ML20046B072

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Submits Rev 5 to Hope Creek Generating Station UFSAR Which Contains Text,Table & Figure Changes Required to Accurately Reflect Current Plant Configuration
ML20046B072
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 05/06/1993
From: Labruna S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20046B062 List:
References
NLR-N93066, NUDOCS 9308030064
Download: ML20046B072 (25)
v • d • e


Text

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. GM 13-of -

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' Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department MAY 0 61993  :

NLR-N93066  !

r United States Nuclear Regulatory Commission .

Document Control Desk Washington, DC 20555 Gentlemen:

l UPDATED FINAL SAFETY ANALYSIS REPORT, REVISION 5 i HOPE CREEK GENERATING STATION DOCKET NO. 50-354

original and ten (10) copies are being transmitted.to the Document Control Desk, one copy is being sent directly to the >

Region I Administrator and.one copy is being.sent directlylto.the l Hope Creek Resident Inspector.

Revision No. 5 to the Hope Creek UFSAR contains text, table and  :

figure changes required to accurately reflect the current plant I configuration. In addition, there are corrections of l typographical errors and general editorial changes. A brief I summary and explanation for each change is provided in Attachment 1 to facilitate your review.

Should you have any questions regarding this submittal, please do not hesitate to contact us.

Sincerely

/C e S. LaBruna Vice President - )

Nuclear Engineering Attachment (1) i 9309030064 DR 930723 's p ADOCK 05000354'-

PDRt

. The pmeris in murlands.

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l 9A Correction of typographical errors and a clarification regarding data contained in the Fire l Hazard Analysis Tables.

11.5 Correction of the description of the Radiation 12.3 Monitoring System due to resolution of DEFs.

11.5.2.2.3 Reflect normal operation for the low range sample pump 1C-P-372 of the radiation monitoring system for the filtration, recirculation, and ventilation i system vent as continuously running.

13.1.2 Station organizational changes.

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i 13.4 Incorporation of changes from Technical

) 13.5 Specification Amendment 52 to clarify and improve l l 17.2.2 the process flow, membership composition, and 17.2.8 "

requirements relative to SORC. '~

I 17.2.1 Reflection of current organizational structure 17.2.2 and programmatic changes as well as editorial 17.2.6 enhancements related to Quality Assurance during 17.2.11 the operations phase.

' 17.2.15 17.2.18 17.2.6 Revised method for revision control of proced,o and instructions.

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17 2.1

. Organization r 6

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 the station.

Implementation is assured by ongoing review, monitoring and audit General Manager - Quality under the direction of the ,

Assurance / Nuclear Safety Review, who reports to the Vice President  ;

and Chief Nuclear Officer. <

t 13.1-1 through 13.1 10 and ,

Company organization is shown on Figures  !

17.2 1. Responsibilities for activities affecting safety are I described in the following sections. i r

17.2.1.1 Nuclear Denartment

- - 4 7 . , .!

-l The Vice President and Chief Nuclear Officer (VPCNO) is responsible l for managing and directing the nuclear activities of the company. j Overall duties and responsibilities of the Nuclear Department are .

l provided in Section 13.1. General managers reporting to the VPCNO _+

are responsible for . implementation of QA requirements by their are contained in the Nuclear f staff. These QA regsirements ),

individual department Administrative Procedures.. Manual. and ~in l i

manuals. .>

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1 The VPCNO regularly assesses the scope, status,. adequacy, and l

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compliance of the QA program to 10CFR50, Appendix B through: '

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1. Frequent contacts in staff meetings, QA audit reports, t audits by independent auditors, NRC inspection reports, ^!

department status reports.  !

2. An annual assessment of the QA program is preplanned and documented. This assessment addresses the scope. . status, Corrective action is :l and ~ adequacy of the QA program. ,

identified, and. tracked. ,

l 17.2-3 Revision.4 HCGS-UFSAR April'11',21992

a , _ . m <_--,4'+ -e41-ww-.. J. +h'* A-. _a_A _,

17.2.1.1.1 Quality Assurance .

The General Manager - Quality Assurance / Nuclear Safety Review f; j

(QA/NSR) is responsible for defining, formulating, implementing, and coordinating the QA program. He has been delegated the authority. l i

and has the independence to interpret quality requirements, identify and provide recommendations or quality problems and trends, solutions to quality problems. He is responsible for approval of the QA/NSR Department Manual used during the operations-phase of the nuclear stations. He also is responsible for. assuring compliance j with established requirements for the QA program through document  ;

review, inspection, monitoring, and audit. QA provides a l

centralized coordinating function for QA/QC activities applied to the opera.cion phase. '

The General Manager .QA/NSR has the authority and responsibility to ,

issuance of ' a 'stop work order, vnen' l stop work through the  ;

significant conditions adverse . quality require such action.  ;

The PSE&G policies and organization structure assure that the .!

l General Manager - QA/NSR has sufficient' organizational freedom and.

independence to carry out his responsibilities.

Responsibilities of the Manager-QA Programs and Audits include the  !

following:  ;

er .- (4

l. Preparation and maintenance of the QA/NSR organization manual, the QA Program description in the UFSAR and the Operational QA -

1 Program description in the Nuclear Administrative Procedures-  ;

Manual. 1 and approval of PSE&G QA Program implementing 2 Review

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procedures.

3. Development and implementation of the QA Audit Program.

i 17.2-4 Revision 5 HCGS-UFSAR May ll, 1993 1

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Program orientation for Nuclear Department

4. Conducting QA f personnel., administering the training and certification program involved in inspection and auditing for QA personnel l

activities, maintaining the QA training plan, and maintaining r QA training records.  ;

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5. Review of new regulatory requirements for QA program impact. ,
6. Development and implementation of a trend analysis program to  !

identify quality problems. ,

7. Coordination of the commitment verification program on a ,

selected basis. i Responsibilities of the Manager - QA Engineering and Procurement include: , ,,

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documents such as 'eq'ihment u l

1. Review of engineering specifications, weld procedures, etc, for inclusion of QA reqairements. i

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2. Review of specifications for inclusion of QA requirements. r
3. Review of procurement documents for insertion of applicable QA ,

requirements. .

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4. Conduct of supplier surveys, audits, and surveillances.

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5. Performing supplier evaluation. ,

on items subject to

6. Performing snaterial evaluation activities the QA Program.

Assurance reports to the Manager - Station Quality The as shown on Figure 17.2-1. His General Manager - QA/NSR, of the inspection responsibilities include implementation 17.2-5

. Revision 5 HCGS-UFSAR May 11E1993- ,

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the plant,  ;

and monitoring program for activities conducted at -

surveillance of site contractor activities and approval of plant 't quality related implementing' instruction.

Review are 3 Manager - Nuclear . Safety Responsibilities of the described in Section 13.1. o i

i 17.2.1.1.1.1 Quality Assurance Personnel Qualifications i The General Manager - QA/NSR and the QA managers reporting directly in the to him must each have a combination of 6 years of experience ,

field of QA and operations.

At Icast 1 of these 6 years of i

experience must be in the overall implementation of a nuclear power of 4 of the A minimum of 1 year and a maximum plant QA program. l 6 years of experience may be fulfilled by related technical examinations, or academic training. Personnel performing inspections,

.f and test activities (i.e., to verify conformance) are certified as their-Level II, or Level III, as appropriate to Level 1, [

responsibilities, also in accordance with Regulatory Guide 1.58.  !

Personnel performing quality assurance audits are- certified as auditors or lead auditors, as appropriate to their responsibilities 4 in accordance with Regulatory Guide 1.146. lii above qualifications with  ;

The General Manager - QA/NSR fulfills the Li the addition of the following: l n- *SY  %

1. Knowledge and experience in quality assurance, t

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2. High level of leadership with the ability to command the respect and cooperation of company personnel, suppliers, and construction forces, J l

Initiative and judgment to establish related policies to

.3. ,

attain high achievements and economy of operations.

t 17.2-6 Revision 4 '

HCCS-UFSAR April'11, 1992  ;

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17.2.1.1.2 Operational Review l

.f Three advisory groups, the Station Operations Review Committee j (SORC), the Onsite Safety Review group (SRG), and the Offsite safety f review group (OSR), are responsible for reviewing and evaluating l 6

items related to nuclear safety. The overall responsibilities of l

)

these groups are provided in Section 13.4 The Manager - Station  !

Quality Assurance is invited.to all SORC meetings and r2ceives . the j minutes of the meetings. He attends the meetings periodically. .!

L As part of its independent review functions, the OSR is responsible for selected preplanned, independent audits of plant operations in accordance with Technical Specification requirements. These audits are generally conducted by QA under OSR cognizance. 9 r

17.2.1.2 Research and Testine Laboratory i

The Research and Testing Laboratory is a part of the PSE6G Research Corporation, which is an independent entity.

The Research and Testing Laboratory performs calibrations, analyses, and evaluations on systems, equipment, and materials, as requested f

. by PSE&G departments, and maintains compliance with its quality assurance program.

17.2.1.3 Nuclear Fuels Denartment j

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The Manager Nuclear Fuel reports directly to the Vice-President -

Nuclear Operations. The Nuclear Fuel Department is responsible for-arranging for procurement of uranium ore, conversion and enrichment services and fuel assembly, fabrication services to satisfy Nuclear {

Department core designs,- enrichment requirements, . and ' delivery.

schedules.

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17.2-7 HCGS-UFSAR Revision 5 May 11, 1993

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17.2.1.4 Distribution Svstems Department .

f The Vice President - Distribution Systems reports to the Senior Vice President Electric. This organization is responsible for It is responsible' [

distributing electrical energy to the consumers.

f for setting and testing protective relays for the external vital  !

power supplies at the station. .

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17.2.1.5 Purchasine Denartment 't, b

k The General Manager - Purchasing reports to the ' Vice President '-

Information Service and Corporate Services under the Senior Vice.

President - Corporate Performance.

Initiation of requests for procurement of materials, equipment, structures, and services required to support operations at the i

station is the responsibility. of the Nuclear Department.

Procurement of same is the responsibility of the General Manager - ,

Purchasing. Both activities are bound by Nuclear Department  :

l procedt..es and corporate purchasing policies established by the Purchasing Department. P Nuclear Human Resources 17.2.1.6 l

The General Manager - Nuclear Human Resources reports to the Vice i President and Chief Nuclear Officer and ' is responsible _w for the -, l' implementation of screening, testing and evaluation requirements.

described in 10CFk26 " Fitness-for-Duty Program".

17.2.2 Quality Assurance Program The QA program is designed to comply ' with the requirements of 10CFR50, Appendix B, and with fire protection program requirements .

of Appendix A of Branch Technical Position No. 9.5-1.

This program is applied to items and activities that can affect the health and I

'l 17.2-8 Revision 5 )

.HCGS-UFSAR May 11, 1993

Concrete and Structural Steel. during the Construction .

Phase of Nuclear Power' Plants 17 .. Regulatory Guide 1.116, Quality Assurance Requirements for Inspection, and Testing of Mechanical Installation.

Equipment and System i j

18. Regulatory Guide 1.123, Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear '

1 Power Plants Regulatory Guide 1.137, Fuel.011 Systems for Standby 19.

Diesel Generators -

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20. Regulatory Guide 1.143, Design Guidance for Radioactive Structures, and Components Waste Management Systems, d

'" s Installed in Light Water Cooled Nuclear PowermPlannt

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Quality- Assurance

21. Regulatory Guide 1.144, Auditing }

Programs for Nuclear Power Plants 1

22. Regulatory Guide 1.146, Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants
23. BTP 9,5-1, Appendix A, Guidelines for Fire Protection for Nuclear Plants Docketed Prior to July 1, '1976. -e ,

I to revision level; Commitments to Regulatory Guides,- with respect '

exceptions, etc, are contained in Section 1.8. 1 The code QA requirements are used for the procurement- of systems, components and structures covered by the ASME Boller and Pressure - ,

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'l Vessel Code Section III (classes' 1, 2, and 3). The standard ' QA =

items following. receipt at l program controls apply to Q-Listed code l

the station.

In addition, applicable requirements of- Regulatory '  !

Guide 1. 38 are applied to ASME Code procurements where necessary to assure safe shipment.

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17.2-11 '!

Revision 5 HCGS-UFSAR- May11,f1993.

Substantive changes to the QA program described herein will be ~

30 days of implementation.

submitted to the NRC within Nonsubstantive changes will be identified in the annual UFSAR updates.

PSE6G organizations performing safety related activities prepare and These procedures maintain implementing procedures and instructions.

and instructions, and subsequent revisions thereto, are subject to QA review and concurrence to the extent necessary to verify f compliance with the QA Program and the applicable quality related '

Regulatory Guides and standards identified above.

The station General Manager - has instituted .and will maintain an '

administrative procedures (AP) manual for the station.

Regulatory Guide 1.33' requires- 'that plant.. activities affecting  ;

with quality-related ite'ms' 'and' service's 'be ~ conducted :in accordance prepared by management. The ,

written administrative controls activities are performed  ;

procedures and instructions by which plant l are prepared by the responsible organization as required by Nuclear ,

Administrative Procedures Manual, reviewed by the organization responsible for the activity, reviewed as required by QA and SORC ,

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17.2 12 Revision 5-HCGS-UFSAR May 11, 1993 4

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l the manager. Nuclear Administrative approved by department Procedures (NAPS) and Station APs and all subsequent revisions I

thereto are reviewed by QA and SORC and are approved by the Station j

General Manager. Procedures cannot be implemented unless the

' review / approval process is accomplished. The Nuclear Administrative F Procedures Manual provide a means to accommodate on-the-spot changes to subtier implementing procedures. The routine practice for  ;

revising a procedure is to repeat the original review and approval  ;

sequence. I Implementation of the QA program is verified by means of independent

[

inspections, monitoring, and audits conducted by QA.

r occur during QA reviews and analyzes problems affecting quality that the operational phase. Items subject to review include:

t

1. Documented nonconformances occurring at the supplier's .

l facility and those identified during receiving, , storage, and operation, e g., Deficiency installation, test, Reports. Nonconformance Reports, Work Orders, Licensee I

Event Reports, etc.

corrective actions taken on significant j

2. Documented noncompliances and on audit findings.

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3. NRC inspection findings, notifications, bulletins, w etc.

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The General Manager - QA/NSR, or his desi 5 nee, has the authority to -

stop work through the issuance of a Stop Work Order. Yhere-continuance of an . activity would seriously compromise quality , or

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constitute a persistent and deliberate failure to correct a serious i the Manager -Station'~ Quality Designees include deficiency.

Assurance for activities conducted at the station and the Manager - '

QA Engineering and Procurement for supplier activities.

QA reports significant problems affecting the quality assurance 1 program to respective management along with: 1 i

17.2-13 Revision 5 -l HCGS-UFSAR May 11;J1993

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1. Measures taken to improve QA program controls
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2. Appropriate recommendations to achieve compliance with i applicable requirements.

and administrative procedures provide all ,

Management policy personnel with awareness and direction for reporting of defects and noncompliance pursuant to 10CFR21.

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The QA program requires that safety-related activities including I be activities affecting the fire protection of safety-related areas, The program f accomplished under suitably controlled conditions. .

takes into consideration the need for procedures, special controls, cleanliness ~, special processes, test' equipment, tools, and skills to l I

obtain the required quality and the verification of quality by l

_ inspection, test, examination, monitoring, and independent review to, and audit. These activities "includei but are not limited l

designing, purchasing, fabricating, handling, shipping, storing.

installing, inspecting, testing, operating,  !

cleaning, erecting, saintaining, reworking, repairing, refueling, and modifying.  !

Personnel who have the responsibility to implement the QA program

  • also have the responsibility and authority to escalate unresolved quality problems to the level of management necessary to ' e f fe c t -

resolution. Escalation is applied by QA personnel to increasingly l

higher levels of management, up to the VPCNO, as required.,

1 are trained Personnel performing Q,F, and R-designated activities J .

7 or indoctrinated as necessary to assure that suitable proficiency is' r Personnel outside-the QA organization who l achieved and maintained.

perform inspections and tests are : trained - and qualified in QA  ;

concepts and practices.  :

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~l 17.2-14 Revision 5 HCGS-UFSAR May 11', 1993- ,

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. Orientation is provided for new employees entering QA from other f An' outline organizations within PSE&G and from outside the company. >

of the course content and program objective is contained in . the QA f

training and certification program. The training and certification- i program is designed to familiarize the employee with:

Codes, regulations, specifications, .etc, applicable to 1.

nuclear and other power generation equipment [

i procedures, instructions, specifications,  ;

2. QA documentation, records, etc
3. Auditing objectives and techniques t
4. Operational-Quality Assurance Program  :

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5. Other organizations within PS$&G with which QA interfaces -;

QA administers formal QA training sessions for personnel outside the QA organization who perform safety related activities. The content

~ of these training programs, dates of the sessions, and names of the i evaluations are attendees and their individual performance documented and retained.

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4 17.2-15 Revision 5 HCGS-UFSAR May 11, 1993

t Personnel requiring certification are evaluated to establish their .

level and discipline.

qualifications for their respective Recertification is based upon demonstrated continued proficiency or Personnel requiring certification in requalification, if necessary. ,

accordance with Regulatory Guide 1.58 are limited to personnel who  :

-perform inspection, test and non-destructive examination (NDE) l activities., personnel who perform post desig,n modification testing, I

tests and Nuclear Inspection Services personnel who perform NDZ and I Those above personnel ,

required by the Inservice Inspection Program.

who perform visual examination (VT1, 2, 3 and 4) and NDE in  ;

accordance with the Inservice Inspection Program are trained, qualified and certified in accordance with a program which j

additionally meets the prescribed supplementary requirements of ASME <

periodic training needsSection XI. These personnel receive a j assessment to identify additional supportive training needs, as well performance. The )

as, to evaluate individual post-training .j n . +c assessment period is three years 'o r less.

Personnel who are -

level and discipline qualified and requalified for their respective - 3.1 and in accordance with Regulatory Guide 1.8 and ANSI /ANS direct or supervise the conduct of individual preoperational, including Technical startup, and operational inspections and tests, Specification Surveillances and periodic inspection and test of fire-protection equipment, do not require certification per Regulatory When a single inspection or test Guide 1.58 and ANSI N45.2.6 1978 requires implementation by a team or group, personnel not meeting 1.58 and ANSI N45.2,6 J978 may the' requirements of Regulatory Guide be used in data-taking assignments or in plant or equfpment. _

operation provided they are supervised or overseen by .an individual participating in the inspection, examination, or - test and the~

their respective level individual is qualified and requalified for  ;

and discipline in accordance with either Regulatory Guide 1.8 and ANSI /ANS - 3.1 or the individual is certified in accordance In with '

Regulatory Guide 1.58 and ANSI N45.2.6 1978 as appropriate. =

addition, Regulatory Guide 1.58 and ANSI N45.2,6 1978 do not apply to NRC - Licensed Operators and Senior Operators for the performance of duties specified in 10CFR55 " Operator Licenses".

17.2-16' Revision 4 HCGS-UFSAR April 11, 1992

made by cognizant department heads and as a minimum, complies with ,

t applicable requirements of Regulatory Guide 1.33.

scope, statement of Procedures include, as appropriate, applicability, references, prerequisites, precautions, limitations, and checkoff lists of inspection requirements, in addition to the s Instructions, detailed steps required to accomplish the activity.

procedures, and drawings also contain acceptance criteria where appropriate, ,

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The station General Manager is responsible for assuring that station compliance procedures are prepared, approved, and implemented in Documents with the Nuclear Administrative Procedures Manual.

affecting nuclear safety are reviewed by the ' SORC for + .. technical '

content, by QA for QA requirements, and are approved by the responsible station department manager or his designee.

Plant Betterment is The General Manager - Engineering and responsible for issuing specifications, drawings, blueprints, and '

Q, F. and-instruction and technical manuals associaced with I Approved and R-designated structures, systems, and components.

implemented modifications and design changes are incorporated to Master lists these reference documents for the life of the station. ,

of current editions or revisions of these documents are periodically  !

Betterment to issued by the General' Manager - Engineering and Plant ,

the station General Manager to periodically assure that onlycurrent .

and approved referenced documents are used at the station, t

QA reviews and approves selected station procedures that implement' I

calibration, maintenance, including testing,  ;

the QA program, '

modification, rework, and repair. Changes to these documents ~ are also reviewed and approved. In addition, QA is responsible for review and approval of selected specifications, rest procedures, and ,

results of testing.

l 17.2-23 Revision 4 HCCS-UFSAR April.11, 1992 I

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_17,2,6' D'ocument Control Instructions, procedures, drawings, and changes thereto are reviewed for the inclusion of appropriate QA requirements approved by organizations appropriate levels of management of the PSE6C producing such documents, and distributed on a timely basis to using for the timely removal of locations. Measures are provided obsolete or superseded documents from the using location. Supplier documents are controlled according to contractual- agreements with suppliers.

The following is a generic listing of key documents for the operational phase , showing minimum organization responsibility for review and/or approval, including changes thereto:

1. Design specification - Engineering and Plant Betterment, Station Technical Department, QA.
2. Design . modification, manufacturing,. construction, and installation drawings - Engineering and P. ant Betterment, Station Technical Department Nuclear Services, station operations
3. Procurement documents - initiating nuclear department organization, Purchasing Department, Site Services, QA Administrative Procedures Manual = Nuclear 4 Nuclear Department organizations responsible for implementation, QA .
5. Nuclear department second tier manuals, including station administrative procedures - cognizant department head, QA
6. Maintenance, modification, and calibration procedures for Q, F, and R designated station work activities ' Station I

operations I

7. Operating procedures - station operations 17.2-24 llCGS-UFSAR Revision-5 -

May 11,.1993

8. UFSAR - Nuclear Services and other Nuclear Department.  !

organizations responsible for implementing- applicable sections.

In addition, QA reviews all UFSAR sections and subsequent changes for compliance with applicable- QA program requirements

9. Maintenance, inspection, and testing instruction - Nuclear .

Department implementing organizations i

10. Post modification test procedures - Engineering and Plant Betterment, Station Technical Department ,
11. Design Change Requests - Engineering and Plant Betterment, Station Technical Department, QA QA involvement in the work activity includes review of work f procedures prior to approval for designation of inspection hold i points (see Section 17.2.10), review of completed safety-related Vork Orders on a sampl'ing basis, and periodic QA surveillance. ,

The establishment and maintenance of a document control system for all instructions, procedures, specifications, and drawings received from the Nuclear Department, or prepared.at'the station for use in operating, maintaining, refueling, or modifying items and services covered by the QA program, is the responsibility of the Manager -

Meth_ds o and Systems. The Nuclear Administrative ' Procedures Manual describes the control of ' specific documents. Control o f* s ta t> ion practices is included in the administrative procedures. and in directives authorized by the responsible station; department ,

department managers. Measures are established to assure that .the administrative procedures and department directives are up to date,

. properly authorized, changed only after the required review and

.l approvals are obtained, and distributed to appropriate personnel.

  • Design' change procedures provide for the timely update of affected drawings, following- design change implementation,- to reflect as-built configuration. A computerized data base controlled by. the Engineering and Plant Betterment Department is used to control drawings and specifications.

17.2-25 Revision 5 HCGS-UFSAR May 11, 1993 i

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Revision control of ' procedures and instructions is accomplished ,

through the control of indices. Controls' of software affecting nuclear safety are identified in the Nuclear Administrative Procedures Manual. These controls are based on applicable guidelines provided by the NRC and include sof tware review and j I

approval as well as access controls to prevent unauthorized software i changes.

1 17.2.7 Control of Purchased Material, Equipment, and Services i QA maintains an up-to-date listing of approved suppliers- of 1

material, equipment, and services covered by the QA program. This list identifies suppliers and contractors who have demonstrated the ability to supply acceptable material, equipment, or' services. The-list includes manufacturers of commercial grade items. All QA  ;

program procurements are made from approved suppliers. .

The responsible. engineer and QA personnel select and evaluate .

t prospective bidders and suppliers. The responsible engineer :i determines the technical competence of the supplier, while QA evaluates.the prospective supplier's QA program for the capability of meeting applicable requirements of 10CFR50, Appendix B, and for extending applicable program requirements to subtier suppliers.

Qualified QA personnel evaluate the . prospective supplier's QA  :

capability using one or more techniques, including abut not necessarily limited to:

1. Evaluation of supplier's or contractor's procedures or
  • manuals and changes thereto
2. ASME code stamp approval

)

Nuclear Utility Procurement Issues Council (NUPIC) o'r .j 3.

Nuclear Fuel Users Forum (NFUF) Audits.

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'4 . Satisfactory past history of provi :ng similar items l i

17.2-26 l HCGS-UFSAR Revision 5 l May 11, 1993 .l

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17.2.11 Test Control ,

l Q, F, and R-designated equipment and components that must be tested l periodically to assure- satisfactory performance, or have been replaced, modified, or repaired, are tested by qualified personnel  !

in accordance 'with written procedures that provide acceptance l criteria based on requirements contained in applicable design and i procurement documents.

Provisions are implemented that assure that nonconformances are corrected or resolved prior to the initiation of the preoperational test program on the item.

t Retest requirements are provided by engineering specifications or the responsible engineer, or both as were the original test l requirements. The E&PB Department is responsible for preparation of ,

test procedures incorporating.the engineering parameters. .

Test procedures prescribe, as applicable:

1. Prerequisites, including completeness of test item (s) l
2. Instructions for performing the test
3. Instrumentation and equipment for conduct of the test ,

r adequate to the test objective w i adequate ' test 4 Suitable environmental conditions and methods '

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5. Critical test sequenc2 -)

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6. Acceptance criteria. . t I

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.i 17.2-35 HCGS-UFSAR Revision 5 May 11, 1993-.

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Test results.. including verification of above items, are documented . i by the qualified department _

' and reviewed for acceptability to f representative. System tests performed following modifications j Q, F, and R-designated systems require review of test procedures and l test results by the SORC.

In addition, the Nuclear Administrative Procedures Manual provides '

for the use of temporary changes which are controlled in accordance Technical Specifications. Detail instructions for with -

implementation of temporary changes are provided.

QA monitors the conduct of selected post modification tests to f

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.

1 17.2.12 Control of Feasuring and Test Equipment Test equipment, instrumentation, and controls used to - monitor and I are measure activities affecting quality and personnel sgty identified, controlled, and calibrated at specific intervals by.

f cognizant- Nuclear Department personnel. 'Uritten procedures for meeting these requirements inciade provisions for:

1. Specifying calibration frequency ,

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2. Recording and maintaining calibration records

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17.2-36 Revision-4 <

HCGS-UFSAR Apri'l 11, 1992 )

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, 17.2.14 Inspection, Test, and Operating Status ,

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Nuclear Department procedures are required to specify the periodic  ;

tests and inspections required f'o r 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  ;

1 accordance with specified requirements. l

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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 control the application and removal of tags and are  ;

designed to prevent operation of valves and/or switches that could result in personnel hazard or equipment damage.

Valve and equipment status boards or logs are maintained to indicate-status, i

i 17.2.15 Nonconforming Materials, Parts, or Components-Organizations involved in material receipt, installation, test, design modification and other operating activities are responsible for identifying, and documenting nonconformances. Nonconforming ~

materials, where practical, are segregated to prevent insta11ation or use until proper approvals are obtained. Materials, parts. ev s or components that have failed in service are identified and,' where.

practient. segregated. Procedures control the application and removal of tags.

1 Documentation of the nonconformance includes a description of the nonconformance, review by SNSS/NSS for Limiting Condition for ,

Operation (LCO) applicability when appropriate and the disposition i and inspection or retest requirements, as appropriate. The l 1

responsible Engineer dispositions each nonconformance report.

Dispositions for repair-or "use-as-is a are required to be reviewed  ;

and approved by QA prior to implementation. Rework or~ repair of {

nonconforming material, parts, 17.2 HCCS-UFS AR . Revision 5 May 11, 1993

  • j i

or components is inspected-or retested.or both in accordance with f specified test and inspection requirements established by the  !

representative, based on. applicable responsible engineering requirements. QA shall verify the satisfactory completion of the disposition of nonconformances.  !

review QA and other organizations in the Nuclear Department e l

including adverse nonconformance reports for quality problems, reports to higher management,.

quality trends, and initiate identifying significant quality problems with recommendations for .

appropriate action. ,

L P

L 17.2.16 Corrective Action  ;

Organizations involved in activities covered by the QA program are  !

required to implement corrective action for deficiencies identified I

within their scope of activity. Noncompliances identified by QA are documented and controlled by issuance of an action request. QA reviews responses to action requests for adequacy and monitors these i action requests through periodic summary and status reports to management.

' Responses to action requests are based on the four elements of corrective action, which are:

" 1. Identification of cause of deficiency a ,

i

2. Action to correct deficiency and results achieved to date I i
3. Action taken or to be take,n to prevent recurrence j

Date when' full compliance was or will be achieved.

4  !

=

For significant conditions a'dverse to quality not identified by QA, l

such as LERs and NRC/INP0/CMAP findings, QA is involved in the review of such conditions and provides oversight to assure timely 17.2-u0 Revision 5 HCGS-UFSAR May 11, 1993

'a-  !

t f

follow-up and close out through monitoring, auditing, and commitment I

verification. i Items 3 and 4 are optional for. noncompliances that do not have a ,

significant effect on the QA program.

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

The station general manager is responsible for assuring that ,

conditions adverse to quality are promptly -identified and corrected j station operation, maintenance,  ;

for all activities involving ,

testing, refueling, and modification. ,

t Administrative procedures that govern station activities covered by 1 the QA program provide for the timely discovery and correction of nonconformances. This includes receipt of defective material, failure or malfunction of equipment, deficiencies or deviations of l I

4 equipment from design performance , and deviations from' procedures .

In cases of significant conditions adverse to quality, . the cause of- i the condition is determined, and measures are . established to preclude recurrence. Such events, together with corrective action taken, are documented and reported as described in Section 17.2;15. j Corrective action is initiated by the responsible department head.

QA closely monitors station conditions requiring coriective action.

cr . .

Repetitive deficiencies, procedure or process violations at- the station that are not classified as operational. incidents'.or reportable occurrences, or nonconformances under the QA program, are This j documented by QA via the issuance of an action request.

request provides a formal administrative' vehicle to alert management-of conditions adverse to quality that require corrective action. .

.i i

17.2-41 l HCGS-UFS AR

. Revision 4 April:ll, 1992

~1

, s,- e --.m wa. a-a. ..a. .~m u .a. =- . 4 ,_. m ..p . - - + -- e 4

17.2.17 Quality Assurance Records Records necessary to demonstrate .that activities important to have been performed in accordance with applicable quality requirements are identified and maintained in accordance with f Regulatory Guide 1.88, as noted in Section 17.2.2. Documents shall  ;

3 be considered valid records only if stamped or initialed or signed  ;

i and dated by authorized personnel or otherwise authenticated.

Record types, as a minimum, comply with applicable technical specification requirements and include operating logs, maintenance and modification procedures and related inspection results and ,

reportable occurrences.

Design and other QA records are replicated via microform and stored in record facilities at the generating station and at offsite ,

i locations.

. i The Nuclear Department is responsibic for the permanent storage of i station records. The retention period for records; permanent and methods of control, identification, and -

l storage location; retrieval are specified by administrative procedure. Individual {

j station department heads are responsible for submitting applicable f

department records to the designated location for retention.

17.2.18 Audits e . '

Audits of PSE6G and supplier organizations that _. implement the QA -l program are perfctmed by QA to verify compliance with the applicable

.[

portions of the program through personnel interview and review of t applicable documents and records, as required. An annual audit  ;

sched.ule is prepared, identifying audits to be performed and their

(

frequency..

Audits are conducted by audit teams comprised of a certified lead q auditor and certified auditors, and technical specialists (when ,

deemed necessary).

l 17.2-42 _,

llCCS-UFSAR Revision 5 May 11, 1993

. _ __ _ _ _.

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