ML20207F469

Change 5 to Rev 20 of (Nuqap) Topical Rept

ML20207F469
Person / Time
Site:	Millstone
Issue date:	03/03/1999
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
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NUDOCS 9903110253
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l l February 25,1999 010-PRG-99 l

TO: Northeast Utilities Quality Assurance Program Topical Report Controlled '

Copyholders O \

vE FROM: - S. Orefice  !

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SUBJECT:

NUQAP Topical Report Revision 20, Change 05 i

Enclosed is civ 7e number 05 to NUQAP revision 20. Please replace the entire contents of i existing sect! 1.0,3.0 and new Appendix F with the enclosed sections.  !

Change 05 cn, tges are in bold anditalics with a revision bar in the right margin. The footer of the affected section willinclude a reference to change 05 Insert the summary of changes document in the front of your manual.

If you have any questions, contact R. Fletcher at X4350 Attachments; 1.. Summary of changes incorporated as part of revision 20, change 05.

Enclosure:

Change 05 to the Northeast Utilities Quality Assurance program Topical Report revision 20.

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Summary of Changes to NUQAP Rev. 20 incorporated as Change 05

' Summary Description of Channes Reference Section 1.0, para.1.4 After reference to Technician Specifications add the words" or Appendix F". Change Request 99-02 1.0, para After reference to Technicie.n Specifications add the words" or Appendix F". Change Request 1.4.2 99-02 1.0, para After reference to Technician Specifications add the words" or Appendix F". Change Request 1.4.2.1.2 99-02 3.0, para. After reference to Technician Specifications add the words" or Appendix F" Change Request 3.2.2 99-02 Appendix Add new appendix F Change Request 99-02 Table of contents Change Request 99-02 Page I of1

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. TABLE OF CONTENTS NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM (NUQAP)

TOPICAL REPORT- MILLSTONE POWER STATION I O -

Table of Contents l

l Abstract Policy Statement Introduction Quality Assurance Program QAP 1.0 Organization QAP 2.0 Quality Assurance Program j QAP 3.0 Design Control  !

QAP 4.0 Procurement DocumentControl I QAP 5.0 Procedures, Instructions and Drawings  !

QAP 6.0 Document Control QAP 7.0 Control of Purchased Material, Equipment and Services QAP 8.0 Identification and Control of Materials, Parts and )

Components QAP 9.0 Controlof Special Processes QAP10.0 Inspection QAP11.0 Test Control QAP12.0 Control of Measuring and Testing Equipment QAP13.0 Handling, Storage, and Shipping i QAP14.0 inspection, Test, and Operating Status QAP15.0 Nonconforming Materials, Parts, Components, or Services  !

QAP16.0 CorrectiveAction QAP17.0 Quality Assurance Records QAP18.0 Audits Appendices A. Category I Structures, Systems, and Components B. Qualification and Experience Requirements, Recovery Officer-NuclearOversight C. Regulatory Guide and ANSI /IEEE Standard Commitments D. Glossaryof Quality AssuranceTerms E. Program Exceptions F AdministrativeControls l QAP Table of Contents Rev.: 20 Change 05 Date: 3/3/99 Page 1 of 1 l l

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.1.0 ORGANIZATION 1.1 -INTRODUCTION l

The Chairman, President and Chief Executive Officer of Northeast Utilities (NU) has the  !

ultimate responsibility for the NU Nuclear Program. While retaining full responsibility and {

overall authority, the Chairman has delegated the necessary authority and responsibility l

.for all nuclear operations to the President and Chief Executive Officer - NU Nuclear i Group. _ The NU Nuclear Group includes the. Northeast Utilities Service Company {

(NUSCO) which provides support services to NU's nuclear plants and the Northeast

{

Nuclear Energy Company (NNECO) which operates Millstone Power Station Nuclear ,

Units 1,2, and 3. The President and Chief Executive Officer- NU Nuclear Group is also  !

'the President of NUSCO and the President and Chief Executive Officer of NNECO. i 1.2 GENERAL- i 1.' 2.1 The President and Chief Executive Officer - NU Nuclear Group directs i specified nuclear : re{0ted activities within NU and has the ultimate j responsibility for the establishment and execution of the NU Quality Assurance Program (NUQAP) for the Millstone Power Station. The President and CEO, is. overall responsible for engineering, construction, operation, maintenance, modification, and quality assurance for the Station.

1.2.1.1 Responsibilities-of the President and Chief Executive Officer

' relating to the Quality Assurance Program are described in this QA Program Topical ' Report and applicable NUSCO/NNECO procedures. The President and CEO'has contact with' quality

- assurance activities through meetings with the Recovery Officer -

Nuclear. Oversight, the receipt of various documents such as:

periodic progress ' reports, Nuclear Safety Assessment Board

- meeting notes, other reports, and audits- related to the nuclear

. program and nuclear plant operations acilvities at Millsto'ne Power Station.

1.2.1.2 The President and CEO is responsible to assess the scope, status,  !

implementation, and effectiveness of the Millstone Power Station NUQAP.' To meet this responsibility, the President and CEO i appoints a qualified team of 2 individuals to perform an annual  !

Management Quality Assurance Review. This Management Quality-

- Assurance Review is:

I a) A systematic evaluation;.

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b) Preplanned toward the objective of determining the adequacy j of the NUQAP and its compliance with Appendix B to .10 CFR l 50 and other regulatory requirements; '

OAP-1,0 Rev.: 20 Change 05 ,

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c) Capable of identifying, communicating, and tracking any l

, required corrective action; f i

d) The team is made up of individuals knowledgeable in quality  !

assurance, _q uality activities, auditing, management J responsibilities, and the Millstone ; Power Station NUQAP  ;

Topical Report. i 1.2.1.3 The President and CEO resolves all disputes related . to the  ;

. implementation of this NUQAP for which resolution is not achieved at lower levels within the nuclear organization. l

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1.3 RESPONSIBILITIES l 1.3.1 Overall responsibility for the'NUQAP is assigned to the Vice President -  :

Nuclear Oversight & Regulatory Affairs (VP NORA) who reports to the Chief-Nuclear Officer. These responsibilities include: direction 'of the Quality Assurance Program; implementation of policies,' plans, requirements, procedures, and audits; verification to assure compliance with 10'CFR 50 Appendix B and other regulatory requirements; and verification of the implementation ~ of the Millstone Power Station NUCAP Topical Report I requirements.  !

O 1.3.2 The head of each NUSCO/NNECO Department performing quality activities is responsible for

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a. Administering those activities within their organization which are required by this NUQAP;

b. Ensuring implementation of the Quality Assurance Program;

c. Establishing and clearly defining the duties and responsibilities of personnel within their organization who perform quality activities;

d. Planning, selecting, and training personnel to meet the requirements of the NUQAP Topical Report;

e. Performing and coordinating quality activities within their department and

interfacing with the Nuclear Oversight Department.

1.3.3 ' Each individual performing or verifying activities affecting quality is responsible to conduct those activities in accordance with the requirements of this NUQAP

.and implementing procedures; These individuals shall have direct access to such levels of management as may be necessary to perform this function. j O QAP-1.0 Rev.: 2J Change 05 3/389 l Page 2 of18

_7 O 1.3.4 The responsibility, authority, and organizational relationship for performing quality activities within each organization is established and delineated in the NUSCO/NNECO organizational charts, policy statements, and written job or.

functional descriptions.

1.3.5' Vendors may be . delegated the execution of quality assurance functions; however, NU shall retain responsibility for this Quality Assurance Program.

1.4 PARTICIPATING GROUPS - MILLSTONE POWER STATION (Refer to Fiaure 1.0)

The President and Chief Executive Officer - NU Nuclear Group, reporting to the NU

' Chairman,L President, and Chief Executive Officer, is overall responsible for the development and implementationof this NUQAP. The Nuclear Safety Assessment Board reports to the President and Chief Executive Officer in compliance with Millstone Power Station nuclear unit Technical Specdications or Appendix F. . The President and Chief l Executive Officer has delegated the necessary authority and has assigned responsibility for development and implementation of this NUQAP for Millstone Power Station to the: l l

e . Vice President NORA & Recovery Officer - Nuclear Oversight, e Senior Vice President and Chief Nuclear Officer - Millstone Power Station, e Director- Special Projects .

. Vice President - Human Services.

1.4.1 The VP NORA & Recovery Officer - is responsible for the preparation and issuance of this NUQAP Topical Report and verification of the implementation of its requirements and compliance with 10 CFR 50, Appendix B and other regulatory requirements by the applicable ;NUSCO/NNECO Department. I Verification is performed through a planned program of audits, surveillances, -l and inspections by Nuclear Oversight Sections. The VP NORA & Recovery l Officer provides management with objective evidence of the performance of  !

. quality activities independent of the individual or group directly responsible for j performing the specific activity.  !

The VP NORA'.& _ Recovery Officer has the authority and organizational  !

- freedom to verify all activities affecting quality. This is performed independent  !

of undue influences and responsibilities for schedules and costs. The VP  !

NORA & Recovg Officer has the responsibility- and authority to stop l unsatisfactory - work and control further processing or installation of  ;

nonconforming _ materials; The authority to stop work is assigned to Nuclear j Oversight Department personnel and delineated in a NNECO Procedure. The VP NORA '& Recovery Officer also has the responsibility and authority to identify quality problems, to recommend or provide solutions, and to verify their implementation.-

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l The VP NORA & Recovery Officer - Nuclear Oversight is also responsible for t the Independent Safety Engineering,' Operating Experience Programs, and the Independent Review Team.  !

1.4.2 ' The Senior Vice President and Chief Nuclear Officer - Millstone Power Station  !

has the overall responsibility for.the implementation of this NUQAP at the >

L Millstone Station site and is responsible _ for overall operation of the Station.  !

The Millstone Site. Operations Review' Committee (SORC) reports to the  ;

Senior Vice President and Chief Nuclear Officer in compliance with Millstone i

Power Station ~ nuclear unit Technical Specifications or Appendix F. The l l Senior Vice President (Refer to Figure ~ 1.0) has delegated the necessary  !

authority and has assigned responsibility for these activities to the:- l

. Vice President - Operations, . I e Vice President - Nuclear Work Services,  ;

e- Vice President - Engineering Services

. Vice President - Nuclear Oversight & Regulatory Affairs.

1.4.2.1 The Vice President - Operations is responsible for establishing common policies and standards pertaining to the operating units,

' the safe operation of Millstone Units 2 and 3, and implementation .

- of this NUQAP. The Vice president of Operations has delegated 4 the necessary authority and has assigned responsibility for the Unit ,

activities to the: D e Unit Director - MP 2

• Unit Director- MP 3 1.4.2.1.1 The Unit Director' - MP 2 .(Recovery Officer) is

. responsible for the day-to-day direction ' and administration of the Unit Operations, Maintenance, -

Modification, Work Planning, and Radiological Controls activities. The Plant Operations Review Committee (PORC) reports to the Director - Unit Operations in compliance with Technical Specifications or Appendix F. The Manager of Radiation Protection reports to the Director of Unit Operations to . provide sufficient organizational freedom and independence from operating pressures'.as_ required by the unit technical specifications. The Director has delegated the necessary authority and assigned responsibility for Unit activities to the: (Refer to Figure 1.1) e Manager Radiation Protectica e Asst. Unit Director Nuclear Safety

. Asst. Unit Director O&M QAP-1.0 Rev.:20 Change 05 3/389 l Page 4 of 18 y ., , , . , , - -

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1.4.2.1.2 The Unit Dire'c tor- MP 3 is responsible for the day-to-O day direction and administration of the Unit Operations, Maintenance, Modification, Work Planning, and Radiological Controls activities. The Plant Operations Review Committee (PORC) reports to the Director - Unit Operations in compliance with Technical Specifications or Appendix F. The Manager of Radiation Protection l reports to the Director of Unit Operations to provide sufficient organizational freedom and independence from operating pressures as required by the unit technical specifications. The Director has delegated the necessary authority and assigned responsibility for Unit activities to the: ( Refer to Figure 1.2 )

. Asst. Unit Director Nuclear Safety

. Asst. Unit Director O&M e Manager Radiation Protection 1.4.2.2 The Vice President - Nuclear Work Services has responsibility for implementation of this NUQAP in providing work related services in support of the Station. The Vice President (Refer to Figure 1.3) has delegated the necessary authority and has assigned responsibility for these activities to the:

O e e

Director - Nuclear Services, Director -Information Technology, e Director - Nuclear Materials and Document Management,

. - Director - General Services, e Manager - Nuclear Contracts Administration

. Director- Unit Operations MP1

• Director- Decommissioning MP1 1.4.2.2.1 The Director - Nuclear Services is responsible for the day-to-day direction and administration of Construction Support, Waste Management, Health Physics Support, Facilities Maintenance, and Testing Services for plant operations. The Director is also responsible for project management for the Station nuclear units.

1.4.2.2.2 The Director - Information Technology is responsible for the day-to-day direction and administration of Computer Services Support.

CAP-1.0 Rev,: 20 Change 05 3G99 l Page 5 of 18

1.4.2.2.3 The Director - Nuclear Materials and Document O Management is responsible for the day-to-day direction V and administration of Millstone Power Station Stores, Procurement Engineering, and Documents / Records control activities. The Director is also responsible for the approval and oversight of vendors that provide quality related material and services including source and receipt inspection.

1.4.2.2.4 The Director - General Services is responsible for the day-to-day direction and administration of Station Security, Medical, Safety, and Fire Protection activities.

1.4.2.2.5 The Manager - Nuclear Contracts Administration is responsible for setting policy and for the day-to-day.

direction and administration of the Nuclear Contract Group.

1.4.2.2.6 The Director - Unit Operations MP1 is responsible for the day to day direction and administration of the Unit Operations, Maintenance, Modification, Work Planning, and Radiological Controis activities. The Plant Operations Review Committee (PORC) reports to the Director - Unit Operations in compliance with Technical O Specifications. The Manager of Health Physics reports V to the Director of Unit Operations to provide sufficient l organizational freedom and independence from )

operating pressures as required by the Unit Technical  !

Specifications. The Director has delegated the necessary authority and assigned responsibility for the Unit activities to the: (Refer to Figure.1.4)

. Manager-Operations l

. Manager-Work Management l

. Manager- Support Services e hhanager - Chemistry  !

. Manager - Health Physics l 1.4.2.2.7 The Director - Decommissioning is responsible for the overall direction of decommissioning and  ;

dismantling activities for Millstone nuclear station .

Unit 1, including development of the decommissioning plan, contract development and ]

oversight of contractors. '

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QAP-1.0 Rev.: 20 Change 05 3/3/99 l Page 6 of 18

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1.4.2.3 Vice president - Engineering Services has responsibility for

-( impiementation of this NUQAP in providing work related l

engineering services in support of the station. The Vice president (Refer to Figure.1.5) has delegated the necessary authority and has assigned responsibility for these activities to the:

. Director - Nuclear Engineering

. Director - Unit 3 Engineering

• Director- Engineering MP2 e Manager - Engineering MP1 1.4.2.3.1 The Director - Nuclear Engineering is responsible for the day-to-day direction and administration of Nuclear

- Fuels, Radiological Engineering and Assessment, Redwaste Engineering, Probabilistic Risk Assessment, Safety Analysis activities, and the Quality Software program.

1.4.2.3.2 The Director - Engineering Programs is responsible for the day-to-day direction and administration of Engineering Programs and Standards, the Engineering Assurance Program, and the administration of the Design and Configuration Control Program and the Design Control Manual for the Station nuclear units.

1,4.2.3.3 The Director - Engineering is responsible for the day-to-day direction and admirdstration of Unit Design Engineering, Technical Support, System Readiness, and for maintenance of the Unit Design Nsis in" accordance with the Unit Licensing basis.

1.4.2.3.4 The Manager - Engineering MP1 is responsible for the day-to-day direction and administration of the Unit Design Engineering, Technical Support, System Readiness, and maintenance of the Unit design basis in accordance with the Unit licensing basis.

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t 1.4.2.4 The.Vice President - Nuclear Oversight & Regulatory Affairs

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(Nuclear Group - Millstone Station ) is responsible for the effective  ;

performance of all departments within the Nuclear Cversight and '

Regulatory Affairs functions. Acts as advisor to Chief Executive Officer and Chief Nuclear Officer on items related to nuclear quality and safety for Millstone Station. The V P - NORA (Refer to Figure 1.6) has delegated the necessary authority and responsibility for these activities to the: .

• Director - Nuclear Oversight

. Recovery Officer Technical Services

. Manager- Regulatory Affairs  :

1.4.2.4.1 Director - Nuclear Oversight is responsible for the effective performance of activites related to Quality Control lospections, Quality Assurance assessments  ;

including auditing, and Nuclesr Safety Engineering for  ;

Millstone Station. The Directo has delegated the '

necessary authority and responsibility for theses activities to the:

e Manager- Nuclear Safety Engineenng I e' Manager- Operations & Maintenance Assessment e Manager- Engineering & Site Programs Assessment e Manager- Quality Control 1.4.2.4.1.1' The mnager- Nuclear Safety ,

F.ngineering is responsible for the independent Safety Engineering,

~ Operating Experience review, and Human Factors review functions.

1.4.2.4.1.2 The Manager- Operations &

Maintenance Assessment is responsible for oversight of operations and maintenance activities including 10CFR50, Appendix B audits and other assessments of quality related activities.

1.4.2.4.1.3 The Manager - Engineering & Site Programs Assessment is res, nsible for oversight of engineering and other site program activities including 10CFR50, Appendix B audits and other -

assessments of quality related activities.

1.4.2.4.1.4 The Manager of Quality Controlis

p. responsible for activities associated with d QAP-1.0 Rev.:20 Change 05 3/3/99 l Page 8 of 18

j the field inspection and verification of O, physical work activites including modifications pertaining to safety related or augmented quality structures, systems, or components.

l 1.4.2.4.2 Manager - Regulatory Affairs is responsible for establishing and overseeing the implementation of nuclear regulatory policies', . stanrNds, processes, programs and procedures for site-wide initiatives .

1.4.2.4.3 The Recovery Officer - . Technical Services is responsible for Engineering and Technical Support Services at Millstone Station. The Recovery Officer is-responsible for implementation of the Corrective Action,_

Configuration Management. The. Recovery Officer is also responsible for Regulatory Affairs interface. The Recovery Officer (refer to Figure 1.6b has delegated the necessary authority and has assigned responsibility for these activities to the:

• Director- Corrective Actions e Manager-Independent Review Team

, .- Director- Regulatory Affairs 1.4.2.4.3.1 The Director - Corrective Actions is responsible for the development and maintenance of the Corrective Action ,

Program implemented for the Station 1 including reporting of program j performance indicators, analysis and [

identification of trends, and identification i of necessary preemptive corrective l action as required.

1.4.2.4.3.2 The Recovery Director - MP2 Regulatory Affairs is responsible for the riverall '

direction and administration of Regulatory Affairs and the Nuclear Regulatory Program activities, for the day-to-day direction and administration of '  !

the Unit Regulatory Compliance activties  !

and- ~ the Station Administrative Procedures Group.

1.4.2.4.3.3- The Manager-Independent Review QAP-1.0 Rev.: 20 Change 05 -

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Team is responsible for conducting in "O depth and critical reviews of selected U topics and events of critical importance to nuclear safety and/or organizational success.

~1.4.3. ' The Director - Special Projects is responsible for the day-to-day direction and .

- administration of Nuclear Operations. Support Services anu the performance

of specital projects in support of nuclear operations.

1.4.4 The Vice President .- Human Services has responsibility for the Employee Concerns and Nuclear Training Programs, and implementation of this NUQAP in ' providing - Emergency Planning and Support Services to the-Millstone Power Station. The. Vice President .(refer to Figure 1.5) has delegated the necessary authority and has assigned responsibility for these activities to the: (Referto Figure.1.7) e Director - Nuclear Training Services, e Director- Emergency Planning.

. Director- Employee Concems 1.4.4.1- The Director - Nuclear Training Services is responsible for the- day-to-day ~ direction and administration of Nuclear Training and related support services. The O Manager of Operator Training reports directly to the Director of Nuclear Training to provide sufficient organizational freedom and eindependence - from operating pressures as required by the unit technical i

specifications.

1.4.4.2 The Director - Emergency Planning is responsible for the development and maintenance iof the on site Radiological Emergency Plan and the development and coordination of required off site Radiological Emergency Response Plans.

1.4,4.3 Director - Employee Concems Program is responsible for the day-to-day direction and administration of the Employee Concerns Program. The Director assures that nuclear safety concerns receive appropriate management attention and concerns are addressed in a timely manner.

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Organizational Relationships '

• Note: The Vice President Nuclear Oversight of Personnel Having Quality Chairman, President and Regulatory Affairs (NORA)is a dual Functions for Millstone & CEO NU Position with Recovery Officer N ; lear Oversight.

Power Station President & Chief Employee Concerns uclear Safety Oversight Panel (ECOP)

Executive Officer of Nuclear Group Assessment Board (NSAB)

(

Director Special ite Perations SenioNe PmsMent

• Recoven Vice President p Review Committee & Chief Nuclear Officer Nuclear Officer Millstone Overs:ght Human Services (SORC)

. Vice President * ** '" * ** "

Vice President Nuclear Oversight & "" ' " U '"'"I Operations Regulatory Affairs Services Servit.es Director Director Unit 2 IJnit 3 QAP 1.0 Figure 1.0 Rev.: 20 Change 05  ;

Date: 3/3/99 l Page 11 of 18

') . .o O rg a n iza tio n a l R e la tio n s h ip s o f P e rs o n n e l H a vin g Q u a lity F u n c tio n s fo r M ills to n e P ow e r S ta tio n - U n it 2 U nit Directo r M ills to n e U nit 2 PORC I

M a n a g e r R a dia tio n A s s t. U n it D ire c to r A s s t. U nit  ;

'P ro te c tio n N u clea r S afety Director O & M - -

t I

M anager Manager o rre c tiv e M a ln te n a n c e A c tio n

! M anager of P ojects Manager M anager _W o rk - .

P O R C - P la n t O p e ra tio n s N u clea r S afety Pla n nin g & f R e vie w C o m m itte e O u ta g e s O & M - O p e ra tio n & M ain te n a n c e  ;

I M anager M a na ger t& C l l

P ro c e d u res i  ;

M anager M anager O p e ra tio n s t C h e m Is try . [

QAP 1.0  !

Figure 1.1 Rev.: 20 Change 05 Date: 3/389 l l

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Organizational Relationships of ~

Personnel Having Quality Functions for Millstone Power Station - Unit 3 Vice President Operations Unit Director Unit 3 PORC Asst. Unit Director Asst. Unit Director Manager Radiation Nuclear Safety O&M Protection Manager Nuclear  ;

Safety i Manager Work Manager Operations Planning & Outage Management

- Manager Corrective Action Manager Manager Chemistry Maintenance /ISC Manager Procedures PORC - Plant Operations Review Committee O&M -Operations & Maintenance IRC -Instrument & Controls QAP 1.0

. Figure 1.2 Rev.: 20 Change 05 Date: 3/3/99 l Page 13 of 18

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Organizational Relationships of Personnel Having Quality Functions Vice President Nuclear for Millstone Power Station Work Services ,

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Director Nuclear l .l I

Materials & Director General Director Information Director Nuclear Mgu - hh Document Services Technology Services Contracts Management Administration j

i l l I Manager Nuclear - Manager Manager Millstone Manager Facilities Manager Station Document Services Security Computer Services -

Engineering -~

Projects l Manager Industrial Manager Process Procurement Team Safety Team Computers & _

Manager Genention Manager Waste

• Unit 1 Leader Simulators Test Services ,

L Manager i Manager Pro)sct manager Manager Nuclear Manager Health Procurement Team -

Fire Protection Software QA Construction - ~ '

Physics Support Unit 2 anager Su ervisor Station Director MP1 Procurement Tea m Procurement Decommissioning Director OPS General Supervisor MPI Warehouse Services f i

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QAP 1.0  ;

Figure 1.3 Rev.: 20 Change 05 '

Date: 3/3/99 l 7 Page 14 Of 18

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Organizational Relationships of -

Personnel Having Quality Functions Vice President

. for Millstone Power Station Unit i Nuclear Work Services Director Unit l Operations PORC MP1 Asst. Operations Manager Work Manager Support Manager Health  !

Manager Management Services Manager Chemistry p ,, ,

PORC - Plant Operations Review Committee QAP 1.0 Figure 1.4 Rev.: 20 Change 05 Date: 3/3/99 Page 15 of 18

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Vice President Engineering Services Director Diractor Director Director Manager Nuclear Engineering Engineering Unit 3 Engineering Engineering Programs MP2 Engineering MP1 QAP 1.0 Figure 1.5 Rev.: 20 Change 05 Date: 3/3/99 Page 16 of 18

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Nuclear Oversight and Vice President Nuclear Oversight Regulatory Affairs O rganization & Regulatory Affairs I RONO j fo r M ills to n e S ta tio n .

• Recovery Officer Director N uclear Manager O ve rsig ht Regulatory Affairs Technical >

S e rvic e s u

l l l M anager Nuclear ' Supervisor M P1 Director  ;

- Safety - _ Regulatory C o rre c tiv e -  !

E n gin ee rin g C om plia n c e A c tio n s .

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f i "*"*88' Operations &

Supervisor M P3 ' Director a1nt R e g ula to ry R e g ula to ry

,,, s C o m plia n ce A ffairs nt S u p e rvis o r Manager Manager _ R e g ula to ry Independent Engineering & Site }

A{rgirs Review Team P ro g ra m s Assessment fI S u p e rvis o r. R e c o va ry  ;

- Licensing Director MP2  ?

t M ana ge r Q uality Support R e g ula to ry 1 S e rvic e s - ,

c o n trol c om plia n c e t

L QAP 1.0 i Figure 1.6 -

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Page 17 of 18

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Organizational Relationships of Personnel Having Quality Functions Vice President

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for Millstone Power Station Human Services Y

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Director Employee Director Nuclear Director Emergency

• Concerns Training Services Planning ->

I Manager Manager Technical Manager Operator Manager Emergency inv tions --

Training Training Planning d

Manager Engineering Manager Assessment Support & Director Human Group Professional Resources Development ECP - Employee Concerns Program ,

Project Manager SCWE - Safety Conscious SCWE Work Enviroment Manager Process .

Computers & ,

Simulators r

QAP 1.0 Figure 1.7 i Rev.: 20 Change 05 ,

Date: 3/3/99 '

Page 18 of 18

__________.....____..._..._.____.q n 3.0 QEc!GN CONTROL -

3.1 GENERAL REQUIREMENTS This NUQAP provides measures to assure that the applicable design requirements, such as design bases, regulatory. requirements, codes, I technical standards and quality standards, are identified in design l- documents which are reviewed, approved and controlled in accordance with procedures. Such measures include review for suitability of application of materials, equipment, parts and processes that are essential to the functions of quality structures, systems, and components. Changes to, and deviations from specified requirements are identified, documented and controlled.

The Director / Manager - Engineering for each nuclear unit is responsible for controlling design work, administering design control activities (including j design interface) and design modifications for quality structures, systems,  ;

and components.  !

The responsibility for administration of the design control program for the Millstone Station nuclear power plants rests with Engineering Programs. ,

The <tvision of responsibilities and jurisdictional boundaries for design l con ret program implementation are set forth in NUSCO/NNECO O- procedures. Although other organizations may be delegated the task of establishing and executing the design control program or any part thereof, the Director / Manager - Engineering of each nuclear unit shall retain the j i . responsibility for program implementation for the unit. The applicable requirements of this NUQAP shall be imposed on other organizations delegated the task of establishing or executing the design control program in accordance with QAP 4.0, " Procurement Document Controf' and QAP 7.0, " Control of Purchased Material, Equipment and Services".  !

The interface controls, both intemal and extemal, for organizations r

- performing design wmk for quality structures, systems, and components are identified and implemented in accordance with procedures. This identification includes those organizations providing criteria, designs, specifications and technical direction.

Measures are applied to verify the adequacy of design. The extent of design verification is specified and documer.ted by the responsible organization. The individuals performing design verification should not (1) have immediate supervisory responsibility for the individual performing the design, (2) have specified a singular design approach, (3) have ruled l

. out certain design considerations, or (4) have established the design inputs c -.

i -,

QAP-3.0 Rev.: 20 Change 05 Date: 3/3/99 Page 1 of 6

• _ -, 4 -.- , -,

w e - - . - - , - - , , - , - - . . - , - , .-- . , , . < , . .

k i

e '

for the particular design aspect being verified. The independent design l

( .

verification should not dilute or replace the responsibilityof the supervisors i for the quality of work performed under their supervision. Where changes to previously verified designs have been made, design verifications are required for the change, including evaluation of the effects of those changes on the overall design. Design verification may be accomplished by testing. Tests to demonstrate adequacy under adverse design conditions shall comply with the requirements of QAP 11.0, " Test Control".

Design errors and deficiencies which adversely affect quality structures, j systems, arid components in the design process are documented and i appropriate corrective action is taken. These design errors and deficiencies are documented in accordance with design change procedures or as defined in QAP 15.0, " Nonconforming Material, Parts, Components, i or Services" and/or QAP 16.0,

• Corrective Action".  !

)

3.2 IMPLEMENTATION j i

The Director / Manager - Engineering of each unit is responsible for the

. design, design review. engineering approval of design changes, design i evaluation and design control for the unit except that Nuclear Engineering performs design / design changes in support of tne reactor core reload. The function may be delegated to other organizationsto perform the design, or ,

any part thereof, but the responsibility for overall design and final '

engineering decisions and design control of quality structures, systems, O and components related to the nuclear unit is the responsibility of the unit's Director / Manager- Engineering. ,

Nuclear Oversight performs audits, surveillances, and inspections, as i appropriates to verify that NUSCO/NNECO departments are effectively )

complying with this NUQAP and procedural requirements for design control. Additionally, audits, surveillance's and inspections are performed, as appropnate, to verify that vendors are effectively complying with their quality assurance program requirements for design control.

3.2.1 DESIGN PROCESS Design control measures are applied to design analyses, such as, reactor physics, stress, thermal, hydraulic, nuclear radiation, accident and seismic analyses; compatibility of materials; accessibility for in-service inspection, maintenance, and repair, i and delineation of acceptance criteria for inspections and test.  ;

Measures established to control design documents are described i in QAP 6.0, " Document Control".

Program procedures and instructions define the method of implementing design control measures. These measures require LO QAP-3.0 Rev.:20 Change 05 Date:3/3/99 Page 2 of 6

I that applicable design requirements, such as, design bases,

.. regulatory requirements, codes and standards, are translated into specifications, drawings, procedures or instructions. Procedures and instructions further require that appropriate quality standards are specified and included in design documents. Materials, equipment, parts and processes, including standard "off the shelf" commercial or previously approved items essential to quality functions are selected and reviewed for suitability of application.

The basis for selection may include industry standards, material and prototype hardware testing programs, and design review.

i Procedures assure that a documented check is performed to i verify the accuracy and completeness of design drawings and {

specifications before release for procurement, fabrication or construction. Design drawings receive a documented check to verify dimensional accuracy.

I Design drawings and specifications issued for design changes are reviewed for completeness and accuracy before release to operations, in accordance with design control procedures.

Procedures describe the provisions to assure that design  ;

drawings and specific &tions are prepared, reviewed and approved j in accordance with NUSCO/NNECO requirements and that the j g documents contain the . necessary quality assurance i requirements, such as inspections and test requirements, acceptance requirements, and the extent of documenting inspection and test results.

3.2.2 DESIGN CHANGE CONTROL Procedures and instructions goveming design change comrol j during modifications to the Station nuclear plants, the control of discrepant or deficient design conditions, and the reporting of. j unsatisfactory performance provide for the identification of the ,

need for design changes and a documented method to control '

these changes. Design and specification changes are subject to ,

design control measures commensurate with those applied during '

the original design as amended by applicable design or licensing basis changes, j 1

An independent review and approval of design changes is l

, performed by the organization that conducted the original design  ;

reviews, unless such review is performed by NNECO or another  ;

I QAP-3.0 Rev.:20 Change 05 Date: 3/3/99 Page 3 of 6

E p qualified organization delegated by NNECO to perform this Q . function.

Proposed design change modifications are submitted to the appropriate nuclear units management for processing and review.

This review includes the Plant Operations Review Committee (PORC) / Site Operations Review Committee (SORC) as required by applicable procedures. PORC/SORC is advisor to the Senior Vice President and Chief Nuclear Officer and Unit Directors (Millstone Units 2 & 3)/ Unit Operations Director (Millstone Unit No.

1) on matters relating to nuclear safety. The composition, responsibilities, and authority of the SORC/PORC are defined in Section 6 of each nuclear unit Technical Specification or Appendix F.. If the change involves a quality structure, system or component, the change shall be reviewed by qualified engineering personnel for technical adequacy. Reviews of the safety evaluations associated with proposed design changes are performed by the Nuclear Safety Assessment Board (NSAB). The sequence of the NSAB review depends upon the determination of whether an. unreviewed safety question is involved (i.e., in accordance with ANSI N18.7, if a proposed change in the facility involves an unreviewed safety question then the NSAB review is conducted prior to submittal of the proposed change to the NRC g for review and the issuance of a license amendment for its Q implementation).

The combination of these independent reviews by the PORC/SORC and NSAB are performed to assure that:

a. the adequacy of the proposed change is substantiated;

b. unreviewed safety questions are properly identified and handled per 10 CFR 50.59-

c. nuclear safety requirements have been addressed. j Errors and deficiencies in design, including the design process, that could adversely affect quality structures, systems, and components are documented and corrective action is taken in accordance with QAP 15.0,

• Nonconforming Materials, Parts, Components, or Services" and/or QAP 16.0, " Corrective Action".

O QAP40 Rev.: 20 C.'nge 05 Date: 3/3/99 Page 4 of 6

l l

I I

Notification of design changes are transmitted to responsible plant l personnel prior to implementation and as part of the design l change package close out. Procedures describe this notification j which assures that personnel are made aware of design change modifications which may affect the performance of their duties.

3.2.3 DESIGN INTERFACE CONTROL l Procedures and instructions identify design interface controls and j the resolution of design interface questions during modifications to !

the station nuclear power plants. l 3.2.4 INDEPENDENT DESIGN VERIFICATION Original designs and design modifications are reviewed for adequacy and the sign-off performed by a person other than the originator of the design. The originator's supervisor may perform l this independent review only if the supervisor: (1) did not specify a singular design approach, (2) did not establish the design inputs or rule out certain design considerations, (3)is the only individual in the orgarization competent to perform the review. Where the supervisor performs the design review, the next level of management shall fulfill the supervisor's responsibilities. Design verification is documented in accordance with procedures or instructions. Simplified calculations or computer programs may be utilized as attemate means of design verification. When design verification is performed by testing, the tests are performed using procedures, which specify the authority and responsibility of design verification personnel. Responsibility for design adequacy and evaluation is retained by the Director / Manager - Engineering of each unit. l Design verification (if other than by qualification testing) is normally completed prior to release for procurement . fabrication, and construction, or release to another organization for use in

. other design activities. For those cases where design verification cannot be completed prior to release for procurement, fabrication, and construction, procedures assure that design verification is completed prior to' the point when the installation is declared operational.

O QAP-3.0 Rev.: 20 Change 05 Date: 3/3/99 Pago 5 of 6 c

y o

Procedures describe the requirements which assure the following

. - when testing is considered as an alternate method of design verification:

a. Specifications or procedures provide _ criteria that specify when verificationshould be by test.

b. ~ Prototype, component or feature testing is performed as

- early as possible prior to installation of plant equipment, or prior to the point when the installation is declared operational.' I

c. Verification by test performed under conditions that simulate the most adverse conditions as determined by analysis.

. Particular emphasis is placed on assuring that: designs are in conformance with applicable codes, and on selecting the proper design. verification or checking method. Procedures and instructions provide the requirements and necessary controls for design verification. These controls include a review to assure that design characteristics can be controlled, verification that there is adequate accessibility for inspection or test,' and that inspection and test acceptance criteria are incorporated. Documentation of Iaviews is provided.

O Procedures include requirements which identify the responsibility of design verifiers, the areas and features to be verified, and the extent of the documentation.

Procedures assure that procedural control is established for design documents that reflect the commitments of the nuclear unit u FSAR. These procedural controls vary for design documents which receive formal design verification by several disciplines or '

organizations, and those' which can be reviewed'by a single i individual. The specific design documents and specialized reviews are determined and used as required by the design l changes and modifications.

Procedures are established to assure that verified - computer I programs are certified for a specific use.

I NNECO is responsible for assuring that the design documents generated by vendors for the Station nuclear power plants are technicaHy correct, approved, and maintained.

QAP-3.0 Rev.:20 Change 05 Date:3/3/99 page 6 of 6 y ., e a - r -w,- - , - - , + - ~ - - - - - - - - - - -r r,- e-

J APPENDIX F NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM (NUQAP)

t. -

TOPICAL REPORT - MILLSTONE POWER STATION ASMINISTRATIVE CONTROLS' NOTE: " Specification" numbers refer to the unit specific Technical Specification INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)- Unit 3 Only Function The ISEG shall include, as part of its function, examination of unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of unit design and operating exrerience information, including units of similar design, which may indicate areas for improving unit safety. The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving unit safety to appropriate station / corporation management.

Composition The ISEG shall be composed of at least four full-time personnel located on site to perform the functions described above for Millstone Unit 3.

Each person shall have either:

(1) A bachelor's degree in engineering or related science and at least 2 years of professional level experience in his field, at least 1 year of which experience shall be in the nuclear field, or, (2) At least 10 years of professional level experience in his field, at least 5 years of which experience shall be in the nuclear field.

A minimum of 50% of these personnel shall have the qualifications specified in (1) above.

Responsibilities The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification

• that these activities are O

QAP - Appendix F REV.: 20, Change 05 DATE: 03/03/99 PAGE: 1 of 18

T performed correctly and that human errors are reduced as much as practical.  ;

Records Records of activities performed by the ISEG shall be' prepared and  ;

maintained, and quarterly reports of completed safety evaluations will be made to the Vice President-Nuclear Oversight.  ;

'Not responsit'e for sign-off function 1

REVIEW AND AUDIT Plant Operations Review Committee (PORC) - Unit 2 Only Function The PORC shall function to advise the Unit 2 Unit Director on all matters related to nuclear safety. )

l Composition -

The PORC shall be composed of nine to eleven members. Members shall collectively have experience and expertise in the following areas:  ;

Plant Operations-Engineering Reactor Engineering Maintenance instrumentation and Controls Health Physics '

Chemistry Work Planning Quality Assurance The minimum qualifications of PORC members shall be that all members have an academic degree. in an engineering or physical science field, or hold a management position, and have a minimum of five years technical experience

'in their respective field of expertise. The members of PORC shall be appointed in writing by the Unit 2 Unit Director. The Chairperson and alternate Chairperson of the PORC shall be drawn from the PORC members and be appointed in writing by the Unit 2 Unit Director.

O QAP - Appendix F REV.: 20, Change 05 DATE: 03/03/99 PAGE: 2 of 18

L 4

Alternates 1

L O ^ite m 1e m e - 8 er 8 ii 8 e o n eim1e e ie ~ <itim o 8 v 18 e r o a c c 8 i<ne< e e 1e serve-on a temporary basis; however, no more -than two alternates shall l

participate in PORC activities at any one time.

Meeting Frequency The PORC shall meet at least once per calendar month and'as convened by p the PORC Chairperson.

1 1'

Quorum l

A quorum of the PORC shall consist of the Chairperson, or Vice '

Chairperson, and four members including alternates.

. Responsibilities The PORC shall be responsible for:

i

a. Review of 1) all procedures, except common site procedures, required by Specification 6.8 and changes thereto, 2) all programs, i except common site programs, required by Specification 6.8 and changes thereto, 3) any other proposed procedures, programs, or j changes thereto as determined by the Unit 2 Unit Director to affect nuclear safety. . Procedures and programs required by Specification 6.8 that are designated for review and approval by the Station Qualified Reviewer Program do not require PORC review.

b. Review of all proposed tests and experiments that affect nuclear safety.

I

c. . Review of all proposed changes to Sections 1.0 - 5.0 of the -

. Technical Specifications.

d. Review of all proposed changes or modifications to plant i systems or. equipment that affect nuclear safety.

- e. Investigation of all. violations of the Technical Specifications and  ;

preparation and forwarding of a report covering evaluation and recommendations to - prevent recurrence to the Senior Vice President and CNO - Millstone and .to the Chairperson of the Nuclear Safety Assessment Board.

l V(3 4

QAP - Appendix F REV.: 20, Change 05 DATE: 03/03/99 PAGE:. 3 of 18

f. Review of'all REPORTABLE EVENTS.

q

-Q-

.g. Review of facility operations to detect potential safety hazards.

i 1

- h. Performance of special reviews and investig'ations and reports

~ thereon as requested . by - the Chairperson of the Nuclear _ Safety

l. Assessment Board.

l. i. Render determinations in writing if any item considered under (a) through (d) above, as appropriate and as provided by 10CFR50.59 or -10CFR50.92, constitutes an unreviewed safety _. question or i requires a significant hazards consideration determination. j p 1

j. Review of the fire protection program and implementing procedure.

' A0thority i

The PORC shall:

a.  ; Recommend to the Unit 2 Unit Director written approval or disapproval of items considered under Responsibilities (a) through (d) above.

O 'b. Provide immediate written notification to the Senior Vice I President and CNO C Millstone, Millstone Unit 2 Recovery Officer and the' Chairperson of the Nuclear Safety Assessment Board of disagreement between the PORC and the Unit 2 Unit Director:-

however,;the Unit 2 Unit Director shall have responsibility for  ;

resolution of such disagreements pursuant to Specification 6.1.1.

Records The PORC shall maintain written minutes of each meeting and copies

.shall be provided to the Senior Vice President and CNO C Millstone and

. Chairperson of the Nuclear Safety Assessment Board.

Plant Operations Review Committee (PORC) - Unit 3 Only Function The PORC shall function to advise the Unit 3 Unit Director on all matters related to nuclear safety; i; TO OAP - Appendix F REV.: 20, Change 05 DATE: 03/03/99 PAGE: 4 of 18

..- -. - . . - . - - . - - . . . . ~ - . . - - - - . - - - . - - . - . . . -

. Composition The PORC shall be composed of nine to eleven members. Members shall collectively have experience and expertise in the following areas:  !

Plant Operations i Engineering - l Reactor Engineering l Maintenance instrumentation and Contro!s Health Physics Chemistry.

Work Planning i Quality Assurance The minimum qualifications of PORC members sh'all be'that all members  ;

have an academic degree in an engineering or physical science field, or i hold a management position, and have a minimum of five years tech'nical j experience in their respective field of expertise. The members of PORC shall be appointed in writing by lthe.. Unit 3 Unit Director. The  ;

Chairperson and alternate Chairperson of the PORC shall be drawn from  !

the PORC ' members and -be appointed in writing by the Unit 3 Unit

. Director.- l

' Alternates All alternate members shall be- appointed in writing by the PORC _i Chairperson to serve on a temporary basis; however, no more than two  ;

alternates shall participate' as voting members in PORC activities at any ~ i one time. i Meeting Frequency  ;

The PORC shall meet at least once per calendar month and as convened by the PORC Chairperson.

~ Quorum "

The quorum of the PORC shall consist of the Chairperson or Vice

, Chairperson and four members including alternates.

O QAP - Appendix F REV.: ,20, Change 05 DATE: 03/03/99

.p PAGE: 5 of 18 w - ,, _. _ _ ---. ..

b Responsibilities The PORC shall be responsible for:

a. Review of: (1) all procedures, except common site procedures, required by Specification 6.8 .and changes thereto, 2) all programs, except common site. programs required by Specification 6.8 and changes thereto, and (3) any other proposed procedures, programs or changes thereto as determined by the Unit 3 Unit Director to affect nuclear s afety. Procedures and programs required by Specification 6.8 that are designated for review and approval by the Station Qualified Reviewer Program do not require PORC review. ]

)

b. Review of all proposed tests and experiments that affect nuclear safety,

c. Review of all proposed changes to Sections 1.0-5.0 of the Technical Specifications; j

d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety; j l

e. Investigation of all violations of the Technical Specifications, including the preparation and forwarding n of reports covering evaluation and recommendations to .

(d prevent recurrence, to the. Senior Vice President and CNO - Millstone, Vice President - Millstone Unit 3 and to the Chairperson of the Nuclear Safety Assessment Board;

f. Review of all REPORTABLE EVENTS;

g. Review of facility operations to detect potential safety hazards;

h. Performance of special reviews, investigations, or analyses and reports thereon as requested by ' the Chairperson of the Nuclear Safety Assessment Board or the Senior Vice' President and CNO - Millstone or Vice President - Millstone Unit 3; and

i. Render determinations in writing if any item considered under (a) through (d) above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92, constitutes an unreviewed safety question, or requires a significant hazards consideration determination,

j. Review of Unit Turbine Overspeed Protection Maintenance

[Y Q).

and Testing Program and revision thereto.

QAP - Appendix F REV.: 20, Change 05 DATE: 03/03/99 PAGE: 6 of 18

.m___

j k.1 Review of the Fire Protection Program and implementing

.The PORC shall: ,

a. Recommend to the Unit 3 Unit Director written. approval or

• l disapproval ~of items considered under Responsibilities a.

through d. above) and

b. Provide written notification to the Senior Vice President and

'CNO - Millstone,;Vice President - Millstone Unit 3 and the l

Chairperson of the Nuclear Safety Assessment Board of disagreement between the PORC and the Unit 3 Unit Director;

. however, the Unit 3 Unit Director shall have responsibility for.

resolution of . such. disagreements pursuant to Specification 6.1.1.

I Records The PORC shall maintain written minutes of each meeting and copies shall be provided to the Senior Vice President and CNO - Millstone and the Chairperson of the Nuclear Safety Assessment Board.

Site Operations Review Committee (SORC) - Units 2 and 3 Only l.O l

Function The SORC shall function to advise the Senior Vice President and CNO C Millstone on all matters related to nuclear safety of the entire Millstone Station l Site.

Composition The SORC shall be composed of the:

L Chairperson: Senior Vice President and CNO C Millstone L Member: Director, Unit Operations

!. - Member: Unit 2 Unit Director l Member: . Unit 3 Unit Director Member: Director, Nuclear Services -

Member: Manager,' General Services Member: Designated Member of Unit 1 PORC l Member: Designated Member of Unit 2 PORC l . Member: Designated Member of Unit 3 PORC

. Member:  : Designated Member of Nuclear Oversight The senior Unit Director / Director, Unit Operations in attendance shall be the

& Vice-Chairperson.

,=V t

QAP - Appendix F' REV.: 20, Change 05 DATE: 03/03/99 PAGE: 7_of 18 l: . . _ _ . - _ . . ~ . -. . . . - _ . . . _ , , . . .

m W

Alternates: - l

~

Alternate members shall be appointed in writing by the SORC Chairperson to serve on a temporary. basis;~ however, no 'more than two alternates shall participate in SORC activities at one time.

l Meeting Frequency 1The SORC shall meet at least once per six months and as convened by the ,

SORC Chairperson. i j

Quorum

. A quorum of the SORC shall consist of the Chairperson or Vice 4

Chairperson and five members including alternates. _

i

' Responsibilities 1'

The SORC shall be responsible for:

a. Review of 1) all common site procedures required by Specifi-cation 6.8 and changes thereto, 2) all common site programs, required by I Specification 6.8 and changes thereto, 3) any' other proposed procedures, programs, or changes thereto as determined by the s Senior Vice President and CNO C Millstone to affect site nuclear safety. Common site programs and . procedures required by Specification 6.8 that are . designated for review and approval by.

the Station Qualified Reviewer Program do no require SORC review. q

b. Review of all proposed changes to Section 6.0 " Administrative

Controls" of the Technical Specifications.  ;

c. Performance of special reviews and investigations and reports as L requested by the Chairperson of the Nuclear Safety Assessment Board. 1

_d. . Not used.

e. Not used, l

f. Review of all common site proposed tests and experiments that  ;

affect nuclear safety. -

g. Review of all common site proposed changes or modifications to systems or equipment that affect nuclear safety.

't QAP - Appendix F REV.: 20, Change 05 DATE: 03/03/99 PAGE: 8 of-18

h. Render determinations in writing or meeting minutes if any item considered under (a) through (g) above, as appropriate and as l provided by 10CFR50.59 or 10CFR50.92, constitutes an O. -

unreviewed safety question or requires a significant hazards consideration determination.

i. Review of the common site fire protection program and implementing procedures.

Authority l The SORC shall:

a. Recommend to the Senior Vice President and CNO - Millstone written approval or disapproval in meeting minutes of items considered under Responsibilities (a) through (g) above.  ;

1

b. Provide immediate written notification or meeting minutes to the  !

President and Chief Executive Officer (CEO) and the Chairperson of the Nuclear Safety Assessment Board of disagreement between the ,

SORC and the Senior Vice President and CNO - Millstone; however, the Senior Vice President and CNO- Millstone shall have l responsibility for resolution of such disagreements pursuant to Specification 6.1.1.

Records The SORC shall maintain written minutes of each meeting and copies  ;

shall be provided to the Senior Vice President and CNO - Millstone and Chairperson of the Nuclear Safety Assessmcat Board.

i Nuclear Safety Assessment Board (NSAB) - Units 2 and 3 Only Function The minimum qualifications of NSAB members are as follows:

a. The Chairperson and NSAB members shall have:

1. An academic degree in an engineering or physical science i field, or hold a senior management position, and

2. A minimum of five years technical experience in their

. respective field of expertise.

b LJ

. OAP - Appendix F REV.: 20, Change 05 DATE: 03/03/99 PAGE: 9 of 18

+ .

b. The NSAB shall have-experience in and shall function to provide independent' oversight review and audit of designated activities in D the areas of:

O -

\

1. Nuclear power plant operations; l 2. Nuclear engineering; L

3. : Chemistry and radiochemistry; t

4. Metailurgy; l

5. Instrumentation and control; -!

. 6 '. Radiological safety;

7. ' Mechanical and electrical engineering; and i

8. Quality assurance practices.

I 1 The NSAB serves to advise the President and CEO 'on matters related to j l nuclear safety and notify the President and CEO within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a safety significant disagreement between the NSAB and the organization or function being reviewed.

I Composition The President and CEO shall appoint, in writing, a minimum of seven members

! to the NSAB and shall designate from this membership, in writing, a Chairperson and a Vice Chairperson. The membership shall function to provide independent review and audit in the areas listed in Function (b) above. l l

Alternates ~  !

l All alternate members shall be appointed, in writing, by the President and CEO; however, no.more than two alternates shall participate as members in i i NSAB activities at any one time. j Meeting Frequency The NSAB shall meet at least once per calendar quarter.

Quorum j l

The quorum of the NSAB shall consist of a majority.of NSAB members including the Chairperson or Vice Chairperson. No more than a minority of the quorum shall have line responsibility for operation of the same Northeast i 3.

t QAP - Appendix F l REV.: 20, Change 05 DATE: 03/03/99 PAGE: 10 of 18

h i l

~

i Utilities' nuclear. unit. No more than two alternates shall be appointed as I members at any meeting in fulfillment of the quorum requirements.

D [

l Review Re~sponsibilities  !

The NSAB shall be responsible for the review of

s. The safety evaluations for changes to procedures, equinment, or l systems, and tests or experiments completed under the ;sovisions i of 10 CFR 50.59, to verify that such actions did not constitute an I unreviewed safety question as defined in 10 CFR 50.59;

b. Proposed changes to proceduras, equipment, or systems that involve an unreviewed safety ques' ion as defined in 10 CFR 50.59;

c. Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59;

d. Proposed changes to Technical Specifications and the Operating License;

. e. Violations of applicable codes, regulations, orders, license requirements, or internal procedures having nuclear safety significance;

f. All Licensee Event Reports required by 10 CFR 50.73;

g. Indications of significant unanticipated deficiencies in any aspect of design or operation of structures, systems, or components that  !

could affect nuclear safety;  !

h. Significant accidental, unplanned, or uncontrolled radioactive ,

releases, including corrective actions to prevent recurrence; j

i. Significant operating abnormalities or deviat!ons from normal and expected performance of equipment that cnuld affect nuclear safety

• l

j. The performance of the corrective action program; and '

k. Audits arid audit plans. ,

i Reports or records of these reviews shall be' forwarded to the President and .

-CEO within 30 days following completion of the review.  :

l l

l O

QAP - Appendix F j REV.: 20,' Chai . p 05 DATE: 03/03/99 j PAGE: 11 of 18

_ __ , - _ -, .__4

j l

- Audit Program Responsibilities  !

O

\.)

The NSAB audit program shall be the responsibility of the Audits and Evaldatiun Department. NSAB audits shall be performed at least once l per 24 months in accordance with Nuclear Group Procedures and shall i encompass- '

i

a. The conformance of unit operation to provisions contained within the Technical Specifications ami applicable license conditions; i

b. The training and qualifications of the unit staff;

c. . The implementation of all programs required by Specification 6.8;

d. The Fire Protection Program and implementing procedures.

' e. The fire protection equipment and program implementation utilizing either a qualified offsite license ' fire protection engineer ~or an outside independent fire protection consultant.

) f. Actions taken to correct deficiencies occurring in equipment, structures, systems, components, or method of operation that affect nuclear safety; and

g. Other activities and documents as requested by the President and CEO.  ;

Records Written records of reviews and audits shall be maintained. As a minimum 9 these records shall include:

a. Results of the activities conducted under the provisions of this NSAB Section; i

b. Rewmmended appioval or disapproval of items considered under  !

' PORC, Responsibilities (a) through (d) and Specification 6.8; and I

c. Determination as to whether each item considered under PORC, Responsibilities (a), (b), and (d), and Specification 6.8 constitute an unreviewed safety question as defined in 10 CFR 50.59.

Station Qualified Reviewer Program - Units 2 and 3 Only Function' l The ' (Unit 2 only - Unit ' 2 tanit Director or Millstone Unit 2 Recovery l Officer)(Unit 3 only - Unit 3 Unit Director or Vice President - Mil stone Unit 3) or Senior Vice' President and CNO - Millstone may establish a Station Qualified Fteviewer Program whereby ; required reviews ~ of designated procedures or i

QAP- Appendix F I REV.: 20, Change 05  ;

DATE: 03/03/99 PAGE: 12 of 18

l 4

classes of procedures required by PORC, Responsibilities item (a), and SORC,

Responsibilities item (a) are performed by Station Qualified Reviewers and

! approved by designated managers. These reviews are in lieu of reviews by l the PORC or SORC. However, procedures which require a 10CFR50.59 evaluation must be reviewed by the PORC or SORC.

Responsibilities The Station Qualified Reviewer Program shall: i

a. Provide for the review of designated procedures, programs, and changes thereto by a Qualified Reviewer (s) other than the individual l who prepared the procedure, program, or change. j i

b. Provide for cross-disciplinary review of procedures, programs, and j changes thereto when organizations other than the preparing organization are affected by the procedure, program, or change.

c. Ensure cross-disciplinary reviews are performed by a Qualified l Reviewer (s) in affected disciplines, or by other persons designated by cognizant Managers or Directors as having specific expertise required to assess a particular procedure, program, or change.

Cross-disciplinary reviewers may function as a committee.

d. ProvW e a screening of designated procedures, programs and p

changu, nereto to determine if an evaluation should be performed in accordance with the provisions of 10CFR50.59 to verify that an I

unreviewed safety question does not exist. This screening will be performed by personnel trained and qualified in performing  ;

10CFR50.59 evaluations. l l

e. Provide for written recommendation by the Qualified Reviewer (s) to the responsible Manager for approval or disapproval of procedures )

and programs considered under PORC, Responsibilities item (a) and '

SORC, Responsibilities item (a), and that the procedure or program ,

was screened by a qualified individual and found not to require a j 10 CFR 50.59 evaluation.

If the responsible manager determines that a new program, procedure, or change thereto requires a 10 CFR 50.59 e"eluation, that Manager will ensure the required evaluation is performed to determine if the new procedure, program, or' change involves an uareviewed safety question. The new procedure, program, or change will then be forwarded with the 10 CFR 50.59 evaluation to PORC or SORC for review.

Personnot recommended to be Station Qualified Reviewers shall be designated in writing by the (Unit 2 only - Unit 2 Unit Director or Millstone Unit 2 Recovery Officer) (Unit 3 only - Unit 3 Unit Director or Vice President -

, Millstone Unit 3) or Senior Vice President and CNO C Millstone for each QAP - Appendix F REV.: 20, Change 05 DATE: 03/03/99 PAGE: 13 of 18

H -

L procedure, program, or class of procedure or program within the scope of the

Station Qualified Reviewer Program.

i Temporary procedure changes shall be made in accordance with Specification

! -6.8.3.with the exception that changes to procedures for which reviews are assigned to Qualified Reviewers will be reviewed and approved as described in Responsibilities (a) through (d) above.

Records L

The review of procedures and programs performed under the Station Qualified Reviewer Program shall_ be documented in accordance with administrative procedures.

Training and Qualification l

The training and qualification requirements of personnel designated as a Qualified Reviewer in accordance with the Station Qualified Reviewer Program shall be in t.ccordance wit" administrative procedures. Qualified reviewers shall have:

L

, a. A Bachelors degree in engineering, related science, or technical

' discipline, and two years of nuclear power plant experience; L OR

b. Six years of nuclear power plant experience; OR ci An equivalent combination of education and experience as approved by a Department Manager.

SAFETY LIMIT VIOLATION - Units 2 and 3 Only The Senior Vice President and CNO - Millstone and the Chairperson of the NSAB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the event a Safety Limit is violated.

u The Safety Limit Violation Report shall be submitted to the Commission, I the. Chairperson of the NSAB, and the Senior Vice President and CNO -

L - Millstone, within 14 days of the violations.

I RECORD RETENTION - Unit Two Only (1) _ The following records shall be retained for at least five years:

a. Records and logs of facility operation covering time interval at each power level.

QAP - Appendix F REV.: 20, Change 05 DATE: LJ/03/99 PAGE: 14 of 18

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b. Records and logs of principal' maintenance activities,

~

inspections, repair and replacement of principal items of equipment related to nuclear safety,

c. All REPORTABLE EVENTS.

d. Records of surveillance activities, inspections, and calibra- I tions required by these technical specifications,

e. Records of reactor tests and experiments.

.f. Records of changes made to operating procedures.

g. Records of radioactive shipments.

h. Records of sealed source leak tests and .asults.

i. Records of annual physicalinventory of all sealed source material of record. i

-(2) The following records shall be retained for the duration of the facility operating license:

a. Records and drawing changes reflecting facility design

' modifications made to systems and equipment described in -

.( the Final Safety Analysis Report.  !

Records of new and irradiated fuel inventory, fuel tran:fers,

' b. .

and assembly burnup histories,

c. Records of faciiity radiation and contamination surveys.

d. Records of radiation exposure for allindividuals entering radiation control areas.

e. Records af gaseous and liquid radioactive material released to the environs.

f. Records of transients or operational cycles for those facility components designed for a limited number of transients er cycles.

.l

g. Records of training and qualification for. current r.: embers of the plant staff. )

h. Records of inservice inspections performed pursuant to the l Technical Specifications. l

i. Records of' quality assurance activities required by the QA Manual.

OAP - Appendix F REV.: 20, Change 05 DATE: 03/03/99 PAGE: 15 of 18 i

~. - , ~ , . . .. _ - - , . . . _ . _

,I

'e i

j. Records of reviews performed for changes made to procedures or l ( equipment or review of tests and experiments pursuant to k ~

10 CFR Part 50.59.

i l

k. Records of meetings of ca PORC, the NSAB, and the SORC.

l. Records of Environmental Qualification which are covered under the provisions of Specification 6.13.

m. Records of reviews performed for changes made to the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM) and the Process Control Program.

RECORD RETENTION - Unit 3 Only (1) In addition to the applicable record retention requirements of Title 10, ,

Code of Federal Regulations, the following records shall be retained for I at least the minimum period indicated.

(2) The following records shall be retained for at least five years:

l

a. Records and logs of unit operation covering time interval at each power level;

m b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety; '

i c. All REPORTABLE EVENTS; l

d. Records of surveillance activities, inspections, and calibra- ,

tions required by Techn: cal Specifications;  !

e. Records of changes made to the procedures sequired by l Specifications 6.8.1;

f. Records of radioactive shipments;

g. Records of sealed source and fission detector leak tests and results; and

! h. Records of annual physical inventory of all sealed source material of record.

(3) The following records shall be retained for the duration of the unit Operating License:

D

) _J i QAP - Appendix F REV.: 20, Change 05 DATE: 03/03/P9 PAGE: 16 of 18 i

)

.e

a. . Records and drawing changes reflecting unit design modifications made to systems and equipment

. described in the Final Safety Analysis Report;

, b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories;

c. 'Hecords of radiation exposure for all individuals entering radiation

. control areas;

d. Records of gaseous and liquid radioactive material released to the environs;

e. Records _ of transient or operational cycles for those unit 1 components identified in Technical Specifications Table 5.7-1.

f. . Records of reactor tests and experiments;

g. Records of training and qualification for ;urrent members of the unit staff;

h. Records of inservice inspections performed pursuant to the j Technical Specifications; i .~ Records of quality assurance activities required by the Quality Assurance Topical Report not listed in (2) a. through (2) h. above;

j. Records of reviews performed for changes.made to procedures or equipment or reviews of tests and experiments pursuant to i 10 CFR Part 50.59;  !

k. Records of meetings of the PORC, the NSAB, an'd the SORC; )

1

1. Records of - the service lives of all hydraulic .nd mechanical i snubbers required by Technical Specifications 3.7.10 including the  ;

date' at which the - service life commences and associated _i

. installation and maintenance records; m .- Records of secondary water sampling and water i quality; and

, n- ' Records of analyses required by the Radiological Environmental Monitoring . Program that ' would permit evaluation of the accuracy of the analysis at a ' later -date. This should include procedures.  :

effective .at specified l times 'and QA records l showing that these procedures were followed.

O e QAP - Appendix F REV.: 20, Change 05 DATE: 03/03/99 PAGE: 17 of 18 M

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, - ., .,n -, .-,,,i+--a - - - - r-.- , , - , , . , , . . - . , , , -

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s

o. Records of reviews performed for changes.made to the Radiological Effluent Monitoring and Offsite

\ ~

Dose Calculation Manual (REMODCM) and the Process Control Program.

' Relocation of Technical Specification Administrative Controls Related to Quality Assurance in Response to AL 95-06.

i O

I l

I l

4 QAP - Appendix F REV.: 20, Change 05 DATE: 03/03/99' PAGE: 18 of 18

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