ML18092A294

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Rev 3 to QA Program (Updated FSAR Section 17.2)
ML18092A294
Person / Time
Site: Salem  PSEG icon.png
Issue date: 07/22/1984
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Public Service Enterprise Group
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NUDOCS 8410050223
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J7.2 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 Generdtfog Station is accomplished in a manner which protects public health aQd 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 the operation phase of the Salem Generating Station.

This Operational Quality Assurance Program, hereafter also referred to as 11the QA Program, 11 1s.r:na inta ined by Nu cl ear Operations Qua 1 ity Assurance

( NQA), and is documented in the Nu cl ear Department Manua 1. 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 c~iteria 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 th~ details of how that policy is implemented for 10CFR50, Appendix B.

Applicable NRC Regulatory Guides, codes and*

standards, and the policy statements contained in 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 Ope~ational Quality Assurance Program, independent auditors from outside the company audit.the program every two years for

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p SGS-UFSAR 2540Q: 1 17.2-1 Revision 3 July 22, 1984

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compliance with 10CFR50 Appendix Band oth~r Regulatory commitments.

Reports of such ~udits are made directly to upper management.

PSE&G requires its suppliers and*contractors to assume responsibility for establishing and implementing QA/QC prograrns, as applicable, to meet 10CFRSO, Appendix B.

NQA reviews those programs and conducts appropriate monito*ring and auditing as required to assure that sup-pliers properly implement their QA/QC programs.

The Operational QA P~ogram verifies that requirements necessary to assute 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 Operation~l 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. Respon-

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

17.2.1.2 Nuclear*Departme~t The Vice President - Nuclear reports to the Senior Vice President - Energy Supply and Engineering and is responsible for managing and directing SGS-UFSAR 2540Q: 1 17.2-2 Revision 3 July 22, 1984

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  • I
  • the nuclear activities of the Company.

Reporting to the Vi~e President

- Nuclear are th~'*General Manager - Nuclear Services, General Manager -.

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

~ Hope Creek Oper~tions *and Mana~er - NQA.

Also reporting to the Senicir Vice President - Energy Supply and Engineering is the General Manager -

Nu cl ear Assurance *and Regulation. the* Manager - Corporate Quality Assurance reports *to the General Manager - Nuclear Assurance and Regulation and

~s located at the plant site.

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

17.2. 1.2.1 Nuclear *IJepartment - Nuclear Services The General Manager - Nuclear Services is responsibl~ for pro~iding technical support to Stat1on organization in the ~reas of radiation protection, site protection-, (including fire, security, and emergency p~eparedhess) planning an~ scheduling of plant betterment and mainte-nance work, in-service inspection, nuclear procurements and materials control, and station personnel t~aining.

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, and Technical Support Departments.

The General Manager - Salem Operations directs the SGS-UFSAR 2540Q: 1 17.2-3 Revis ion 3 July 22, 1984

activities of the Station Operations Review Committee (SORC) and is responsible for assuring that plant positions are staffed by fully qualified and trained personnel.

17.2.1.2.4 Nuclear Operations Quality Assurance The Manager NQA js responsible for the approval and coordination of nuclear-related QA programs established and implemented by Company

. departments. *He is responsible fo~ conduct-ing independent audits, with his staff or consultants, of quality related activities of Company departments, suppliers, and contractors.

The Manage~ NQA has the authority and responsibility to:

1.

Establish and implement a Qua 1 ity Assuran.ce Program in conformance with the requ)rements of 10CFR50, Appendix B,

2. Provide centralized c6ordination of Quality Assurance functions regarding Nuclear Operations.
3. 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 Safety Analysis Report (SAR),
4. Establish and interpret quality assurance requirements and policies for other departments,
5. Interpret quality assurance requirements of regulatory commitments and a~sist upper management in establishing policies needed to rneet those commitments,
6.

A~sure compliance with PSE&G Quality A~surance policies and applica-ble government regulations including Regulatory Guides, Standards, SGS-UFSAR 2540Q:l 17.2-4 Revision 3 July 22, 1984 r.

I Codes, etc., as committed in the Safety Analysis Reports and license, 7_.

Provide top management with visibility into the status and adequacy of implementation of the QA Program by reporti~g significant quality problems and their solutions, and recommending preventive or correc-tive action to prevent their recurr-ence,

8.

Provide supeort 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,

9. Represent the PSE&G Nuclear Operations Quality Assurance at regulatory agency public hearings and other meetings, on matters affecting the Operational QA Program, and
10. Stop work when significant conditions adverse to quality require such __ action.

The PSE&G policies a*nd organization structure assure that the Manager -

Nuclear Ope_rations 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 ~re 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 st~dy of quali~y ccintrol techniq~es, testing and inspection methods, and/or by having acquired working knowledge of and familiarity with the requirements of the applicable Codes and Standards for accor11pl ishing quality activities performed in the nuclear power industry
  • SGS-UFSAR 2540Q:l 17.2-5 Revision 3 -

J1,1ly 22, 1984 I

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, vendQrs, and operations forces, and

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

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 four 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 'responsi-bilities, 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 activi-ties affecting nuclear safety. The onsite advisory group is designated the Station Operations Review Committee (SORC).

Composed of key station personnel, its responsibilities include revi.ew of plant operations, reportable occurrences, investigation of Technical Specification viola-tions (with recommendations* to preclude recurrence), and procedure reviews for safety-related activities or plant modifications.

Recom-mendations of this advisory group are forwarded to the General Manager -

Salem Operations, with copies to the Chairman of the Nuclear Review SGS-UFSAR 2540Q: 1 17.2-6 Revision 3 July 22, 1984 I 1*

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~oard. !he SQAE is invited to all SORG meetings and attends them periodically as P.art of the planned surveillance program. *He receives minutes of all the meetings.

The off-site advisory group is the Nuclear Revi~w Board (NRB), which advises the Vice President - Nuclear in matters affecting nuclear safety or relatin~ to pl~nt operation or modification to the plant design.

The NRB is responsi~le for performing an independent review of plant activi-ties.

In addition, NRB is resµonsiole for selected planned, independent audits of plant operations in accordance with Technical Specification requirements. These audits are generally conducted by NQA undef. NRB cognizance.

The Manager, NQA is a member of the Nuclear Review Board.

SORC and NRB organization and responsibilities are delineated in the Te'chnjcal Specifications.

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

The Research & Testing~aboratory performs calibrations, analyses and evaluations on systems, equipment, and materials as requested* by PSE&G deµartments, and maintains tompliance 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-Presid~nt - Fuel Supply reports to the Senior Vice President - Energy Supply and Engineeriny. The Fuel Supply Department is responsible for arranging the procurement of uranium ore, Gonversion SGS-UFSAR 2540Q: l 17.2-7 Revision 3 July 22, 1984

and enrichment services and fuel assembly fabrication services to satisfy Nuclear Department core designs, enrichment requirements, and delivery scheduTes.

17.2.l.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 eneryy to the area of use and for distrib-uting it to the consumers. It is responsible for setting and testing protective relays for the external vital power supplies at the Station.

17.2.l.6 Purchasing Department The General Manager - Purchasing reports to the Vice President - Corpo-rate Services under the Senior Vice Preside-nt - Administration.

Initiation of requests for procurement of materials, equipment, struc-tures, 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 Cofporate purchasing policies established by the Purchasing Department.

17.2.1.7 Nuclear Assurance and Regulation Department The General Nanager - 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 and public hearings with local, state, regional, and federal re~ulatory agencies; and provides a management focal point for generic regulatory matters.

SGS-UFSAR 2540Q:l 17.2-8 Revision 3

  • July 22, 1984

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}7.2.2 OPERATIONAL ~UALITY ASSURANCE PROGRAM The Operational QA Program is designed to comply with the requirements of 10CFRSO, 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).

Proc~dures require that personnel also utilize the MEL System List in GOnJunction with the Component.List for determining whether an activity is safety-related and/or whether the QA Program applies to the activity. Once an activity has thus been determined to be safety-related or applicable to the Operational QA Program, established aµproved procedures are utilized in the performance of the activity.

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The QA Program is applied during the operational phase using a graded approach to ari ext~n~ cbnsistent with the item's or activity's impor-tance to safety. These activities are performed in compliance with license requirements and with applicable regulatory guidance.

Such regulatory guidance, with exception~ ~oted, includes:

1.

Regulatory Guide_ 1.8, 11Personnel Selection and Training 11, 9/75, (endorses N18.l),

2.

Regulatory Guide 1.17, 11Protection of Nuclear Plants Against Indus-trial Sabotage 11, 6/73, (endor~es NlS.17),

3. Regulatory Guide 1.29, 11Seismic.Design Classification 11, 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.

Regulato~y Guide 1.33, "Quality Assurance Program Requirements (Operation)," 2/78, (endorses N18.7-1976/ANS-3.2),

SGS-UFSAR 2540Q:l 17.2-9 Revision 3 July 22, 1984

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Regulatory Guide 1.37, "Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants*'r, 3/73, (endorses N45.2.1 ),

7.

Regulatory Guide 1.38, "Quality Assurance Requirements for Pack-aging, Shipping, Receiving, Storage, and Handling of Ite~s for Water-Cooled Nuclear Power Plants"l 10/76l (endorses N45.2.2),

8. Regulatory Guide 1.39, "Housekeeping Requirements for W*ter-Cooled Nuclear Power Plants", 3/73, (endor~es 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", 6/73, _
10. Regulatory Guide.1.54, "QA Requirements, for Protective Coatings Applied to Water-Cooled Nuclear Po~er Plants", 6/73, (endorses NlOl.4),
11. Regulatory Guide 1.58, "Qua 1 ification of Nu cl ear Power Pl ant Inspec-tion, Examinafion, a~d Testing Personnel", 9/80, (endorses N45.2.6).

All PSE&G personnel performing inspectiori, 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" *** 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."

Other factors may.provide reasonable assurance that a person can compe-tently perform a particular task. The other factors which may demon-strate capability in a g~ven job are previous performance or satisfac-tory completion of testing. These two factors will be considered when SGS-UFSAR 2540Q:l 17.2-10 Revision 3 July 22, 1984

  • ev~l~ating education and experience requirements for certification.

In addition, quaJ{fication certificates for personnel performing inspec-tion and test activities are issued for the duration of the person's employment by PSE&& unless the person's status is changed,

12. Regulatory Guide 1.64, "Quality Assurance Requirements for the Design of Nuciear Power Plants", 10/73, (endorses N45.2.ll),
13. Regulatory Guide 1.74, "Quality Assurance Terms and Deftnitions 11,

2/74, (endorses N45.2.10),

14. Reyulatory Guide l.88, "Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records", 10/76, (endors-es

. N45.2.9). Provisions for the storage of records comply with the requirements of Section 17.4 of NUREG-0800 (Standard Review Pl.an),

revision 2, July 1981, 15.. Regulatory Guide 1.94, "Quality Assurance Requirements for Instal-lation, Inspection, and Testing of Structural Concrete and Struc-tural Ste-el during the Construction Phase of Nuclear Power Plants",

4/7$ (endorses N45.2 *. 5). Major modifications made to the Salem Station will comply with Regulatory Guide 1.94,

16. Regulatory Guide. 1.137~

11Fuel-Oil Systems for Standby Diesel Genera-tors", 10/79. Uiesel fuel oil sampling is performed as follows:

1. A fuel oil sample is taken from each truck delivering fuel oil_

to Salem whenever possible~ However, if several trucks arrive at once, a minimum of l in 4 trucks is sampled depending on the shift~ staffing, arid existing personnel work load at the time.

2. All newly receiv~d 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.

SGS-UFSAR 2540Q:l 17.2-11 Revision 3 July 22, 1984

3. A small percentage of the fuel oil in the 20,000 barrel tank is introduced into the diesel fuel oil storage system as neces-sar~. This s~all percentage is added infrequently to the four 30,000 gallon Diesel Fuel Oil Storage Tanks (two for each unit) as necessary to 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.
5. All fuel oil samples taken in actions J-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 labora-tory.
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, 11Auditing Quality Assurance Programs for Nuclear ~ower _Plants,11 *-9/80 (endorses N45.2.12)
18. Regulatory Guide 1.146, 11Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants 11, 8/80, (endorses N45.2.23).
  • 19. Branch Technical Position APCSB 9.5-1, Appendix A, "Guidelines for Fire Protection for Nuclear Plants Docketed Prior to July 1, 1976",

2177.

SGS-UFSAR 2540Q:l 17.2-12 Revision 3 July 22, 1984

The QA Program is applied to the Fire Protection Program to an extent consi?{ent with the requirements of Section C of Appendix A to Branch Technical Position APCSB 9.5-1.

PSE&G organizations performing activities affecting nuclear safety, prepare and maintain implementing procedures and in structions. These procedures and instructions, and subsequent revisions thereto, are subject to NQA review and approval to an extent necessary to verify compliance with the Operational QA Program and the applicable quality-related Regulatory Guides and standards identified above *.

The General Manager - Salem Operations has instituted and will maintain an Administrative Procedures Manual for Salem Generating Station to implement the detailed requfrements 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 Gene~al Manager, and are approved by the General Manager -

Sal~m_Oper~fion~ and the* Manager -

~uclear Operations Qua11ty Assurance.

    • Regulatory Guide 1.33'requires that safety-related plant activities be conducted in accordance with written administrative controls prepared by 1nanagement.

The departmental procedures and instructions by which plant activities are performed are prepared by the responsible station depart-ment, as required by the Station Administrative Procedures, revie~~ed by the SQAE for quality 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 unles*s the review/approval process is accomplished.

Station Admin*istrative 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

  • SGS-UFSAR 2540Q:l 17.2-13 Kevi s ion 3 July 22, 1984 I

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

NQA revi~1s and analyzes quality-related problems occurring during the operational phase.

Items subject to revie~J include:

1.

Documented nonconformances 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 noncompli-ances and on audit findings, and

3.

NRC inspect~on'findings, notices, bulletins, etc.

The Manager Nuclear Operationi Quality Assurance 6r his designee, has the authority to stop work where continuance of an ~ctivity would

  • seriously compromise safety or constitute a persistent and deliberate failure to correct a serious deficiency *

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

l. Measures taken to improve QA program controls, and
2. Appropriate recommendations to achieve compliance with applica-ble requirements.

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

I The Operational QA Progra~ requires that activities affecting nuclear safety, I including activities affecting the fire protection of safety-related SGS-UFSAR 17.2-14 2540Q:l Revision 3 July 22, 1984

areas, be accoraµlished under suitably controlled conditions.

The program takes in~o consideration the need for procedures, special controls, cleanliness, special processes, test equip~ent, tools, and skills to obtatn the required quality and the verification of quality by inspection, test, examination, monitoring and independent review and audit. These attivities include, but are not limited to, des1gning, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, insta1ling, inspecting, testing, operating, maintaining, repairing, refueling, and modifying.

Personnel who have the responsibility to implement the Operational Quali~y Assurance Proyrarn 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 m~nagernent up to the Vice President - Nuclear as required.

Personnel_ performing safet~-related activities are trained and/or indoc-I trinated as necessary to assure that suitable proficiency'is achieved and maintained.

The Man~ger - 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 frorn outside the Company.

An outline of the course content is cont~ined in the. N~A Orientation, Training, and Qualification Manual.

The training and indoct~ination program is designed to famil-iarize the emµloyee 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, SGS-UFSAR 17.2-15 2540Q:l
  • Revis ion 3 July 22, 1984
4.

Nuclear Operations QA Program,

5. The QA program and the organization of major contractors,
6. Other organizations within PSE&G with which QANO interfaces, and
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 Construct ion, Engineering, Fuel

  • Supply, Research & Testing Laboratory, etc., who perform activities related to nuclear operations safety.

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

The Nuclear-Training Center is resp6nsible for th~ 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 Nu cl ear Support Department procedures, ap.proved by the Manager - QA Nuclear Operations, provide implementation direction for the intent of*

Regulatory Guide 1.G4 "Quality Assurance Requirements for the Design of Nuclear Power Plants". Within that department, the Nuclear Engin~ering Department has the following responsibilities:

1. Prepare and update detailed engineering and design documents, including drawings and specifications, for all systems, components and structures, SGS-UFSAR 2540l~: 1 17.2-16 Revision 3 July 22, 1984

.2. Specify applicable codes, standards, regulatory and quality require-ments, accep~ance standards and other design input in design output documents,

3. Identify syste1as, components, and structures which are covered by the QA Program,
4. Perfor1n des1gn verification for systems, compon_ents, and structures,
5. Perform safety evaluations of proposed design changes,
6. Prepare documents for procurement orequipment, materials and c*omponents, 7 ~ *Recommend engineering consultants and laboratories for procurement services ~nd cbordinate their activities,
8. Review de.sign documents submitted by suppliers (including the NSSS supplier) ~nd contractors, and
9. Specify, or approve as *required, inspections and/or tests.
10. Designate whether they will use the servic~s of other qualified engineering organizations both inside and outside PSEG.

The cognizant Engineer is responsible for the identification and comple-tion 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 1 imited

-* to, reactor physiCs, stress, seis1nic, thermal, hydraulic and accident.

Design verification is performed on design analyses, drawings, specifi-cations 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 SGS-UFSAR 2540Q: 1 17.2-17 Revision 3 July 22, 1984

changes to previously verified designs including evaluation of the

~ffects 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 ~rior authorization on an individual basis. Control of this function will be assured through periodic QA audits.

Desig~ verification methods include but are not limited to:

  • 1. Design reviews,
2. Alternate or independent calculations, and
3. Qualification testing.

Changes td specifications prepared-by the Engineering Department for items-covered by the QA Program are revie\\~ed and approved by NQA to assu~e that 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 SORG reviews proposed changes affecting nuclear safety and makes reco1nmendations concerning implementation of the change to the General Manager - Salem Operations: If the proposed modification involves a Technical Specification change or is considered by the SORC to involve an unreviewed safety question (10CFRS0.59), the matter is submitted to the NRB for a determination of its safety implication before a license change request. is submit~ed for NRC approval.

External interfaces with manufactur~rs, consultants, and other depart-ments, including procedures for the preparation, transmittal, review and SGS-UFSAR 2540Q: l 17.2-18 Revision 3 July 22, 1984

c.pproval of design infori.1ation, are identified in docurnents such as contracts, specifications, purchase orders, design data sheets, and dra~lings.

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

17.2.4 PROCUREMENT DOCUMENT CONTROL All procurement documents and changes thereto 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. This does not include reorder of items classified as commercial grade items which have been determined by NQA on the initial procurement to have no QA requirements applicable.

NQA review assures that spare and replacement parts are procured utilizing controls which are at least equivalent to the original procurement

1.

Identify applicable QA Program requirements,

2.

Reference applicable regulatory requirements,* codes, and stan-

dards,
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, and S.

Provide for PSE&G review and approval of critical procedures pri?r to fabrication, as appropriate

  • SGS-UFSAR 2540Q:l 17.2-19 Revision 3 July 22, 1984
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 coraplies with applicable criteria of 10CFRSO 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~ ~o not require a detailed written procedure.

Complex activities shall require detailed 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 alio contain acceptance criteria where appropriate.

.. ~

The General Manager - Salem Operations is responsible for assuring that station procedures are prepared, approved, and implemented in compliance with the Station Administrative Procedures. *oocuments affecting nuclear safety are reviewed by the SORC for technical content, and by the SQAE for QA requirements including designation of QA hold points where required and are approved oy 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 wih structures, systems, and components covered by SGS-UFSAR 2540Q: 1 17.2-20

-Revision 3 July 22, 1984

the QA Program.

These reference documents are kept up to date for the life of the statJon by the incorporation of approved and implemented modifications and design changes. Master lists of turrent editions or revisions.*of these documents are issued by the General Mariager - Nuclear Support to the General Manager - Salem Operations periodically to a~sure that only current, approved reference documents. are used at the station.

The SQAE review~ and approves station inspection plans, and procedures for test, calibration, maintenance, modification and repair. Chahges to these documents are also reviewed and approved.

In addition NQA is responsiole for review and approval of the following documens:

PSE&G specifications, test procedures, and results of preoperational testing.

17.2.6 DOCUMENT CONTROL Instructions, proc.edl!res~ *and drawings and changes thereto are approved by appropriate levels of m*anagement of -the PSE&G organizations producing such docuri1ents.

Supplier documents are controlled according to contrac-tual agreements with suppliers

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

Design Specifications: Nuclear Department/Engineering Department, NQA

  • --~

Design, manufacturing, construction and installation drawings:

Nuclear Department/Engineering Department Procurement documents:

Nuclear Department/Engineering Department, 1

Purchasing Department, NQA NQA Manual:

N~A Station Administrative Procedures: General Manager - Salem Operations, NQA SGS-UFSAR 2540Q:1 17.2-21 Revision 3

  • July 22, 1984

Maintenance, modification, calibration procedures for Q-listed station work activities: General Manager - Salem Operations, NQA Operating procedures: General Manager - Salem Operations, Station Opera-tions Review Committee (SORC)

FSAR:

Nuclear Department, NQA Manufacturing, inspect ion and testing instruct ions:

Nu cl ear Depart-ment/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, specif i*cat ions, and drawings received from the Nuclear Department/Engineering Department, or prepared at the station for use in operating, maintaining, refueling, dr modifying the nuclear safety-related structures, components and systems is the r~sponsibility 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. Measures have been established to insure that the Administrative Procedures and department instructions are up to date, are properly authorized, are chanyed only after required review and the approvals are obtained, and are distributed to cognizant personnel.

17.2.7 CONTROL OF PURCHAStD 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 SGS-UFSAR 2540q: 1

  • 17.2-22 Revision 3 July 22, 1984 I.
  • supply acceptible material, equipment, or services. The list need not include original~rn~~ufactur~rs of commercial catalog items. All QANO Program procurements are made from approved suppliers.

Selection and evaluation of prospective bidders and suppliers are performed by the responsible enyineer and the NQA.

The responsible engineer determin~s the technical competence of the supplier. - The NQA evaluates the P'l'.'Ospective supplier's quality assurance program for compliance with-the capability of meeting applicable requirements of 10CFRSO Appendix Band for the requirement that applicable progr~rn 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*contrattor*s procedures or ~anuals and changes thereto; _

2 ~ -ASME code stamp appro'val,

~-

3.

CASE register listing~

4.

Satisfactory past history of providing similar items, and

5. Survey of supplier 1s facility.

The evaluation of prospective suppliers is conducted utilizing standard checklist/forms designed t? include the 18 quality criteria of 10CFR50 Appendix Bas appropriate. Surveys of suppliers* capabilities shall include evaluation of managem~nt systems, and manufacturing process, as well as adherence to QA/QC procedures.

The results of supplier evalua-tions are documented by the appropriate checklist/form and filed

  • SGS-UFSAR 2540Q:l 17.2-23 Revision 3 July 22, 1984

Supplier control is r.iaintained through a planned inspection, lilonitoring.

and audit pro_gra~ 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 the N~A and the responsible sponsor engineer. This I

review establishes critical inspection points and establishes a Notifi-cation Point Program for the identified inspection or surveillance activitie~.

The.e~tablished irispection or sur~eillance 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 condutted by qualified NQA personnel or NQA agents at the supplier's/contractor's facility or at the generating station. Surveillances a~e conducted in accordance with written proce-dures and are designed to assure conformance with procurem~nt require-

.ments in accor~ance with the safety significance of the item or service.

Consistent with the_importance or complexity of the item -0r service, periodic evaluations of the supplier/contractor quality program are conducted.

Dependent upon the.evaluation, additional audits or correc-tions 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 AHWA, AISC, SPCC and ASME Section III 1971 and Summer 1972 Addenda or

. later). This will provide-the intended level of safety, and will not resu*lt in redesign of the system. Quality assurance requirements are consistent with the FSAR commitments.

SGS-UFSAR.

2540Q: 1 17.2-24 Revision 3 July 22, 1984 *

l.

~;:..

~

Jhe requirement for appropriate supplier dbcurnentation of conformance to applicable code,_standard, specification or other quality requirement is provided by the procurement document.

The supplier-provided documenta-:-

tion is reviewed either at the supplier's facility duririg 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, materfal and s~rvices is conducted by qualified personne1 to verify correct identification, and appropriate 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 MATERIALS, PARTS, ANU COMPONENTS Procurement document controls provide assurance that mater~als, parts, and components received ~an be properly identified. The identification is ma~ked 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 identjty be main-

. ~= tained either 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 2540Q:l 17.2-25 Revision 3 July 22, 1984

Material identification and tracieability shall be maintained for repairs, replace~ent, and modifications throughout operation.

17.2.9 CONTROL OF SPECIAL PROCESSES Procedures for special processes such as welding, heat treating, and NOE, assure compli~nce with codes and design specifications. The General Manager - 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 excep-tion of special process procedures prepared by code suppliers holding an.

11 N 11 stamp}.

  • Procedur.es prepared by suppliers are al so reviewed and approved by NQA.

17.2.10 INSPECTION A planned inspection program is conducted by personnel appropriately qua 1 if ied in accordance with Sect ion 17.2.2. The inspect ion program verifies conformance to the established procedure, code or standard, consistent with the ~ctivity*s importance to safety *

. When required, Inspection Hold Points, to be accomplished by the applicable QA or QC 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 Opera-tions Review Committee (SORC) may recommend to the General Manager -

SGS-UFSAR 2540Q:l 17.2-26 Revision 3 July 22, 1984

Salein Operations, additfonal or di'ffer*ent hold potnts, as a result of their review~

S~fety related procedures are reviewed by NQA prior to issuance and additional inspection hold points may be ad~ed to a procedure~ The hold points must not be passed without authorization frolil the applicable QA or QC representative. Typical critical activities fnclude:

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 ~n~ loading of radioactive matetial for shipment,
5.

Hydr6static testing of safety related systems,

6. *Acceptance testing of safety related system modifications, and
7.

atcepta~c~ testing of major r~pairs on safety related systems.

Inspection of operating activities (work functions associated with the normal operation of the pl~nt,- routine rnaint~nance, and certain

- technical services) may be conducted by qualified individuals other than those who performed or directly supervised the activity being

-~.-::.

inspected. These activities typically include periodic inspections of:

l. Storage areas,
2. Housekeep in!;) (General), * * *
3. Fire protection ~quipment,
4. Special handling tools and equipment, and SGS-UFSAR 2540Q:l 17.2-27 Revision 3
  • July 22, 1984 i
5.

NOE visual inspection ~equired by the Inservice Inspection Pro gram.

The applicable inspection and retest requirements necessary to assure that modifications or repairs have been accomplished correctly are proviJed 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 conduct~d by.the SQAE.

N~A performs ~onitoring of supplier and contractor activities. Discrepancies discovered during the conduct of the monitoring are.brought to the attention of the management responsible for actomplishment of the activity.

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

Retest requirements following repair or modification are provided by enyineering specifications and/or the responsible engineer, as were the oriyinal test requirements. The Operational Test Group is responsible for preparation of test procedures incorporating the engineering parameters.

Test procedures prescribe:

l. Prerequisites, SGS-UFSAR 2540Q:l 17.2-28 Revision 3 July 22,.1984
2.

Instruinentation and equipment for conduct of the test adequate to th~ test objective,

3.

Suit~ble ~nvironmental conditions and adequate test methods, and

4.
  • Acceptance criteria.

Te~t results ar~ documented and reviewed for acceptability by the quali-fied department representative. Sys tern tests performed f o 11 owing modifications to safety-related systems require review of test proce-dures 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 review*ed for the follouing:

1. Presentation of proper documentation,
2. Assurance that tests meet objectives, and
3.

Identification and reporting of unacceptable results and initi-ation of corrective measures.

Retention of test reports are described in Administrative Procedures.

17.2.12 CONTROL OF MEASURING AND TEST EQUIPMENT Test equipment, instrumentation, and controls used to monitor and measure activities affecti~g quality and personnel safety are identi-fied~ controlled, and calibrated at specific intervals. Written proce-dures for meeting these requirements include provisions for:

1. Specifying calibration frequency,
2. Recording and maintaining calibration records,.

SGS-UFSAR.

2540Q:l 17.2-29 Revision 3 July 22, 1984

.~

~*:

3. Controlling and calibrating primary and secondary standards,
4.

Determining methods of ca 1 ibration, and

5. Tracing use on safety related components.

Prior use of measuring and test equipment found to be out of calib~ation is evaluated for possible effect on safetyrelated equipment or func-tions. 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 induitry st~ndards 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 c~librated to the extent permitted by the state-of-the-art.

Test equipment is marked to indicate the latest calibration date anct the next re~uired calibration date.

Out-of-calibration identification is used for instruments and controls to indicate this status pending 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 specifying equipment requirements *

(performance characteris~ics, operational characteristics, special

-SGS-UFSAR 2540Q:l 17.2-30 Revision 3

  • July 22, 1984
  • ~torage and handliny cha~acteristics). Manufacturer's instructions ~nd recommendations,_design requirement~, and applicable codes and sta~dards are implemented, as appropriate. *Compliance with specific handling, storage or shipping requirements, as established by the cognizant Huclear Departrnent/En~ineering Department engineer is required.

Requirements for new components and spares, where applicable,*are included in the procurement documents.

17.2. 14 INSPECTION, TEST AND OPERATING STATUS Procedures are required to ~pecify 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 inadver~ent operation. These procedures are designed to prevent operation of valves andi.or switches which could result in ~ersonnel 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 co_mponents 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

  • havi failed in service are identified, and where practical segregated.

Documentation of the nonconformance includes a description of the non-conformance, and the disposition and inspection or retest requirements, as appropriate.

Al 1 dispositions* for.repair or use-as-is are r.equ-ired to be approved by the responsible engineering representative.

Rework or repair of nonconforming material, parts, or components are inspected SGS-UFSAR 2540Q: 1 17.2-31 Revision 3 July 22, 1984

and/or retested in accordance with specified test and inspection require~ents estgblished by the cognizant engineer based 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 nonconforrnance reports for quality problems and initiate reports to higher rnanageme~t, identifying significant quality problems with recommendations for appropriate action.

17.2.16 CORRECTIVE ACTION Oryanizations involved in activities cover.ed 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** cqntrol led by the issuance of an Action Request.

NQA

  • reviews action requests for quality trends and periodically reports the

. : $tatus and review results to management.

Responses to Action Req~ests are based on the four elements of correc-tive action whith are:

1. Identification of cause of deficiency,
2. Action taken to correct deficiency and results achieved to date,
3. Action take.n or to be taken to prevent recurrence, and
4.

Date when full compliance was or will be achieved.

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

c* The General.Manager - Sa l_em Operations is responsible for assuring that conditions adverse to qua 1 ity are promptly identified and corrected for SGS-UFSAR 2540Q:l 17.2-32 Revision 3 July 22, 1984.

all activities *involving ~tation operation, maintenance, testing, refueling and rnoqification *

..Administrative procedures which govern station activities covered by the QA Program, provide for the timely discovery and correction of non~

conformances.

This include receipt of defective material, failure or

  • malfunction of equipment, deficiencies or deviations of equipment from design perform~nce, and deviations from procedures.

In cases of significant conditions adverse to quality~ the cause of th~ 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 condition's requiring

Repetitive deficiencies~ procedure or process violations at the Station

  • which are not classified as -Operational Incidents or Reportable Occur-rences or nonconformances 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 main-

Design and construction records are replicated via microform and stored

_,.in record facilities at the generating station and at off-site locations_

  • SGS-UFSAR 2540Q: 1 17.2-33 Revis ion 3 July 22, 1984

The General Manager - Salem Operations is responsible for the permanent storage of statiqn records.

The retention period for records, the per~anent storage locatio~, and methods of control, identification, and retrieval are specified by administrative procedure.

Individual station department heads are responsible for submitting applicable department records to the Technic~l Document Room for retention.

17.2~18 AUDITS Audits of PSE&G and supplier organizations which implement the QA Program are performed by the NQA to verify complian~e 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 condutted usirig pre-established written procedures and check-lists. Areas of deficiency revealed by audits are reviewed with manage-ment and are required to be corrected in a timely manner.

Required corrective action shall be documented and verified. Follow-up ac~ion,

. 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.

l. Operation, maintenance, and modification,
2. Preparation, review, approval, and control of design, specifi-cations, procurement documents, in structions, procedures, and
drawings,
3. Inspection programs,
4. Indoctrination and training~

SGS-UFSAR 2540Q:l 17.2-34 Revision 3 July 22, 1984

5.

Implementation of operatiny and test procedures,

6. Calibration of *ileasuring and test equipment,
  • 7. Fire protection, and *
8. Other appiicable activities delineated in Table 17.2-1.

A written report of the results of each audit is distributed to appro-.

priate management reµresentatives 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 4A Program.

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

  • SGS-UFSAR 2540Q:l 17.2-35 Revision 3 July 22, 1984

I TABLE 17.2-1 (Sheet l of 5)

SALEM Q-LIST The listing below identifies those activities, services, structures, components and systems to which_the operational Quality Assurance Proyram applies.

I. Activities/Services A.

Safety Related Activities Delineated in Regulatory* Guide 1.33, App. A (See R.G. for furth~r breakdown ~f activities)

A. 1 Administrdtive Procedures a)

Security Proyram (Reyulatory Guide 1.17) b)

Equipment Control (e.g., Locking and Tagging) c)

Shift ~nd Relief Turnover d)

Bypass of Safety Fun~tions and Jumper tontrol e)

Maintenance of Minimum Shift Complement and Call-In of Personnel f) Fire Protection Program including Inspection b) Fire Consultants g)

Communication System A.2 General Plant Operating Procedures A.3 Startup, Operation, and Shutdown ~f Safety-Related Systems A.4 Ai.rnor1nal, 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)

PUR Gaseous Effluent System d)

R~diation Protect_ion includin!J 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 h)

Packaging and Transport of Radioactive Material per 10CFR71 i) Decontamination SGS-UFSAR 2540Q:l Revision 3 July 22, 1984

~.

I.

j I

p TABLE 17.2-l (Sheet 2 of 5)

A.7 Tech. Spec. Surveillance A.8 Perfor~ing Maintenance A.9 Chemical and Radiochemical Control B.

Additional NRC Requirements:

B.1 Tech Spec Adrn.inistrative Controls a)

SORG b)

NRB c)

Reportable Occurences B.2 Inservice Inspection Plan B.3 Reportin~ of Defects and Noncompliance B.4 Fuel Management B.5 License Conditions a)

Shift Tech.nical Advisor.

b)

Shift Supervisor Duties c)-

Safety Review Group and Onsite Evaluation II. Equipment, Components, and Structures A.

The following are items and systems contained in commitment letters to the NRG.

A.l 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 SGS-UFSAR 2540Q: 1 Revision 3 July 22, 1984 I

~

J TABLE 17.2-l (Sheet 3 of 5)

A.8 Auxiliary Feedwater ~ystem A.9 Component Cooling System A.lo Containment (including penetratio~s, concrete shielding, inte~ior structures, air locks, equipment hatch)

A. lOA Containment Polar Crane A.ll Conta~nraent Pressure - Vacuum Relief System A. 12 Control Area Air Conditioning System A.14 Control Panels - Class IE circuits A.15 Electrical Cable Tunnels A. 16 Emergency Power for Pressurizer Heaters A.17 Ernergenty Po~er Supply Systems a) DC Power Supply System b) Diese*1 Generator Area Ventilation System c) Diesel Generators {including a~sociafed fuel oil, lubeoil, starting auxiliary sy$tems, fuel storage and day tanks,

  • jacket cooling, governor, voltage regulat~on 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

. SGS-UFSAR 2540Q:l a) Containment Spray System (including spray pumps, spray headers, spray additive tank, connecting piping and valves) b) Containment Ventilation System (including fan coolers, distribution ducts, dampers, HEPA filters and moisture separators)

  • Revision 3 July 22, 1984

'**,*I l Iii TABLE 17.2-1 (Sheet 4 of 5) 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)

A.20 Expendable and consumable items necessa~y for the functional performance of critical structures, systems, and components

{i.e., welu rod, boric acid, fuel oil, etc).

A.21 A.22 A.23 A.24 A.25 A.26 A.27 A~28 A.29 A.30 A.31 A.32 A.33 A.34 A.35 A.36 A.37 A.38 SGS-UFSAR 2540Q:l Feedwater System (to outermost isolation valve)

Fire Protection System for safety-related areas {hard\\~are)

Fuel Handling Building Fuel Handling Building Ventilation System {exhaust units)

Fuel Handl~ng System Fuel Transfer Tube Hydrogen Recombiners, Hydrogen Analyzers, and Supports Instrument Air System {including accumulators, interconnecting piping and valves) for air-operated valves that perform a safety function Instrumentation and Control Systems required for safe shutdown

{including safety related instrumentation)

Instrumentation for detection of inadequate core-cooling Leakag~ Detection System {as discussed in UFSAR Secti6n 5.2.7)

Main Stea1i1 System {to isolation valve)

Meteorological Data Collection Program {Hardware)

Missile Barriers {protecting safety-related equipment)

Nuclear Instrumentation System Plant Shieldin~

Process Instrumentation and Controls {those. portions required for Class I equipment and systems Radiation Monitoring System {those portions required for Class I equipment an~ systems)

Revision 3 July 22, 1984

"\\.

I

~

A.39 a) b)

A.40 TABLE 17.2-1 (Sheet 5 of 5)

Radioactive Waste Disposal Systems Gas Decay Systems Compressor 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)

A.41 Reactor (including vessel, supports, internals, fuel assemblies, Rte 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 A.45 A.46 A.47 A.48 A.49 A.50 A.51 A.52 verification only)

Sampling System {to outermost containment isol~tion valve)

Service Water Intake Structure Service Water System (entire system serving the nuclear portion of the plant, as shown in UFSAR Figure 9~2-1)

Shoreline Dike (for protection against excessive wave action)

Spent Fuel Pool Cooling System Steam Generator Slowdown System (to outermost containment isolation valve)

~1itchgear Room Ventilation System Valve operators for all valves incorporated in this list B.

Items designated in the Salem Master Equipment Li~t (MEL) as safety-related "Yes" and other items designated sa~ety-related "No", QA "Yes".

t. Items Required by Reg. Guide l.29 "Seismic Design Classifications 11 Regulatory Position 3
  • SGS-UFSAR 2540Q:l Revision 3 July 22, 1984

BOARD Of DIR[CTORS OfflC~ Of Tiff Ctllff llfCUTIVE

---------------------------i CHAIRMAN Of THE llDARD i

I.

l'SUO RlSlARCll PRESIDENT UECUllVE SECRETARY CDRPOllA TION VICE PRESIDENT

  • PllESIDENT FINANCE ENERGY DEVELOPMENT CORPORAllON I

I I

I PRESIDENT SENIOR SINIOfl SENIOR SENIOR SENIOR VICE PRESIDENT*

VICE PllESIDENT

  • VICE PllESIDENT -

VICE PRESIDENT*

VICE PRESIDENT

  • i\\DMINISTRATION PLi\\NfflNO CORPORATE ENERGY SUPPLY CUSTOMER i\\HO RESEARCH PLANNING AND ENGINEERING OPfRAllONS GA~il>l..l PIPl:llNl I

I I

I SYSTCM INCORPORATrll PRESIDENT VICE PRESIDENT VICE PRESIDENT.

VICE PRESIDENT

  • VICE PRESIDENT
  • VICE PRESIOEN T Vlf;l PIH ~.nu NI AND COflPOAATE ADMINISTRATIVE fUELSUPPLY CUSTOMER ANO C';0Vl11NMCNll\\l GENERAL COUHSEl SERVICES PLANNING MARKE TINO SERVICES Af fAIRS
  • CNCRGY PIPELINE CORPORA 1 ION PRlSIOENJ VICE PRESIDENT *

, VICE PRESIDENT

  • VICE PRESIDENT*

VICE PRESIDENT,

HUMAN SYSTEM NUCLEAR RAIES AND RESOURCES PlANNINO LOAD ~NAGEM~Nt VICE PRESIDENT

  • VICE. Pf1ESIOENT
  • VICE PRESIOENT -

VICE PflESIOlNT

  • VICE PRl SllJ[ NI COMPU1ER SYSTEMS PUBLIC ENOINEUUNG ANO rnoDllCllON IRANSUISSION ANO ANO RELATIONS CONS rnuc TION OISIRIBUJION SERVICES PUBLIC SERVICE ELECTRIC AND QAS COMPANY General Company. Organization Chart SALEM NUCLEAR QENERATINQ STATION UPDATED FSAR FIQ
17. 2-l ENERGY U AMIN~'

SlAVICES conPon." TtON l'HE~IOHH I

I I

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f".l1'(1 01/t ll',f A~*

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.,, *I JI VICE PRESIDENT ENGINEERING AND CONSTRUCTION SENIOR VICE PRESIDENT ENERGY SUPPLY AND ENGINEERING V,I CE PRES I DENT VICE PRESIDENT FUEL SUPPLY NUCLEAR GENERAL MANAGER NUCLEAR ASSURANCE AND REGULATION VICE PRESIDENT PRODUCTION Revision 1 July 22, 1983 PUBLIC SERVICE ELECTRIC AND GAS COMPANY Office of the Senior Vice President-Energy Supply and Engineering SALEH NUCLEAR GENERATING STATION l 7. 2-2 UPDATED FSAR FIQ

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MANAGER NUCLEAR OPERATIONS QA e

VICE PRESIDENT NUCLEAR PUBLIC AFFAIRS MANAGER

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PROCURE.MENT ENGINEER PUBLIC SERVICE ELECTRIC NC> DAS COMPANY Quality Assu*ran*ce SALEM NUCLEAR GENERATING STATION UPDATED FSAR SALEM STATION

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