear Department core designs, enrichment requirements, and delivery schedules.

17.2.1.5 Transmission and Distribution Department The Vice President - Transmission and Distribution reports to the Senior Vice President - Customer Operations; This organization is responsible for transmitting electrical energy to the area of use and for distributing it to the consumers. It is responsible for setting and testing protective relays for the external vital power supplies at the Station.

17.2.1.6 Purchasing Department The General Manager - Purchasing reports to the Vice President - Cor.porate Services under the Senior Vice President - Administration.

SGS/UFSAR 17.2-7 Revision 4 July 22, 1985

Initiation of requests for procurement of materials, equipment, structures, and services required to support operations at the Station is the responsibility of the Nuclear Department. Procurement of same is the responsibility of the General Manager - Purchasing. Both *activities. are bound by Corporate purchasing policies established by the Purchasing Department.

17.2.1.7 Nuclear Assurance and Regulation Department The General Manager - Nuclear Assurance and Regulation reports to the Senior Vice President - Energy Supply & Engineering. The Nuclear Assurance

&Regulation Department provides management with independent evaluation of the effectiveness of nuclear safety and quality programs; pursues licensing, safety analysis and environmental programs as required to obtain and retain regulatory approval; coordinates company participation in meetings a~d public hearings with local, state, regional, and federal regulatory agencies; and provides a management focal *point for generic regulatory matters.

17.2.2 OPERATIONAL QUALITY ASSURANCE PROGRAM The Operational QA Program is designed to comply with the requirements of 10CFR50, Appendix B and with the Fire Protection Program requirements of Appendix A of Branch Technical Position No. 9.5-1. Items and activities covered by the QA Program are delineated in the Salem Q-list (Table 17.2-1). Procedures require that personnel also utilize the Master Equipment List (MEL) in conjunction with the Component List for determining whether an activity is safety-related and/or whether the QA Program applied to the activity. Once an activity has thus been determined to be safety-related or applicable to the 0perational QA Program, establi.shed approved procedures are utilized in the performance of the activity.

The QA Program is applied during the operational phase using a graded approach to an extent consistent with the item's or activity's importance to safety. These activities are performed in compliance with license requirements and with applicable regulatory guidance. Such regulatory guidance, with exceptions ndted, includes:

SGS/UFSAR 17.2-8 Revision 4 July 22, 1985

1. Regulatory Guide 1.8, "Personnel Selection and Training", 9/75, (endorses Nl8.l).

2. Regulatory Guide 1.17, "Protection of Nuclear Plants Against Industrial Sabotage", 6/73, '(endorses Nl8.17).

3. Regulatory Guide 1.29, "Seismic Design Classification", 8/73.

4. Regulatory Guide 1.30, "Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation Electric Equipment", 8/72, (endorses N45.2.4).

5. Regulatory Guide 1.33, "Quality Assurance Program Requirements (Operation)", 2/78, (endorses Nl8.7-1976/ANS-3.2).

6. Regulatory Guide 1.37, "Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants", 3/73, (endorses N45.2.l).

7. Regulatory Guide 1.38, "Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants", 10/76, (endorses N45.2.2).

8. Regulatory Guide 1.39,. "Housekeeping Requirements for Water-Cooled Nuclear Power Plants", 3/73, (endorses N45.2.3).

9. Regulatory Guide 1.52, "Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Absorption Units of Light Water-Cooled Nuclear Power Plants", B/73.

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10. Regulatory Guide 1.54, 1"QA Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants", 6/73, (endorses NlOl.4).

11. Regulatory Guide 1.58, "Qualification of Nuclear Power Plant Inspection, Exami.nation, and Testing Personnel", 9/80, (endorses.

N45.2.6).

SGS/UFSAR 17.2-9 Revision 4 July* 22, 1985

.e ,*

. All PSE&G personnel performing inspection, examination, or.testing, are qualified in accordance with this Regulatory Guide, with the following exception:

Paragraph 6 of Regulatory Guide 1.58 requires that for 11

• • • 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. 11 Other factors may provide reasonable assurance that a person can competently perform a particular task. The other factor~ which may demonstrate capability in a given job are previous performance or satisfactory completion of testing. These two factors will be considered when evaluating education and experience requirements for certification. Personnel requiring certification in accordance with Regulatory Guide 1.58 are l~mited to NQA personnel who perform inspection and test activities, members of the Operational Test Group (OTG) who perform post-design modification testing, and Salem Operations Department personnel who perform visual inspection as part of the Inservice Inspection Program.

Personnel requiring certification are evaluated to establish their qualification for the respective level and discipline.

Recertification is based upon demonstrated continued proficiency, or requalification if necessary. These personnel receive a periodic training needs assessment .to identify additional supportive training needs as well as to evaluate individual post-training performance. The assessment period is three years or less. Inspection and test activities not requiring personnel certification per Regulatory Guide 1.58 include Technical Specification surve"Vllances and periodic inspection and test of fire protection equipment. These personnel are qualified and retrained i~ accordance with applicable requirements of Regulatory Gui de 1.8.

12. Regulatory Guide 1.64, Quality Assurance Requirements for the Design 11 of Nuclear Power Plants", 10/73, (endorses N45.2.11).

SGS/UFSAR 17 .2-10 Revision 4 July 22, 1985

13. Regulatory Guide 1.74, 11 Quality Assurance Terms and Definitions 11 ,

2/74, (endorses N45.2.10).

14. Regulatory Guide 1.88, 11 Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records 11 , 10/76, (endorses ANSI N45.2.9), as modified by provisions stated in ~ection 17.4 of NUREG-0800 (Standard R~view Plan), Revision 2, July 1981.

15. Regulatory Guide 1.94, 11 Quality Assurance Requirements for Instal-lation, Inspection, and Testing of Structural Concrete and Structural Steel during the Construction Phase of Nuclear Power Plants 11 , 4/76 (endorses N45.2.5). Major modifications made to the Salem Station will comply with Regulatory Gutde 1.94.

16. Regulatory Guide 1.137, 11 Fuel-Oil Systems for Standby Diesel Generators 11

, 10/79. Diesel fuel oil sampling is performed as follows:

1. A fuel oil sample is taken from each truck delivering fuel oil to Salem whenever possible. Howeve~, if several trucks arrive at once, a minimum of 1 in 4 trucks is sa~pled depending on the shift, staffing, and existing personnel work load at the time.

2. All newly received fuel oil is pumped into the 20,000 barrel Fuel Oil Storage Tank. Fuel oil in this tank is sampled at least once every 30 days.

3. A small percentage of the fuel oil in the 20,000 barrel tank is introduced into the diesel fuel oil storage system as necessary.

This sm~ll percentage is added infrequently to the four 30,000 gallon Diesel Fuel.Oil Storage Tanks (two for each unit) ~s

?

necessary io maintain the minimum level above the 20,000 gallon limit in each Diesel Fuel Oil Storage Tank as specified by the Salem Technical Specifications.

4. Fuel oil in the four 30,000 gallon Diesel Fuel Oil Storage Tanks is sampled as required by the Salem Technical Specifications.

SGS/UFSAR 17 .2-11 Revision 4 July 22, 1985

5. All fuel oil samples taken in actions 1-4 above are sent to an independent laboratory within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the time the sample is taken. The analysis performed is consistent with Regulatory Guide 1.137 and the analysis report is submitted to the Salem Station within 30 days of receipt of the sample at the laboratory.

6. All fuel oil deliveries, samples taken, and related analysis reports are logged at the station~ When reports indicate that fuel oil quality is not within acceptable limits, station management will take appropriate action to restore it to within acceptable limits.

7. Actions 1-6 above are subject to verification during routine monitoring and audits of the fuel oil program and procedures conducted by NQA personnel.

17. Regulatory Guide 1.144, 11 Auditing Quality Assurance Programs for Nuclear Power Plants", 9/80, (endorses N45.2.12).

18. Regulatory Guide 1.146, "Qualification of Quality Assurance Program.

Audit Personnel for Nuclear Power Plants", 8/80, (endorses N45.2.23).

19. Branch Technical Position APCSB 9.5-1, Appendix A, "Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1, 1976 11 ' 2/77.

The QA Program is applied to the Fire Protection Program to an extent consistent w_ith the requirements of Section C of Appendix A to Branch Technical Position APCSB1 9.5-1.

PSE&G organizations performing activities affecting nuclear safety, prepare and maintain implementing procedures and instructions. These procedures and instructions, and subsequent revisions thereto, are subject to NQA review and approval to an extent necessary to verify compliance with the Opera ti anal QA Program and the app 1icab1 e qua 1ity-re1 ated Regul ato.ry Gui des and standards identified above.

SGS/UFSAR 17.2-12 Revision 4 July 22, 1985

The General Manager - Salem Operations has instituted and will maintain an Administrative Procedures Manual for Salem Generating Station to implement the detailed requirements of the Program relative to the station.

The Station Administrative Procedures and all subsequent revisions thereto are prepared by the Technical Manager, are reviewed by the Assistant General Manager, and are approved by the General Manager - Salem Operations and the Manager - Nuclear Operational Quality Assurance.

Regulatory Guide 1.33 requires that safety-related plant activities be conducted in accordance with written administrative controls prepared by management. The departmental procedures and *instructions by which plant activities are performed are prepared by the responsible station department, as required by the Station Administrative Procedures, reviewed by the SQAE for inspection requirements, approved by the department head responsible for the activity, reviewed by the SORC (if safety related), and approved by the General Manager - Salem Operations. Procedures cannot be implemented unless the review/approval process is accomplished. Station Administrative Procedures provide a means to accommodate on-the-spot changes to sub-tier implementing procedures. The routine practice for revising a procedure is to repeat the original review and approval sequence.

Implementation of the Operational QA Program is verified by means of independent inspections, monitoring, and audits conducted by NQA.

NQA reviews and analyzes quality-related problems occurring during the operational phase. Items subject to review include:

1. Documented nonc9nfprmances

- i occurring at the vendor's facility and during receiving, storage, installation, test and operation (e.g., Deficiency Reports, Non-Conformance Reports, Licensee Event Reports, etc.).

2. Documented corrective actions taken on significant noncompliances and on audit findings.

SGS/UFSAR 17.2-13 Revision 4 July 22, 1985

3. NRC inspection findings, notices, bulletins, etc.

The Manager - Nuclear Operations Quality Assurance or his designee, has the authority to stop work where continuance of an activity would seriously compromise safety or constitute a persistent and deliberate failure to correct a serious deficiency.

NQA reports significant problems affecting the Program to respective management along with:

1. Measures taken to improve QA program controls.

2. Appropriate recommendations to achieve compliance with applicable requirements.

Management policy and implementing procedures provide all personnel awareness and direction for reporting of defects and non-compliances pursuant to 10CFR21.

The Operational QA Program requires that activities affecting nuclear safety, including activities affecting the fire protection of safety-related areas, be accomplished under suitably controlled conditions. The program takes into consideration the need for procedures, special controls, cleanliness, special processes, test equipment, tools, and skills to obtain the required quality and the verification of quality by inspection, test, examination, monitoring an~ independent review and audit. These activities include, but are not limited to, designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, operating, maintaining, repairing, refueling, and modifying.

Personnel who have the responsibility to implement the Operational Quality Assurance Program also have the responsibility and authority to escalate unresolved quality problems to the level of management necessary to effect resolution. This escalation is applied by NQA personnel, who are independent of cost and scheduling, to increasingly higher levels of management up the the Vice President - Nuclear as required.

SGS/UFSAR 17.2-14 Revision 4 July 22, 1985

Personnel performing safety-related activities are trained and/or indoctrinated as necessary to assure that suitable proficiency is achieved and maintained. The Manager - Nuclear Operations Quality Assurance is responsible for the training of NQA personnel. Orientation is provided for new employees entering the NQA Department, whether from other parts of PSE&G or from outside the Company. An outline of the course content is contained in the NQA Orientation, Training, and Qualification Manual. The training and indoctrination program is designed to familiarize the employee with:

1. Codes, regulations, specifications, etc., applicable to nuclear and other power generation equipment.

2. QA procedures, instructions, specifications, documentation, records, etc ..

3. Auditing objectives and techniques.

4. Nuclear Operations QA Program.

5. The QA program and the organization of major contractors.

6. Other organizations within PSE&G with which NQA interfaces.

7. .The general theory, structure, function and mode of operation of nuclear generating stations.

NQA also offers formal training sessions for personnel in the Nuclear Department and other departments such as Construction, Engineering, Fuel Supply, Research & Testing Laboratory, etc., who perform activities related I

to nuclear operations safety.

NQA personnel requiring certification are evaluated to establish their qualifications for the respective level. The qualifications are approved by NQA management for the required certification level.

SGS/UFSAR 17.2-15 Revision 4 July 22, 1985

The Nuclear Training Center is responsible for the licensed operator training and retraining in addition to other technical and supervisory training programs including general Employee Indoctrination which is required for all personnel having access to the station.

17.2.3 DESIGN CONTROL The Nuclear Support Department procedures, approved by the Manager - NQA, provide implementation direction for the intent of Regulatory Guide 1.64 nquality Assurance Requirements for the Design of Nuclear Power Plants."

Withi~ that department, the Nuclear Engineering Department has the following respcrnsibilities:

1. Prepare and update detailed engineering and design documents, including drawings and specifications, for all systems, components and structures.

2. Specify applicable codes, standards, regulatory and quality requirements, acceptance standards and other design input in design output documents.

3. Identify systems, components, and structures which are covered by the QA Program.

4. Perform design verification for systems, components, and

- structures.

5. Perform safety evaluations of proposed design changes.

6. Prepare documentsifor procurement of equipment, materials and components.

7. Recommend engineering consultants and laboratories for procurement services and coordinate their activities.

8. Review design documents submitted by suppliers (including the NSSS supplier) and contractors.

SGS/UFSAR 17 .2-16 Revision 4 July 22, 1985

9. Specify, or approve as required, inspections and/or tests.

10. Designate whether they will use the services of other qualified engineering organizations both inside and outside PSE&G.

The cognizant engineer is responsible for the identification and completion of design analyses. The purpose of design analyses is to assure that the technical design is accomplished in a planned, controlled and correct manner. Types of design analyses include, but are not limited to, reactor physics, stress, seismic, thermal, hydraulic and accident.

Design verification is performed on design analyses, drawings, specifications and other design documents, as applicable. Design verification is the process of reviewing, confirming or substantiating the adequacy of a design by one or more methods. Design verification is performed on changes to previously verified designs including evaluation of the effects of those changes on the overall design. Design verification is performed by competent individuals or groups other than those who performed the original design with the following exception: A design verifier may be the design originator's supervisor provided that he did not specify a singular design approach or rule out certain design considerations and did not establish the design inputs used in the design, or if the supervisor is the only individual competent to perform the verification. This design verification provision requires prior authorization on an individual basis.

Control of this function will be assured through periDdic QA audits.

Design verification methods include but are not limited to:

1. Design reviews.

I

2. Alternate or independent calculations.

3. Qualification testing.

Changes to specifications prepared by the Engineering Department for items covered by the QA Program are reviewed and approved by NQA to assure that SGS/UFSAR 17.2-17 Revision 4 July 22, 1985

-~ -

the QA Program requirements are specified. Specifications are forwarded to NQA for review and approval of quality and quality assurance requirements.

NQA performs the same function in this case as during the original design stage.

The SORC reviews proposed changes affecting nuclear safety and makes recom-mendations concerning implementation of the change to the General Manager -

Salem Operations. If the proposed modification involves *a Technical Specification change or is consid~red by the SORC to involve an unreviewed safety question (10CFR50.59), the matter is submitted to the NRB for a determination of its safety implication before ~ license change. request is submitted for NRC approval.

External interfaces with manufacturers, consultants, and other departments, including procedures for the preparation, transmittal, review and approval of design information, are identified in documents such as contracts, specifications, purchase orders, design data sheets, and drawings.

Updating of records, including drawings, blueprints, instructions and technical manuals, and specifications resulting from design changes, is the responsibility of the Nuclear Support Department.

17.2.4 PROCUREMENT DOCUMENT CONTROL All initial procurement documents for the purchase of Q-listed material, equipment or services, are reviewed and approved by NQA prior to issuance by the Purchasing Department to the prospective supplier. Procurement documents for subsequent reorders of Q-listed material, equipment or services are selectively reviewed and approved by NQA prior to issuance by the Purchasing Department to the prospective supplier. NQA review assures that spare and replacement parts are procured utilizing controls which are at least equivalent to the original procurement.

The review also assures that procurement documents adequately and correctly:

SGS/UFSAR 17.2-18 Revision 4 July 22, 1985

1. Identify applicable QA Program requirements.

2. Reference applicable regulatory requirements, codes, and standards.

3. Provide right of access for source surveillance and audit by NQA or its agents.

4. Provide for required supplier documentation to be submitted to PSE&G or maintained by the supplier, as appropriate.

5. Provides for PSE&G review and approval of critical procedures prior to fabrication, as appropriate.

6. Account for special testing and/or qualification testing requirements.

Procurement documents require suppliers and contractors of other than commercial grade items to provide services or components in accordance with a QA program which complies with applicable criteria of 10CFR50 Appendix B.

17.2.5 INSTRUCTIONS, PROCEDURES AND DRAWINGS Organizations engaged in Q-listed activities are required to perform these activities in accordance with written and approved procedures, instructions or drawings, as appropriate.

Simple routine activities, that can be performed by qualified personnel with normal skills, do not require a detailed written procedure. Complex activities shall require det~iled

,,. instructions.

Procedures include, as appropriate, scope, statement of applicability,

• references, prerequisites, precautions, limitations, and checkoff lists of inspection requirements in addition to the detailed steps required to accomplish the activity; Instructions, procedures, and drawings also contain acceptance criteria where appropriate.

SGS/UFSAR 17.2-19 Revision 4 July 22, 1985

• The General Manager - Salem Operations is responsible for *assuring that station procedures are prepared, approved, and implemented in compliance with the Station Administrative Procedures. Documents affecting nuclear safety are reviewed by the SORC for technical content, and by the SQAE for inspection requirements including designation of QA hold points where required and are approved by the responsible station department head and the General Manager - Salem Operations.

The General Manager - Nuclear Support is responsible for issuing specifications, drawings, blueprints, instruction manuals and technical manuals associated with structures, systems, and components covered by the QA Program. These reference documents are kept up to date for the life of the station by the incorporation of approved and implemented modifications and design changes. Master lists of current editions or revisions of these documents are issued by the General Manager - Nuclear Support to the General manager - Salem Operations periodically to assure that only current, approved reference documents are used at the station.

The SQAE reviews and approves selected station inspection plans and procedures for test, calibration, maintenance, modification and repair.

Changes to these documents are also reviewed and approved. In addition NQA is responsible ~or review and approval of the following.documents: PSE&G specifications, test procedures, and results of preoperational testing.

17.2.6 DOCUMENT CONTROL Instructions, procedures, and drawings and changes thereto are approved by appropriate levels of management of the PSE&G organizations producing such documents *. Supplier documents are controlled according to contractual agreements with suppliers.

I The following is a generic listing of documents for the operational phase showing organizational responsibility for review and approval, including changes thereto:

SGS/UFSAR 17.2-20 Revision 4 July 22, 1985

Design Specifications: Nuclear D*epartment/Engineering Department, NQA Design, Manufacturing, Construction and Installation Drawings: Nuclear Department/Engineering Department Procurement Documents: Nuclear Department/Engineering Department, Purchasing_ Department, NQA VPN Manual: Vice President Nuclear, NQA Station Administrative Procedures: General Manager - Salem Operations, NQA Maintenance, Modification, Calibration Procedures for Q-listed Station Work Activities: General Manager - Salem Operations, NQA (involving QA inspection requirements)

Operating Procedures: General Manager - Salem Operations, Station Operations Review Committee (SORC)

FSAR: Nuclear Department, NQA Manuf actur1ng, Inspection and Testing Instructions: Nuclear Department/

Engineering Department, NQA Test Procedures: Nuclear Department, NQA Design Change Requests: Nuclear Department/Engineering Department, NQA The establishment and maintenance of a document control system for all instructions, procedures, specifications, and drawings received from the p

Nuclear Department/Engineertng Department, or prepared at the station for use in operating, maintaining, refueling, or modifying the nuclear safety-related structures, components and systems is the responsibility of the General Manager - Salem Operations. The Station Administrative Procedures Manual describes the control of specific documents. Control of station practices is included in Administrative Procedures and in department instructions authorized by the responsible station department heads.

SGS/UFSAR 17.2-21 Revision 4 July 22, 1985

Measures have been established to insure that the Administrative Procedures and department instructions are up to date, are properly authorized, are changed only after required review and the approvals are obtained, and are distributed to cognizant personnel.

17.2.7 CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES NQA maintains an up-to-date listing of approved suppliers of material, equipment, and services covered by the QA Program. This list identifies suppliers and contractors which have demonstrated the ability to supply acceptable material, equipment, or services. The list need not include original manufacturers of commercial catalog items. All QA Program procurements ~re made from approved suppliers.

Selection and evaluation of prospective bidders and suppliers are performed by the responsible engineer and the NQA. The responsible engineer determines the technical competence of the supplier. The NQA evaluates the prospective supplier's quality assurance program for compliance with the capability of meeting applicable requirements of 10CFR50 Appendix B and for the requirement that applicable program requirements be extended to subtier suppliers.

Qualified NQA personnel evaluate the prospective supplier's quality assurance capability utilizing one or more techniques including, but not necessarily limited to:

1. Evaluation of supplier's or contractor's procedures or manuals and changes thereto.

2. ASME code stamp a~proval.

3. CASE register listing.

4. Satisfactory past history of providing similar items.

5. Survey of supplier's facility.

SGS/UFSAR 17.2-22 Revision 4 July 22, 1985

The evaluation of prospective suppliers is conducted utilizing standard checklist/forms designed to include the 18 quality criteria of 10CFRSO Appendix B as appropriate. Surveys of supplier's capabilities shall include evaluation of management systems, and manufacturing process, as well as adherence to QA/QC procedures. The results of supplier evaluations are documented by the appropriate checklist/form and filed.

Supplier control is maintained through a planned inspection, monitoring and a.udit program by NQA.

A review of the. manufacturing process for complex manufactured items such as pumps, valves, heat exchangers, .vessels, electrical panels, etc. is conducted by NQA and the responsible *sponsor engineer. This review establishes critical inspection points and establishes a Notification Point Program for the identified inspection or surveillance activities. The established inspection or surveillance activities are implemented by qualified NQA personnel or NQA agents. Standard catalog items, where quality can be verified by receiving inspection or installation checkout, are not normally included in the Notification Point Program.

Monitoring of suppliers/contractors during fabrication, installation, modification, repair, inspection, testing and shipment of materials, equipment and services, is conducted by qualified NQA personnel or NQA agents at the supplier 1 s/contractor 1 s facility or at the generating station. Surveillances are conducted in accordance with written procedures and are designed to *assure conformance with procurement requirements in accordance with the safety significance of the item or service. Consistent with the importance or complexity of the item or service, periodic evaluations of the supplier/contractor quality program are conducted.

Dependent upon the evaluatiog,;

additional audits or corrections may be required of the supplier/contractor.

Procurement of replacement parts is by adherence to the original design criteria, where feasible (such as NSSS components in accordance with Westinghouse documentation, other code components in accordance with AQQA, AISC, SPCC and ASME Section III 1971 and Summer 1972 Addenda or later).

This will provide the intended level of safety, and will not result in SGS/UFSAR 17.2-23 Revision 4 July 22, 1985

redesign of the system. Quality assurance requirements are consistent with the FSAR commitments.

The requirement for appropriate supplier documentation of conformance to applicable code, standard, specification or other quality requirement is provided by ~he procurement document. The supplier-provided documentation is reviewed either at the supplier's facility during an inspection or surveillance visit, or at receiving inspection. A data review check off is provided and utilized documenting the acceptability of the supplier provided data or identifying discrepancies.

Receiving inspection of supplier equipment, material and services is conducted by qualified personnel to verifJ correct identification, and appro~riate documentation, and to verify that the item is acceptable and can be released for storage, installation, or use.

Nonconforming items identified at receiving inspection are tagged or segregated to prevent inadvertent use. Nonconforming items are controlled as described in Section 17.2.15.

17.2.8 IDENTIFICATION AND CONTROL OF MATERIAL, PARTS, AND COMPONENTS Procurement document controls provide assurance that materials, parts, and components received can be properly identified. The identification is marked directly on the item, or on records traceable to it. The data review conducted at receiving assures that proper documentation of received items is available. Materials and items received without proper identification are tagged or segregated until satisfactory documentation and identification is obtained.

Procedures require that Q-listed materials, parts, and components be marked or otherwise identified and require that such identity be maintained ~ither on the item or on records traceable to it throughout receipt, storage, installation, and use. Protection against use of incorrect or defective items* is also provided.

SGS/UFSAR 17.2-24 Revision 4 July 22, 1985

Material identification and traceability shall be maintained for repairs, replacement, and modifications* throughout operation.

17 .2.9 CONTROL OF SPECIAL PROCESSES Procedures for special processes such as welding, heat treating, and NOE, assure compliance with codes and design specifications. The General Manger - Nuclear Support is responsible for preparing special process specifications. These specifications are reviewed and approved by NQA for necessary quality content.

Procedures for implementing the requirements of the specifications -are prepared either by the Nuclear Department or by supplier personnel, and are approved by the General Manager - Nuclear Support (with the exception*of 11 11 special process procedures prepared by code suppliers holding an N stamp). Procedures prepared by suppliers are also reviewed and approved by NQA.

17 .2.10 INSPECTION A planned inspection program is conducted by personnel appropriately qualified in accordance with Section 17.2.2. The inspection program verifies conformance to the established procedure, code or standard, consistent with the activity's importance to safety.

When required, Inspection.Hold Points, to be accomplished by the applicable NQA representative, are identified and included in the procedure or instruction.

Station Department Heads are,responsible

, for inserting inspection hold points for critical activities in procedures they approve. These hold points are witnessed by members of the SQAE staff. The Station Operations Review Committee (SORC) may recommend to the General Manager - Salem Operations, additional or different hold points, as a result of their review. Selected procedures are reviewed by NQA prior to issuance and additional inspection hold points may be added to a procedure. The SGS/UFSAR 17.2-25 Revision 4 July 22, 1985

hold points must not be passed without authorization from the applicable NQA representative. Typical critical activities include:

1. Visual and NOE of ASME pressure boundary welds.

2. Verification of cleanliness prior to closing safety-related systems.

3. -Verification of reactor trip and Engineered Safety Features initiation setting after adjustment.

4. Packaging and loading of radioactive material for shipment.

5. . Hydrostatic testing of safety-related systems.

6. Acceptance testing of safet~-related system modifications.

7. Acceptance testing of major repairs on safety-related systems.

Inspection of operating activities (work functions associated with the normal operation of the plant, routine maintenance, and certain technical services) shall be conducted by qualified individuals.other than those who performed or directly supervised the activity being inspected. These activities typically include periodic inspections of:

1. Storage areas.

2. Housekeeping (General).

3. Fire protection e~uipment.

4. Special handling tools and equipment.

5. NOE visual inspection required by the Inservice Inspection Program.

SGS/UFSAR 17.2-26 Revisfon 4 July 22, 1985

The applicable inspection and retest requirements necessary to assure that modifications or repairs have been accomplished correctly are provided by the design change package, work order, or procedure. The inspection and retest requirements for modification and repair are based on the original inspection and test program, and the nature and scope of the modification or repair activity.

A planned and documented monitoring program is conducted for Q-listed activities. Monitoring of implementation of the QA Program by station personnel is conducted by the SQAE. NQA perfonns monitoring of supplier and contractor activities. Discrepancies discovered during the conduct of the monitoring are brought to the attention of the management responsible for accomplishment of the acti.vity.

17.2.11 TEST CONTROL Q-listed equipment or components (a) which require seismic or environmental qualification, (b) which*must be tested periodically to assure satisfactory performance, or (c) which have been replaced, modified or repaired, are tested by qualified personnel in accordance with written procedures which provide acceptance criteria.

Retest require~ents following repair or modification are provided by engineering specifications and/or .the responsible engin,eer, as were the original test requirements. The Operational Test Group is responsible for preparation of test procedures incorporating the engineering parameters.

Test procedures prescribe:

1. Prerequisites,

2. Instrumentation and equipment for conduct of the test adequate to the test objective,

3. Suitable envi~onmental conditions and adequate test methods, and

4. Acceptance criteria.

SGS/UFSAR 17.2-27 Revision 4 July 22, 1985

Test results are documented and reviewed for acceptability by the ~ualified department representative. System tests performed following modifications to safety-related systems require review of test procedures and test results by the SORC.

The SQAE maintains monitoring over the conduct of the design change acceptance tests to assure compliance with the test procedure. Test results are reviewed for the following:

1. Presentation of proper documentation.

2. Assurance that tests meet objectives.

3. Identification and reporting of unacceptable results and initiation of corrective measures.

Retention of test reports are described in Administrative Procedure~.

17.2.12 CONTROL OF MEASURING AND TEST EQUIPMENT Test equipment, instrumentation, and controls used to monitor and measure activities affecting quality and personnel safety are identified, controlled, and calibrated at specific intervals. Written procedures for meeting these requirements include provisions for:

1. Specifying calibration frequency,

2. Recording and maintaining calibration records,

3. Controlling and e~librating primary and secondary standards,

4. Determining methods of calibration, and

5. Tracing use on safety-related components.

SGS/UFSAR 17.2-28 Revision 4 July 22, 1985

e e Prior use of* measuring and test equipment found to be out of calibration is evaluated for possible effect on safety-related equipment or functions.

Measurements are repeated where necessary.

Secondary standards are calibrated by certified calibration laboratories and are traceable to the National Bureau of Standards (NBS) or best industry standards where no NBS standards exist. The accuracy of the primary standards used to perform this calibration is at least greater than the accuracy of the device being calibrated to the extent permitted by the state-of-the-art.

Test equipment is marked to indicate the latest calibration date and the next required calibration date.

Out-of-calibration identification is used for instruments and controls to indicate this status pendin~ calibration, repair, or replacement.

17.2.13 HANDLING, STORAGE AND SHIPPING The control of handling, storage, cleaning, and preservation of material and equipment covered by the QA Program is the responsibility of the various departments involved in these activities. The Nuclear Material Control Group is responsible for control of material in storage, including preservation and the application of appropriate shipping controls on items or materials shipped from the station. The station departments are responsible for system cleanliness and handling of equipment during operational maintenance or modification. Nuclear Engineering is responsible for specifyin~ equipment requirements (performance characteristics, operational characteristics, special storage and handling characteristics). Manufacturer's I

instructions and recommendations, design.

requirements, and applicable codes and standard,s are implemented, as appropriate. Compliance with specific handling, storage or shipping requirements, as established by the cognizant Nuclear Department/

Engineering Department engineer is required. Requirements for new components and spares, where applicable1 are included in the procurement documents.

SGS/UFSAR 17.2-29 Revision 4 July 22, 1985

17.2.14 INSPECTION, TEST AND OPERATING STATUS Procedures are required to specify the periodic tests and inspections required for equipment covered by the QA Program, and to include the necessary management controls to assure that such required tests and/or inspections are completed in accordance with specified requirements.

Equipment awaiting repairs, under repair, or repaired, and received materials are marked to indicate the status of inspection and test requirements and/or acceptability for use. Procedures provide for tagging valves and switches to prevent inadvertent operation. These procedures are designed to prevent operation of valves and/or switches which could result in person.nel hazard or equipment damage.

Valve and equipment status boards or logs are maintained to indicate status.

17.2.15 NONCONFORMING MATERIALS, PARTS OR COMPONENTS Nonconforming materials, parts or components identified during receiving inspection or during performance testing of equipment are identified and, where practical, segregated to prevent installation or use until proper approvals are obtained. Materials, parts, or components which have failed in service are identified, and where practical segregated. Documentation of the nonconformance includes a description of the nonconformance, and the disposition and inspection or retest requirements, as appropriate. All dispositions for repair or use-as-is are required to be approved by the responsible engineering representative. Rework or repair of nonconforming material, parts, or components are inspected and/or retested in accordance with specified test and insp~ction requirements . established by the

~

cognizant engineer ba.sed on-applicable code requirements. NQA reviews the disposition of all reports of nonconforming conditions and verifies completion of the disposition.

NQA and other organizations in the Nuclear Department review nonconformance reports for quality problems and initiate reports to higher management, SGS/UFSAR 17.2-30 Revision 4 July 22, 1985

identifying significant quality problems with recommendations for appropriate action.

17.2.16 CORRECTIVE ACTION -

Organizations involved in activities covered by the QA Program are required to maintain corrective action programs commensurate with their scope of activity. Noncompliances with the QA Program identified by NQA are documented and controlled by the issuance of an Action Request. NQA reviews Action Requests for quality trends and periodically reports the status and review results to management.

Responses to Action Requests are based on the four elements of GOrrective action which are:

• 1. Identification of cause of deficiency.

2. Action taken to correct deficiency and results achieved to date.

3. Action taken or to be taken to prevent recurrence.

4. Date when full compli~nce was or will be achieved.

Proper implementation of corrective action is verified through monitoring or audit as appropriate.

The General Manager - Salem Operations is responsible for assuring that conditions adverse to quality are promptly identified and corrected for all activities involving station operation, maintenance, testing, refueling and modification.

Administrative procedures which govern station activities covered by the QA Program, provide for the timely discovery and correction of non-conformances. This includes receipt of defective material, failure or malfunction of equ~pment, deficiencies or deviations of equipment from design performance, and deviations from procedures. In cases of SGS/UFSAR 17.2-31 Revision 4 July 22, 1985

significant conditions adverse to quality, the cause of the condition is determined and measures established to preclude recurrence. Such events, together with corrective action taken, are documented and reported as described in Section 17.2.15. Corrective action is initiated by the responsible department head.

NQA maintains close monitoring over station conditions requiring corrective action~ The SQAE has the authority to stop work when significant conditions adverse to quality require such action.

Repetitive deficiencies, procedure or process violations at the Station which are not classified as Operational Incidents or Reportable Occurrences or nonconf ormances under the QA Program are documented by the SQAE by the issuance of an Action Request. This request will provide the SQAE with a formal administrative vehicle to alert management of conditions adverse to quality that require corrective action.

17.2.17 QUALITY ASSURANCE RECORDS Records necessary to demonstrate that activities important to quality have been performed in accordance with applicable requirements, originated by the station or other departments, are identified and maintained in accordance with Regulatory Guide 1.88 as noted in 17.2.2.

Design and construction records are replicated via microfilm and stored in record facilities at the generating station and at off-site locations.

The General Manager - Salem Operations is responsible for the permanent storage of station records. The retention period for records, the permanent storage location,~and methods of control, identification, and retrieval are specified by administrative procedure. Individua*l station department heads are responsible for submitting applicable department records to the Technical Document Room for retention.

SGS/UFSAR 17.2-32 Revision 4 July 22, 1985

17.2.18 AUDITS Audits of PSE&G and supplier organizations which implement the QA Program are performed by the NQA to verify compliance with the applicable portions.

of the Quality Assurance Program.*

-Audits are conducted by audit teams comprised of a certified lead auditor, and certified auditors.

Audits are conducted using pre-established written procedures and checklists. Areas of deficiency revealed by audits are reviewed with management and are required to be corrected in a timely manner. Required corrective action shall be documented and verified. Follow-up action, including reaudit of deficient areas, is performed~

The audit program conducted by NQA includes, but is not limited to, the following activities covered by the QA Program.

1. Operation, maintenan*ce, and modification.

2. Preparation, review, approval, and control of design, specif i ca ti ans, procurement documents, instruct i ans., procedures.,

and drawings.

3. Inspection programs.

4. Indoctrination and training.

5. Implementation of operating and test procedures.

6. Calibration of measuring an.d test equipment.

7. Fire protection.

8. Other applicable activities delineated in Table 17.2-1.

SGS/UFSAR 17.2-33 Revision 4 July 22, 1985

A written report of the results of each audit is distributed to appropriate management representatives of the organization(s) audited as well as other affected management personnel. NQA is audited by independent auditors every two years to verify implementation of the corporate QA Program.

Reports of these audits are directed to appropriate PSE&G management personnel.

SGS/UFSAR 17.2-34 Revision 4 July 22, 1985

TABLE 17.2-1 (Sheet 1 of 5)

SALEM Q-LI ST The listing below identifies those activities, services, structures, components and systems to which the operational Quality Assurance Program applies.

I. Activities/Services A. Safety Related Activities Delineated in Regulatory Guide 1.33, App. A (See R.G. for further breakdown of activities)

A.1 Administrative Procedu.res a) Security Program (Regulatory Guide 1.17) b) Equipment Control (e.g., Locking and Tagging) c) Shift and Relief Turnover d) Bypass of Safety Functions and Jumper Control e) Maintenance of Minimum Shift Complement and Call-In of Personnel f) Fire Protection Program including Inspection by Fire Consultants g) Communication System A.2 General Plant Operating Procedures A.3 Startup, Operation, and Shutdown of Safety-Related Systems A.4 Abnormal, Offnormal, or Alarm Conditions A.5 Combating Emergencies and Other Significant Events A.6 Control of Radioactivity a) Liquid Radioactive Waste System b) Solid Waste System c) PWR Gaseous fffluent System d) Radiation Protection including Occupational Radiation Exposure per R.G. 8.8 e) Area Radiation Monitoring System Operation f) Process Radiation Monitoring System Operation g) Meteorological Monitoring and Data Collection Program SGS/UFSAR Revision 4 July 22, 1985

TABLE 17.2-1 (Sheet 2 of 5) h) Packaging and Transport of Radioactive Material *per 10CFR71 i) Decontamination A.7 Tech. Spec. Surveillance A.8 Performing Maintenance A.9 Chemical and Radiochemical Control B. Additional NRC Requirements:

B.1 Tech. Spec. Administrative Controls a) SORC b) NRB c) Reportable Occurrences II. Equipment, Components, and Structures A. The following are items and systems contained in commitment letters to the NRC.

A.1 Accident Monitoring Instrumentation A.2 AC control power buses and inverters A.3 All systems which penetrate containment, up to and_ including the, containment isolation valve (identified in UFSAR Section 6.2.4)

A.4 Anticipatory reactor trip on turbine trip A.5 Auxiliary Building (including Control Room and Diesel Generator Area)

A.6 Auxiliary Building Ventilation System (supply and exhaust units)

A.7 Auxiliary Feedwater Storage Tank A.8 Auxiliary Feedwater System

/'

A.9 Component Cooling System A.10 Chill Water System A.11 Containment (including penetrations, concrete shielding, interior structures, air locks, equipment hatch)

A.llA Containment Polar Crane A.12 Containment Pressure - Vacuum Relief System A.13 Control Area Air Conditioning System SGS/UFSAR Revision 4 July 22, 1985

TABLE 17.2-1 (Sheet 3 of 5)

A.14 Control Panels - Class lE circuits A.15 Electrical Cable Tunnels A.16 Emergency Power for Pres*suri zer Heaters A.17 Emergency Power Supply System.

a) DC Power Supply System b) Diesel Generator Area Ventilation System c) Diesel Generators (including associated fuel oil, lube oil, starting auxiliary systems, fuel storage and day tanks, jacket cooling, governor, voltage regulation and excitation systems, piping and valves) d) Control Boards and Motor Control Centers e) Control equipment, facilities and lines required for above items f) Power distribution lines to equipment required for emergency transformers and switchgear supplying Engineered Safety Features (includes 4 kV, 460V and 230V vital buses)

A.18 Emergency Response Facilities (NUREG-0737, Supplement 1; document control and verification of functionality only)

A.19 Engineered Safety Features a) Containment Spray System (including spray pumps, spray header, spray additive tank, connecting piping and valves) b) Containment Ventilation System (including fan coolers, distribution ducts, dampers, HEPA filters and moisture separators).

c) ECCS (including Safety Injection and RHR pumps, RWST, Accumulators, "RHR heat exchangers, containment sump, sump

~"

screen vortex suppression devices, and connecting pipes and valves) d) Portions of the CVCS (including Centrifugal Charging Pumps, Boron Injection Tank, connecting piping)

SGS/UFSAR Revision 4 July 22, 1985

TABLE 17.2-1 (Sheet 4 of 5)

A.20 Expendable and consumable items necessary for the functional performance of critical structures, systems, and components (i.e., weld rod, boric acid, fuel oil, etc.)

A.21 Feedwater System (to outermost isolation valve)

A.22 Fire Protectjon System for safety-related areas (hardware)

A.23 Fuel Handling Building A.24 Fuel Handling Building Ventilation System (exhaust units)

A.25 Fuel Handling System A.26 Fuel Transfer Tube A.27 Hydrogen Recombiners, Hydrogen Analyzers, and Supports A.28 Instrument Air System (including accumulators, interconnecting piping and valves) for air-operated valves that perform a safety function A.29 Instrumentation and Control Systems required for safe shutdown (including safety-related instrumentation)

A.30 Instrumentation for detection of inadequate core-cooling A.31 Leakage Detection System (as discussed in UFSAR Section 5.2.7)

A.32 Main Steam System (to isolation valve)

A.33 Meteorological Data Collection Program (hardware)

A.34 Missile Barriers (protecting safety-related equipment)

A.35 Nuclear Instrumentation System A.36 Plant Shielding A.37 Process Instrumentation and Controls (those portions required for Class I equipment and systems)

A.38 Radiation Monitoring System (those portions required for Class I equipment and systems)

A.39 Radioactive Waste Disposal Systems a) Gas Decay Systems b) Compressor ,

A.40 Reactor Coolant System (including piping, valves, steam generators, pressurizer, safety and relief valves, block valves, piping to pressurizer relief tank, reactor coolant pumps, and supports)

SGS/UFSAR Revision 4 July 22, 1985

TABLE 17.2-1 (Sheet 5 of 5)

A.41 Reactor (including vessel, supports, internals, fuel assemblies, RCC assemblies and drive mechanisms, supporting and positioning members, and in-core instrumentation)

A.42 Reactor Protection System A.43 Residual Heat Removal System A.44 Safety Parameter Display Console (instrument calibration and verification only)

A.45 Sampling System (to outermost containment isolation valve)

A.46 Service Water Intake Structure A.47 Service Water System (entire system*serving the nuclear portion of the plant, as shown in UFSAR Figures 9.2-lA and B)

A.48 Shoreline Dike (for protection against excessive wave action)

A.49 Spent Fuel Pool Cooling System A.50 Steam Generator Blowdown System (to outermost containment isolation valve)

A.51 Switchgear Room Ventilation System A.52 Valve operators for all valves incorporated in this list B. Items designated in the Salem Master Equipment List (MEL) as safety-related 11 Yes 11 and* other items designated safety-related 11 No 11 , QA 11 Yes 11

• C. Items Re qui red by Reg. Gui de 1. 29 11 Seismic Design Classifications" Regulatory Position 3.

SGS/UFSAR Revision 4 July 22, 1985

ATTACHMENT 2 Justifications for changes to the Operational Quality Assurance Program description.

1) Page 17.2-1-section 17.2 The Words Nuclear Department Manual that occur in the second paragraph, have been revised to read Vice President Nuclear - Procedure Manual. This change is to reflect that actual title of the document in which the Operational QA Program is contained. The Nuclear Department Manual and Vice President Nuclear -

Procedure Manual are the same document, with the first reference being the generic reference and the second being the proper specific title.

2) Page 17.2-2-section 17.2.1.2.4(2)

This section has been added to clearly establish the responsibility for preparation and maintenance of the Quality Assurance Manual. The Manager - Nuclear Quality Assurance is responsible for the content of the Operational Quality Assurance Program documented in the Vice President Nuclear - Procedure Manual (VPN-1) and for the review of all implementing procedures including those addressing the maintenance provisions of the VPN-1 Manual.

This addition has been made in order to respond to the Nuclear Regulatory Commission letter of December 6, 1984 addressing 10CFR50.54(a) Quality Assurance Program Description Review, Salem Generating Station Units No. 1 & 2 which specifically requested this clarification.

3) Page 17.2-6-section 17.2.1.2.4.1 A change to the first full paragraph now clarifies the two mutually exclusive qualification requirements, currently reflected in paragraph 17.2.1.2.4.1 of the UFSAR - Rev. 3. This revision provides for clarification of the qualification requirements for the position of Manager, Nuclear Operations Quality Assurance, which was the second request in the Nuclear Regulatory Commission letter of December 6, 1984, addressing 10CFR50.54(a) Quality Assurance Program Description REview, Salem Generating Station Units No. 1 & 2.

4) Page 17.2.11-section 17.2.2.-11 It was indicated previously in revision three (3) that certificates of qualification for personnel performing inspection and test activities, were issued for the duration of the person's employment by PSE&G unless the persons status was changed. This information has been deleted from the text in order to satisfy the requirements set forth in Regulatory Guide 1.58 (ANSI N45.2.6) which provides for a maximum of three (3) years duration on certificates of qualification. This change more clearly defines the functions and organizations requiring certification in accordance with Regulatory Guide 1.58 and is more consistent with PSE&G actual practices, which is and has been tri-annual recertification of personnel.

5) Page 17.2.11-section 17.2.2.-14 The rephrasing within this section is for clarification of present commitments and does not constitute a reduction in current commitments. The justification for this is that the Standard Review Plan endorses a 2-hour fire rating specified in NFPA No. 232 and ANSI N45.2.9 (1979), but no new revision of Regulatory Guide 1.88 (last revised 10/76) taking a regulatory position, has been forthcoming.

6) Page 17.2.19-section 17.2.4 This section which addresses procurement document control has been revised to establish clarification of actual functional activities, which provides measures for NQA verification of reorders on Q-Listed material equipment or services, to assure that the originally reviewed and approved QA provisions have been maintained during the reorder cycle, as opposed to complete review and approval activities.

Page 17.2.21-section 17.2.4 2nd paragraph The word "selective" has been added in the first sentence of the second paragraph. This addition has been made to provide greater clarifications to existing commitments in other sections of the UFSAR, specifically that (1) "operating procedures", as identified on page 17.2-22-section 17/2-6, are not reviewed by NQA and (2) tat only maintenance, modification, calibration procedures for Q-Listed station work activities, that involve QA Inspection requirements are reviewed by NQA as identified in the 1st sentence of page 17.2-22-section 17.2.6

7) Page 17.2-21-section 17.2.6 5th paragraph The reference to the NQA Manual and NQA, as the responsible organization for review and approval has been changed to Vice President Nuclear Manual with the Vice President Nuclear and NQA now designated as the groups with review and approval responsibility. This is consistent with revision in section 17.2.1.2.4 (2). Reference item two (2) of this letter.

8) Page 17.2-27-section 17.2.10 This change was the third and final request in the Nuclear Regulatory Commission letter of December 6, 1984, addressing 10CFR50.54(a) Quality Assurances Program Description REview, Salem Generating Station Units No. 1 & 2 which was to replace to word "may" with the work "shall" in paragraph 1.7.2.10, which addressed the inspection of operating activities.

This paragraph was reviewed and the requested change has been incorporated.

9) Table 17.2-1 (sheet 3 of 5)

The Chill Water System has been added to the equipment, components and structures section of the "Q-List", since the Chill Water System serves as an ancillary function to the control room air conditioning which is currently identified in the Q-List-TAble 17.2-1.