ML20085J766

Rev 19 to Operational QA Plan

ML20085J766
Person / Time
Site:	Monticello, Prairie Island
Issue date:	05/19/1995
From:	Amundson T, Watzl E NORTHERN STATES POWER CO.
To:
Shared Package
ML20085J765	List: ML20085J761 ML20085J766
References
NUDOCS 9506230009
Download: ML20085J766 (87)

Text

-

7:-

. . ~. 7 ; .

v.,9 ,

( ;P- ,

NORTHERN STATES POWER COMPANY I 414 Nicollet Mall Minneapolis,MN 55401 OPERATIONAL QUALITY ASSURANCE PLAN REVISION 19 i

i Reviewed By: Date: 6!/7!9f T. E. Amundson Director, Generation Quality Services J

i Approved By: t Date: ['/9-ff'  :

E. L. Watzl j Vice President Nuclear Generation  !

Effective Date:

(NRC Acceptance Date) 9506230009 950615

-PDR P ADDCK 05000263 PDR

(.

...,c 4

h

[This page intentionally blank]

l l

l I

l l

l l

g , ..

t. .,

, , . i 'e i Y? Operational Q:ality Assura*_ce PI:n

~ Revision 19 Table of Contents East 1.0 - Policy Statement 1

2.0' Introduction 6

3.0 Organization 7

4.0 Operational Quality Assurance Program 11 i

5.0 Modification Control 16 6.0 Procurement Document Control 17 7.0 Instructions, Procedures and Drawings 19 8.0 Document Control

~ 21 9.0 Control of Purchased Material, Equipment and Senices 23 10.0 Identification and Control of Materials, Parts and Components 25 11.0 Control of SpecialProcesses -

26 12.0 Inspection and Examination 27 l J 2- .

13.0 Test Control 32-

'14.0 Control of Measuring and Test Equipment

~34 _,

15.0 Handling, Storage and Shipping 35 16.0 Inspection, Test and Operating Status

.37 ;j 17.0 Nonconforming Materials, Parts or Components i

40 18.0 Corrective Action 42 19.0 Quality Assurance Records 43 20.0 Audits

'45-Appendix A _-Monticello Structures, Systems, and Components Subject to Appendix B of 10CFR50 47 i j

Appendix B - Prairie Island Structures, Systems, and Components Subject to Appendix B of 10CFR50 55

. Appendix C Nuclear Plant Fire Protection Program 65 Appendix D - Revision 19 Change Summary 81 l3

.j.

c _

1 ,.

[This page intentionally blank]

I l

l l

i i

, t_,

4 Operati:nt! Quility Assurance Plin Revision 19 1.0 Policy Statement 1.1 Northern States Power Company (NSP) has established and is implementing an Operational Quality Assurance Program. This quality assurance program is applicable to NSP nuclear  ;

plants that are regulated under provisions of an NRC Operating License.

1.2 The quality assurance program, as applied to activities affecting safety related functions, shall comply with and be responsive to applicable regulatory requirements and applicable industry codes and standards including: ,

1. 10CFR50, Appendix B. )

1

2. NRC Operating Licenses.

3. The ASME Boiler and Pressure Vessel Code,Section XI, Inservice Inspection.

4. 10CFR21, Reporting ofDefects andNoncompliance.

5. 10CFR71, Subpart H, Quality Assurance. ,

6. Nuclear Plant Fire Protection Program, Operational Quality Assurance Plan, Appendix C.

7. NSP Plant Security Plans.

8. NSP Radiation Environmental Monitoring Program.

9. ANSI N45.2.6-1978, Quahfications ofInspection, Examination, and Testing Personnelfor Nuclear Power Plants, as modified by Regulatory Guide 1.58, Resision 1. (See sections 12 and 13.)

10. ANSI N45.2.12-1977, Requirementsfor A uditing of Quality Assurance Programsfor Nuclear Power Plants.

11. ANSI N45.2.23-1978, Quahfication ofQuality Assurance Program Audit Personnel for Nuclear Power Plants, as modified by Regulatory Guide 1.146, August,1980.

1.3 The Operational Quality Assurance Program shall incorporate: (1) the requirements of ANSI N18.7-1976, as modified by Table 1-1 and (2) the requirements of the following standards to the extent specified by ANSI N18.71976, as modified by the regulatory position of the Regulatory or Safety Guides referenced below.

1. ANSI N18.1 -l 971, Selection and Training ofNuclear Power Piant Personnel (Regulatory Guide 1.8, Rev.1).

Page1of84

s*h i Operational Quality Assurance Plan -

. Revision 19

2. ANSI N45.2-1971, Quality Assurance Program Requirementsfor Nuclear Power Plants.

' ANSI N45.2.1-1973, Cleaning ofFluid Systems andAssociated Components During 3.

Construction Phase ofNuclear Power Plants (Regulatosy Guide 1.37, 3-16-73).

4. ANSI N45.2.2-1972, Packaging, Shipping, Receiving, Storage andHandling ofItems for Nuclear Power Plants (During the Construction Phase) (Regulatosy Guide 1.38, Rev. 2).

5. ANSI N45.2.3-1973, Housekeeping During the Construction Phase ofNuclear Power Plants (Regulatory Guide 1.39, Rev.1).

I

6. ANSI N45.2.4-1972, Installation, Inspection, and Testing Requirementsfor l Instrumentation andElectric Equipment During the Construction ofNuclear Power l i

Generating Stations (Safety Guide 30, August 11,1972).

7. ANSI N45.2.5-1974, Supplementary Quality Assurance Requirementsfor Installation, Inspection and Testing ofStnictural Concrete and Structural Steel During the Construction Phase ofNuclear Power Plants (Regulatory Guide 1.94, Rev.1).

8. AN5I N45.2.8-1975, Supplementary Quality Assurance Requirementsfor Installation, Inspection and Testing ofklechanicalEquipment and Systemsfor the Construction Phase ofNuclear Power Plants

9. ANSI N45.2.9-1974, Requirementsfor Collection, Storage andklaintenance of Quality Assurance Recordsfor Nuclear Power Plants (Regulatory Guide 1.88, Rev. 2).

10. ANSI N45.2.10-1973, Quality Assurance Terms and Definitions (Regulatany Guide 1.74, February,1974).

11. ANSI N45.2.11-1974, Quality Assurance Requirementsfor the Design ofNuclear Power Plants (Regulatory Guide 1.64, Rev. 2).

12. ANSI N45.2.13-1976, Quality Assurance Requirementsfor the Control of Procurement ofItems and Servicesfor Nuclear Power Plants

13. ANSI N101.4-1972, Quality Assurancefor Protective Coatings Ayplied to Nuclear Facilities (Regulatory Guide 1.54, June,1973).

l Page 2 of 84 l

\ .. . .

r

) WJ k Op:reti:nr.1 Quility Assurance Pirn Revision 19 1.4 Management directives and departmental instructions and procedures shall provide for compliance with appropriate regulatory, statutory, license and industry requirements. Specific  !

quality assurance requirements and organizational responsibilities for implementation of these j requirements shall be specified in implementing directives and instructions.  !

1.5 Compliance with this policy and the provisions of the Operational Quality Assurance Program ,

is mandatory for NSP personnel with respect to nuclear plant operational activities or i

activities which support nuclear plant operation. Personnel shall therefore, be familiar with the requirements and responsibilities of the program that are applicable to their individual ,

activities and interfaces. j 1.6 The Vice President Nuclear Generation, through an independent organization, shall l periodically have the Operational Quality Assurance Program reviewed to assure its adequacy. l i

i i

l

=

t 6

i i

i i

Page 3 of 84

,U ,

Operational Quality Assurance Plan Revision 19 l Table 1-1 Exception to ANSINI8.7-1976

1. Documentation required by ANSI N18.7-1976 may be deferred for emergency work.

Emergency work is defined as that work that must be completed immediately and which, if delayed, may result in an unsafe condition or significantly interfere with reliable plant operation.

2. Exceptions to Regulatory Guides and ANSI Standards are acceptable for those principal contractors, retained by NSP, such as NSSS contractors and A/E firms, which exceptions l4 have been approved by the NRC.

3. Section 5.1; delete this section. The provisions associated with identification of the Operational Quality Assurance Program scope are explicitly identified in Section 4 of the Operational Quality Assurance Plan.

4. Section 5.2.2; replace the third sentence with the following " Procedure changes shall be reviewed and approved as required by the Technical Specifications" Delete the fourth sentence.

5. Section 5.2 5; replace the second and third sentences with " Temporary procedures shall be reviewed and approved as required by the Technical Specifications".

6. Section 5.2.9; delete the reference to ANSI N18.17. The Plant Security Plans contain required security provisions.

7. Section 5.2.11, first sentence; change " abnormal occurrences" to " reportable events"

8. Section 5.2.13.2, fourth paragraph; change the first sentence to read " . installation or use of such items that serve a safety function" l5

9. Section 5.2.15 of ANSI N18.7-1976 shall govern review, approval, and control of required procedures except that for procedures required by the Plant Technical Specifications, the review and approval requirements stipulated in the Technical Specifications shall be utilized rather than those contained in Section 5.2.15.

10. Section 5.3; change the last sentence to read " Procedures shall be prepared and approved prior to implementation as required by 5.2.15" Page 4 of 84

t Operatirn21 Quclity Assurance Plan l Revision 19

11. Sections 5.3.9 and 5.3.9.1; delete these sections. Emergency Operating Procedures shall be f' consistent with Supplement 1 to NUREG - 0737 - Requirements for Emergency Response Capability (Generic Letter 82-33). i

12. Section 6; delete this section. The referenced documents are explicitly referenced in the i Operational Quality Assurance Plan. NSP will evaluate new or revised ANSI Standards if l appropriate for inclusion in the Operational Quality Assurance Plan. l i

t i

i l .

i Page 5 of 84

i* f Operational Quality Assurance Plan Revision 19 P- 2.0 Introduction ., y

, Northern States Power Company (NSP) is involved in the constmetion and operation of fossil-fueled '

and hydro power plants, and the operation of nuclear power plants. NSP's nuclear plant operational activities are conducted under the Operational Quality Assurance Program. The Operational Quality _

Assurance Program is formulated on a company-wide basis, to govern nuclear plant operational activities and associated support activities as required by NRC Operating License provisions and associated regulations.

n f

i Page 6 of 84 l

c ,

1 Operati=1 Qurlity Assurance Pl:n

Revision 19 l l

3.0 Organization l

., 3.1 GeneralRequirements j i

1. NSP shall be responsible for the establishment and execution of the Operational  !

Quality Assurance Program. NSP may delegate to other organizations the work of establishing and executing the Operational Quality Assurance Program, or any part  !

thereof, but shall retain responsibility therefor. i i

2. The authority and duties of persons and organizations performing quality assurance  !

functions shall be clearly established and delineated in writing. Such persons and  !

organizations shall have sufficient authority and organizational freedom to identify l quality problems; to initiate, recommend, or provide solutions; and to verify ,

implementation of solutions.  !

3. Assurance of quality requires management measures which provide that the individual f or group assigned the responsibility for checking, auditing, inspecting, or othenvise verifying that an activity has been correctly performed is qualified and does not have -

responsibility for performing or directly supervising the work except that-

a. The individual or group assigned the responsibility for auditing is independent i of the individual or group directly responsible for performing the specific

. activity.  ;

I 3.2 Organization Summary Figure 1, NSP Organization with Operational Quality Assurance Responsibilities, presents an .

organizational chart ofNSP showing a summary of functional responsibilities.  ;

i I

i i

i f

Page 7 of 84

Operational Quality Assurance Plan Revision 19

. -s

[This page intentionally blank]

4 l

i I

l l

i i

Page 8 of 84 l

bperational Quality Assurance Plan Revison 19 Figure NSP Organization with Operational Q; Chairman & Chief Executive Officier i

I i

President President NSP Electric NSP Generation I

-Transmission System Operation Vice President Director j Nuclear Generation Generation Quality Services Prc

-Electrical Equipment Maintenance l

I I

-Electrical Testing Services -Internal Audits - M<

Director Licensing & Plant Manager

-Procurement Management issues -Quality Control - Er

-Material Management -Stop Work Authority -Dr

-Ucensing Support -Engineering .

-Control of OQAP -lS

-Maintenance ,

-Supplier Qualification -Tc

-Operation (p

-Control of N1ACDs/N1AWis

-Chemistry -Ti

-Radiation Protection

-Fire Protection

-REMP

-lSFSI(P1 only)

-Design Documentation

-Training M v.p- '~.9

tality Assurance Responsibilities ,

1 I Vice President Vice President 6 Public & Govt Affairs Human Resources 7

l l 8 Director Environmental -Fitness for Duty Program Dir:ctor Director 9 duction Services Fuel Resources & Regulatory Affairs

-Access Authorization 10

,dificctions -Reactor Core Reload Design -Corporate Emergency Planning 12 gine: ring Services -Core & Safety Analysis -Radiation Program Support ,,

-Spent Fuel Management -Chemistry Program Support pwing Control

-Low /High LevelRadiation Waste Management chnical Support felding, ASME Code, NDE) gg sting laboratory Services ' APERTURE y CARD Afco Availabio on Apertura Card h

Page 9 of 84

-e .* .

0 I

' _. 6 7 8 g 1 I _

4 8

ly m f a o rg n 9 s o r

e e g

t e

c P e r

a P

Mt r _

u r e _

o h s

NR t

e u I

k As ' _

n _

ea s

- -- W ic m e c

Vu H hA c 8

hn t t r n o

- la e p p _

lg p P p u i.

u S la . S

.ir

..Na s t n

e ., m a mr a

r g

m - g o

n e ro r

~A

.vto dn C P P _

i lI e n G ta e _

E c VM a&

Icc t

P r

o tc e

ir D

ro p

ro C R d

e a

W C

ng ise n e

- t- t D is e s s

d e

s y m da2 e

e be ie g R i M a le t R n v i ty a e .

l i a e r e M L b o f a t r

i I

J. C S u h" g

s ^. r F i n c t e

c e tr l f s te o

p e a r a

o p wa o

s R.

C- - S -

LW e

R )

E s e D e c c - N, i n e rv e

a s d o S -

r e y u

s *., d .tr C oE p

pM m a r -

s s e r A w s n

r uS o y

t c o f;g o

C S A, ba -

t 1

e r

g a , g lag c

Lg e

i i

D c , b n

l 4 w iri e do g a de s -

I u M ; D,

, r t S eW T( T e

eQ r

t ul ll s g a i

i n W A

Fo i f r 1

N t iee n a h ic r i

G e ts r CRf n e c

D C

e &o

, AP e A p ne G E R A evr 1

tr r r Q u 1 O

ht nt u arc ae i

lee ks ne iI t

o c

ire m,e,, J kr o

O f

o u N Q fo h x eG r D dn Wp d* dr i CE PP r

~

t n

w S e o r e o N

I._ C t

n H - ,

S .C i

o t n o

a . n s i

z i 9 e a tr n c e e .

ag t

o

. )

ly m u

e r n c r u c P c o o O -

d-

- nan nlo ^-i n o .e o lP D n

g n

i te u L. t s P r

P I( g P ,.

r M S H S

in a

ep ~ da E F S

is e e O C- -Rm.

D-C-M - R Tr N

- I. -

l n. .

1 g  ;

r" n u

% t s

is n

e

^, w.

i 3

m e

g l.. ,

a n A L

a M

n a

l P no ._

ec t a

n a i Lr e

r u

p a s

s om M .m. t 2

A n .

-~

y t e e sg it ic s

y m p m g l S is : s a tt n iu n u sce io E q

T e .

~M e

Q l

1 dD is e e s l a

t a -

m c ~

a9 n1 o

n Fr PS N

s n

a ir t

o c

~ *L -W a iae t

r s T Dr M

e iv pe OR Iii ?I ) f !;'

i Operational Quality Assrra:ce Phn Revision 19

[This pageintentionally blank]

I l

l l

l.

4 Page 10 of 84 .

J Operatiozal Quality A'ss:rance PI:s

. Revision 19  !

4.0 Operational Quality Assurance Program  :

,, 4.1 GeneralRequirements j P

1. The Operational Quality Assurance Program shall be:  ;

a. Documented by written Directives, Instructions, or Procedures. j

b. Carried out throughout plant operating life in accordance with those Directives, Instructions, or Procedures.

2. The Program shall include identification of:  ;

a. The structures, systems, and components to be covered. .

I

b. The major organizations participating in the Program, together with the designated functions of these organizations. ,

3. The Program shall provide control over activities affecting the quality of the identified structures, systems, and components to the extent consistent with their importance to ,

safety.

t

4.

• Activities affecting quality shall be accomplished under suitably controlled conditions.  !

Controlled conditions include the use of appropriate equipment; suitable environmental I conditions for accomplishing the activity, such as adequate cleanliness; and assurance ,

that all prerequisites for the given activity have been satisfied.

5. The Program shall take into account the need for special controls, processes, test equipment, tools, and skills to attain the required quality, and the need for verification {

of quality by inspection and test.

6. The Program shall provide for indoctrination and training of personnel performing l activities affecting quality as necessary to assure that suitable proficiency is achieved ,

and maintained.

7. The adequacy and status of the Program shall be regularly reviewed. j

8. Management of other organizations participating in the Program shall regularly review the status and adequacy of that part of the Program which they are executing. .

i t

i Page 11 of 84 l

..~ ,

Operatiozi Q:ality Assur rce PI:n -

Revision 19 4.2 General Description

1. The Operational Quality Assurance Program has been established to govern the operational activities and the activities necessary to support operation of the company's nuclear plants operated under an NRC Operating License. The Operational Quality Assurance Program is thus an overall integrated company-wide program which  ;

governs all safety related, fire protection related and 10CFR71 related activities as they pertain to operating nuclear plants.

2. The Program has been initiated by Senior NSP management issuing a single directive l2 to the Vice President Nuclear Generation establishing him as being responsible for formulating and implementing an Operational Quality Assurance Program and identifying the program objectives.

3. The Operational Quality Assurance Program shall utilize the following documents to meet the program objectives:

a. Operational Quality Assurance Plan (Plan).

b. Administrative Control Directives (Directives) at the Corporate and/or Site l 14 level.

c. . Administrative Work Instructions (Instructions) at the Corporate and/or Site l 14 level.

I

d. Required Procedures (Procedures) at the Plant and Department level.

l

4. The Plan shall be considered an overall document which governs the implementing l documents (i.e., Directives, Instructions, and Procedures).

5. For ease of administration, implementing documents shall be issued at the following program levels:

a. Corpgrate: Approving Authority, President NSP Generation, Vice President Nuclear Generation and Director Generation Quality Services. l6

b. Sites (Prairie Island and Monticellot Approving Authority, Plant Manager. l7

c. Departments Providing Nuclear Plant Supp_o_rt: Approving Authority, Department Manager.

Page 12 of 84

p

! Operational Qrlity Assurance Pla Revision 19

6. Corporate Administrative Directives establish the minimum requirements for Site Administrative Directives and other supporting departmental instructions and procedures.

a. There need not be a corresponding Site level Directive for every Corporate level Directive. Corporate level directives may also be implemented at the Site level through Site level Instmetions or Procedures.

4.3 Operational Quality Assurance Plan

1. The Operational Quality Assurance Plan shall be a document which describes in general terms how compliance with the quality requirements presented in 10CFR50, Appendix B and 10CFR71, Subpart H is accomplished with respect to company nuclear plants regulated by an NRC Operating License.

2. The Operational Quality Assurance Plan shall be issued under the authority of the Vice President Nuclear Generation and shall be reviewed periodically.

3. The 0;ierational Quality Assurance Plan shall be controlled to assure current copies are made available to personnel responsible for the revision, review and approval of Corporate AdministrativeDirectives.

4. . All changes to the Operational Quality Assurance Plan shall be approved by the Vice President Nuclear Generation or equivalent management position.

4.4 Administrative Control Directives

1. Administrative Control Directives (Directives) shall be documents which establish responsibility and requirements governing activities associated with plant operation.

Directives shall be first tier implementing documents and shall receive a quality review prior to issuance. The quality review shall assure compliance with the Operational Quality Assurance Program objectives. Required Directives shall be controlled and reviewed periodically.

2. Administrative Control Directives shall be issued as necessary. It is mandatory that the Directives at the Corporate level assure compliance with all applicable requirements of 10CFR50, Appendix B and 10CFR71, Subpart H. The Directives issued at the site levels are not expected to satisfy all 10CFR50, Appendix B and 10CFR71, Subpart H requirements.

Page 13 of 84

..- , l Operational Quality Assurance Plan

)

Revision 19 4.5 Administrative Work Instructions

1. Administrative Work Instructions (Instructions) shall be documents which provide guidelines or instructions for the implementation of the requirements of Administrative Control Directives. Instructions shall be second tier implementing documents and shall receive a quality review prior to issuance. The quality review shall assure compliance with pertinent Directive requirements and assigned responsibilities.

2. Administrative Work Instmetions may be issued at the Corporate and Site level.

Instructions shall generally be utilized for department interfacing. Required Instmetions shall be controlled and reviewed periodically.

4.6 Procedures

1. Procedures shall be documents which provide specific instructions for performing an activity. Procedures shall be second or third tier documents utilized to perform safety related, fire protection, and 10CFR71 related activities as required by the applicable NRC Operating License Technical Specifications.

2. Procedures shall be provided where applicable, to assure that activities important to safety are performed in the required manner. Required procedures shall be reviewed and approved as required by the applicable Technical Specifications. Approval of procedures not required by the Technical Specifications shall be by a member of the responsible area management. Review of procedures not required by Technical Specifications shall be by an independent knowledgeable person. Required procedures shall be controlled and reviewed periodically.

4.7 Program Administration

1. Administration of the Corporate level of the Operational Quality Assurance Program shall be performed by the Director Generation Quality Services. l6

2. Disputes between Generation Quality Services personnel and other organizations l 15 relative to Program requirements shall be referred to the Approving Authority (as identified in Section 4.2 of this Plan) responsible for establishing the pertinent requirement.

3. Program administration shallinclude the following activities:

a. Review of Corporate Administrative Control Directives.

b. Review of Corporate Administrative Work Instructions.

c Performance of required audits.

Page 14 of 84

!  ; Oper:tinal.Qu lity Assur rce Plan Revision 19

d. Reporting to management concerning:  :

.t 1.- Program status.

2. Program discrepancies including quality trends.  !

I 4.8 Program Boundary  ;

1. The structure, systems, components, and other items requiring quality assurance are 'i listed in Appendices A and B. The Program shall also include shipment of radioactive ,

materials as required by 10CFR71 and systems and activities associated with fire l' protection as identified in Appendix C.

2. An index shall be established and maintained by the Director Generation Quality 6

Services which identifies the Directives and Instmetions that are utilized to implement ,

the requirements of ANSI N18.7-1976 that are committed to in Section 1.0 of this plan and the requirements identified in the remaining sections of this plan. -

4.9 Quality Assurance Training Training programs shall be established for those personnel performing quality-affecting

• activities such that they are knowledgeable in the quality assurance documents and their  :

requirements and proficient in implementing these requirements. These training programs ,

shall assure that.

1. Personnel responsible for performing quality-affecting activities are instructed as to the purpose, scope, and implementation of the quality-related Directives, Instructions, and i Procedures.

2. Personnel performing quality-affecting activities are trained and qualified, as  ;

appropriate, in principles and techniques of the activity being performed.

3. The scope, the objective, and the method ofimplementing the training programs are ,

documented.

4. Proficiency of personnel performing quality-affecting activities is maintained by i retraining, re-examination, and/or recertification as appropriate. .j

5. Methods are provided for documenting training sessions describing content, attendance, date of attendance, and the results of the training session, as appropriate.

6. Fire protection training is accomplished in accordance with Appendix C.

i Page 15 of 84 l l

i

Operational Quality Assurance Plan Revision 19 5.0 Modification Control i 5.1- General Requirements ,

i Modifications shall be subject to design control measures commensurate with those applied to l the original design and be approved by the organization that performed the original design unless the company designates another responsible organization.  ;

5.2 Uniform Modification Process l A uniform process for controlling modifications to nuclear plants shall be provided in the Operational Quality Assurance Program. Measures shall be established to assure that: j

1. The requirements of ANSI N45.2.11-1974 are implemented. i

2. Reviews and approvals are performed.

3. Plant documentation is updated.

4. Appropriate installation procedures are prepared and utilized, t

5. Tests and inspections are pedormed as necessary.

6. Site procedures are reviewed and revised as appropriate. i 1

7. 10CFR50.59 is complied with. J

8. Fire protection reviews are performed as required by Appendix C.

l l

Page 16 of 84 l

n

.. .,- I

! Operatimi Qurlity Assur:nce Plan Revision 19 j 6.0 Procurement Document Control l

,, 6.1 General Requirements  !

i Messures shall be established to assure that applicable regulatory requirements, design bases,  !

and other requirements which are necessary to assure adequate quality are suitably included or l referenced in the documents for procurement of material, equipment, and services, whether i purchased by NSP or by its contractors or subcontractors. To the extent necessary,  ;

procurement documents shall require contractors or subcontractors to provide a quality  :

assurance program consistent with the peninent provisions of 10CFR50, Appendix B or  :

10CFR71, Subpart H. l 6.2 Technical and Quality Requirements j

1. The Operational Quality Assurance Program shall contain provisions for controlling ,

procurement of material, equipment, components, and services that are safety related,  ;

fire protection related, or 10CFR71 related and utilized at or for an operating nuclear l plant.

2. Procurement documents shall contain specific technical and quality requirements. )

Renewal, spare, and replacement parts shall be required to meet the original

]

specification (or properly reviewed and approved revision) or construction code,  ;

quality assurance documentation requirements, and vendor quality assurance program  !

requirements.

3. Quality assurance requirements that are required of the vendor shall be included.

Quality assurance requirements shall be based on ANSI N45.2-1971 (or equivalent standard). Documentation requirements shall include, as applicable, chemical analysis repons, material certification, testing results, and testing reports. Time and frequency of submittals should be included. ,

4. Procurement documents shall contain provisions which establish the right of access to vendor facilities and records for source inspection and audits as appropriate.

5. Procurement documents for contracting packages for transport of radioactive materials shall require a copy of the package license, cenificate, or other NRC approval authorizing use of the package. The procurement documents shall also require copies of all documents referred to in the license, cenificates, or other NRC approval as applicable.

Page 17 of 84

t se a Operational Quality Assurance Plan '

j Revision 19 .,

6.3 ' Review and Approval Documents, and changes thereto initiating procurement of safety related, fire protection related,10CFR71 related material, equipment, components or services shall be approved by appropriate management personnel and shall be subject to a quality review to insure applicable regulatory requirements, design bases, quality assurance, and other requirements are adequately satisfied prior to release. [

6.4 Fire Protection Procurement Control The additional procurement controls identified in Appendix C shall be applied to purchasing fire protection systems and equipment.' l 4

i l

i i

t l

l i

Page 18 of 84 f

I - - _. - .

U 7 Operati=1 Q::rlity Assyr=ce PI:n .

. Revision 19 l;

7.0 Instructions, Procedures and Drawings  ;

,,. 7.1 . General Requirements

1. Directives, Instructions, Procedures, and drawings of a type appropriate to the [

circumstances shall be provided for the control and performance of activities which affect quality.

2. Directives, Instructions, Procedures, and drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities ,

have been satisfactorily accomplished.

7.2 Directives and Instructions Directives and instn2ctions shall be issued which establish procedural requirements for appropriate functional areas. Su ,1rocedural requirements shall include the following as 'f appropriate: l

1. - Procedure review and approval reqmrements. f

2. Procedure control requirements.

{

i

3.

• Procedure content requirements.

7.3 Procedures  ;

1. Procedures of a type appropriate to the circumstances shall be provided for the I performance of activities which affect the quality of safety related, fire protection related, or 10CFR71 related structures, systems, or components. y

2. The following procedures shall be provided:

a. Operating procedures.  !

b. Emergency procedures.

c. Surveillance test procedures.  ;

i u

d. Routine or preventive maintenance procedures.  !

i

c. Calibration procedures.

l

f. Plant chemistry and count room procedures. )

l

g. Radiation protection procedures.

Page 19 of 84

i Operational Quality Assurance Plan - ,

Revision 19 - l f

I

h. Emergency plan procedures.- l

?

i. Special process procedures. {

j. Preoperational and operational test procedures.-.

t

'k. Audit procedures. j

1.  ; Fire fighting procedures.  !

m. Document control procedures. i

.i

n. Radioactive material shipment procedures.

o. Inspection and examination procedures.

7.4 Drawings and TechnicalManuals  !

Drawings and technical manuals of a type appropriate to the circumstances may be used as.

procedural documents for conducting activities that affect the quality of safety related, fire .[

protection related, or 10CFR71 related structures, systems, or components.

i I

)

l Page 20 of 84

f Operati=1 Qudity Assura:ce P!:n Revision 19 i i

8.0 Document Control i

,c 8.1 General Requirements .

1. Measures shall be established to control the issuance of documents, such as Directives, -l Instructions, Procedures, and drawings, including changes thereto, which prescribe i activities affecting quality. i i

2. - These measures shall assure that documents, including changes, are:  !

t a.- Reviewed for adequacy and approved for release by authorized personnel, and -

t

b. Are distributed to and used at the location where the prescribed activity is .

i performed.

3. Changes to documents shall be reviewed and approved by the same organization that i performed the original review and approval or another designated responsible  ;

organization.  ;

8.2 Administrative Control Directive Control l

}

1. Directives issued to implement the Operational Quality Assurance Program shall be i

• controlled to assure that current copies and appropriate indexes are made available to  :

personnel performing the prescribed activities. Directives shall be reviewed to assure ,

their compatibility with the Operational Quality Assurance Program objectives and i shall be approved by the designated management.

2. Changes to Directives shall be reviewed and approved in the same manner as the  ;

original.

8.3 Administrative Work Instruction Control l

1. Instructions issued to implement provisions of Directives shall be controlled to assure that current copies and appropriate indexes are made available to personnel performing ,

the prescribed activities. Instructions shall be reviewed to assure that they are ,

comprtible with pertinent Directive provisions and shall be approved by designated l management.

2. Changes to Instructions shall be reviewed and approved in the same manner as the original.

1 Page 21 of 84 l l

l

Operational Quality Assurance Plan Revision 19 8.4 Procedure Control

1. Required procedures shall be controlled to assure that current copies are made available to personnel performing the prescribed activities. Required procedures shall be reviewed by a knowledgeable individual and shall be approved by a management member of the organization responsible for the prescribed activity. Required procedures shall be reviewed and approved as required by the Technical Specifications. Appropriate indexes of standing procedures shall be formulated and made available to personnel responsible for performing the prescribed activities.

2. Significant changes to required procedures shall be reviewed and approved in the same manner as the original and shall comply with the Technical Specifications.

8.5 Drawing Control

1. Drawings which represent the physical and ftmetional aspects of the operating nuclear '

plants and which are critical to safe plant operation or safety of personnel shall be maintained in a current status. Appropriate indexes shall be formulated and made available to personnel responsible for plant operation, maintenance, and modification.

2. Measures shall be established for revising site drawings and for distributing revised drawings. Proposed revisions to drawings shall be reviewed by a knowledgeable individual to determine the safety significance and appropriateness of the change.

8.6 Specifications Plant design specifications shall be controlled to assure that current copies and appropriate indexes are made available to personnel responsible for plant operation, maintenance, and modification.

8.7 Radioactive Shipment Package Documents ,

All documents related to a specific shipping package for radioactive material shall be controlled by appropriate instructions; all significant changes to such documents shall be similarly controlled.

8.8 Updated Safety Analysis Reports ,

Updated Safety Analysis Reports shall be updated in accordance with the applicable provisions of 10CFR50.

8.9 Technical Manuals Technical manuals that are used as procedural documents shall be controlled.

Page 22 of 84 1

? Operatioxal Q:ality Assira:ce Pl=

Revision 19 9.0 Control of Purchased Material, Equipment and Services

,, 9.1 General Requirements l f

1. Measures shall be established to assure that purchased material, equipment and j services conform to the procurement documents. These measures shallinclude provisions, as appropriate, for vendor evaluation and selection, objective evidence of quality furnished by the vendor, inspection at the vendor source, and examination of  :

products upon delivery.  ;

2. Documentary evidence that material and equipment conform to the procurement i requirements shall be available at the site prior to installation or use of such material - i and equipment. This documentary evidence shall be retained at the site and shall be l

sufIicient to indicate that the purchased material and equipment meet the specific .

requirements of the codes, standards, or specifications.

3. The effectiveness of the control of quality by vendors shall be assessed at intervals consistent with the importance, complexity and quantity of the product or semce.  ;

9.2 Procurement Review

1. Documents initiating procurement of safety related, fire protection related, and ,

• 10CFR71 related material, equipment and services shall be subject to a review to ensure applicable regulatory requirements, design bases, quality assurance, and other -

requirements are adequately satisfied.

1

2. Quality assurance requirements shall include identification of applicable elements of i ANSI N45.2-1971 (or equivalent) that are required to be included in the vendor's quality assurance program.

9.3 Vendor Evaluation and Verification l

1. The adequacy of vendor's quality assurance program specified in procurement documentation shall be verified prior to use of the procured material, equipment, or service. Vendor's adherence to their quality assurance program to the extent  ;

appropriate for the procured material, equipment or service shall be verified.

2. Vendor evaluations shallinclude inspections, audits, or surveillances as appropriate.

These activities shall be planned and performed in accordance with written procedures )

based upon procurement document requirements.  ;

i

3. Material and equipment may be procured and used based on appropriate certificates of conformance, provided the validity of such certificates are periodically evaluated by audits, independent inspection or tests and that such certificates comply with applicable code provisions.

Page 23 of 84

3 i Operational Quality Assurance Plan

' Revision 19 9.4 ' Receipt Inspection

1. Material and equipment shall be inspected upon receipt at the site prior to use or storage to determine that procurement requirements are satisfied. This inspection shall '

include verification that required documentation is complete. l

2. Nonconforming material and equipment shall be controlled to assure such material or l equipment is not utilized to fulfill a safety related, fire protection related or 10CFR1 related function prior to an acceptable resolution of the discrepancies. ,

i L

i I

i h

i

?

Page 24 of 84 ,

• Operationi Qslity Assurance Pirn

. Revision 19 -

10.0 Identification and Control of Materials, Parts and Components 10.1 General Requirements l .1. Measures shall be established for the identification and control of materials, parts and  ;

components, including partially fabricated assemblies. These measures shall assure that identification of the item is maintained by heat number, part number, serial number or other appropriate meana, either on the item or on records traceable to the item, as required throughout fabrication, erection, installation and use of the item.

2. These identification and control measures shall be designed to prevent the use of -

incorrect or defective material, parts and components.

10.2 Spare Parts Control

1. Spare parts held for future use on safety related, fire protection related, and 10CFR71 related components shall be controlled in such a manner that assures they will perform their safety function when utilized.

2. Measures shall be taken which assures these items are in an appropriate condition for use or will be placed in such a condition prior to use.

10.3 Material Control Material held in storage for use on safety related, fire protection related, and 10CFR71 related  :

systems, structures or equipment shall be controlled in such a manner as to prevent its l degradation and to assure the rejection ofincorrect or defective material. This material shall l be identified by heat number or other appropriate means, either on the item or on records 1 traceable to the item. The method utilized in identification shall not significantly affect the fit, function, or quality of the item being identified.

10.4 ReceiptInspection Material, parts and components that are to be utilized to fulfill a safety related, fire protection related, and 10CFR71 related function or used for shipment of radioactive materials shall be inspected upon receipt to assure that associated procurement document provisions have been satisfied. Measures shall be established for identifying nonconforming material, parts and components.

i 10.5 Nuclear Fuel Control Measures shall be established to protect special nuclear material against theft or diversion in i accordance with applicable NRC regulations.

]

Page 25 of 84

r I

Operational Quality Assurance Plan Revision 19 11.0 : Control of Special Processes 11.1 GeneralRequirements l 1

Measures shall be established to assure that special processes, including welding, heat treating, ,

and non- destructive examination are controlled and accomplished by qualified personnel using qualified procedures in accordance with applicable codes,' standards, specifications, criteria and other special requirements.

1 11.2 WeldingProcedures i

1. Safety related welding and brazing shall be performed in accordance with qualified i

procedures. Safety related welding and brazing procedures shall be qualified in -

accordance with applicable codes and standards and shall be reviewed to assure their technical adequacy and approved by management.

2. Measures shall be established for controlling welding and brazing procedures that assure such procedures are qualified, reviewed and approved, as required, prior to use.

11.3 Welder Qualification

1. Measures shall be established that assure safety related welding and brazing is ,

performed by qualified personnel. Welders and brazers shall be qualified, and requalified, in accordance with applicable codes and standards.

2. Measures shall be established for controlling welder and brazer qualification and requalification that assure qualified personnel are utilized to perform safety related welding and brazing.

11.4 Heat Treating Procedures

1. Heat treating shall be performed in accordance with procedures formulated and "

approved in accordance with applicable codes and standards.

2. Measures shall be established for controlling heat treating procedures that assure such procedures are qualified, reviewed, and approved, as required, prior to use.

s Page 26 of 84

rq i

-.: ..c i l.

Operatio al Q::ality Ass r=ce Plas l Revision 19 j i

12.0 Inspection and Examination j

. , , 12.1 GeneralRequirements  ;

1. Measures shall be established for the inspection and examination ofitems or activities ,

affecting quality to verify conformance to specified requirements for the purpose of determining acceptability. j

2. Verification ofitems shall be performed for each work operation where necessary to  ;

assure quality. If verification of processed items is impossible or disadvantageous, indirect control by monitoring processing methods, equipment and personnel shall be -  :

provided.

3. Both verification and process monitoring shall be provided when control is inadequate without both.

i

4. If mandatory inspection hold points, which require witnessing or inspection and i beyond which work shall not proceed without prior consent are required, the specific ,

hold points shall be indicated in appropriate documents.  ;

5. Personnel performing required inspections or examinations shall be qualified in l accordance with applicable codes, standards and training programs. l

~

4

6. Inspections and examinations shall be performed by individuals other than those who  :

performed or directly supervised the activity being inspected or examined.

12.2 Plant Operation l 1

i

1. Measures shall be established that assure periodic inspection of safety related and fire i protection related systems, components, and structures. Such inspection ofplant i systems and equipment shall be performed to assure that such systems and equipment i are in the required status and configuration. Routine general inspections of the [

accessible plant facilities to verify appropriate safety measures are maintained including l fire protection shall also be performed.

2. An inspection of the core shall be performed prior to startup follow' m g refueling to l assure specified fuel and reactor internal configuration.  !

3. Personnel performing plant operation inspections shall be qualified based upon  ;

experience, training applicable to area ofinspection and training in inspection methods. j l,

i i

Page 27 of 84 i

Operational Quality Assurance Plan Revision 19  ;

12.3- Inservice Inspection  ;

, 1. Measures shall be established that assure inservice inspection examinations are  !

- performed in accordance with applicable provisions of the ASME Boiler and Pressure Vessel Code,Section XI as required by 10CFR50.55a. l 16

2. - Personnel performing inservice inspections shall be qualified in accordance with ANSI i N45.2.6-1978, as modified by Regulatory Guide 1.58, Revision 1. (

12.4 Inspection ofMaintenance and Modifications

1. Measures shall be established which assure that activities associated with plant [

maintenance and modifications are inspected when determined appropriate by quality  !

or other qualified personnel. Such inspections shall include verification that:

I

a. Appropriate procedures are available, i

b. Plant equipment control exists,  ;

c. Applicable procedures are adhered to,  !

d. Qualified personnel are utilized, j

. I

e. Fire protection measures are established,  :

f. Radiation protection measures are established,  !

g. Appropriate materials and replacement parts are utilized, l

h. Workis completed as required, I i

i. Plant equipment is returned to service as required, l l

.i . Activities are appropriately documented, and ,

k. Redundant equipment is available. {

i

2. Personnel performing inspections of plant maintenance and modifications shall be  !

qualified based upon experience, training applicable to area ofinspection and traimng l in inspection methods. )

Page 28 of 84 ,

F r . ...

! Operatio al Q:ality Assurc ce PI:n Revision 19 12.5 Modifications and Non-Routine Maintenance

1. Measures shall be established which assure that non-routine maintenance and modification receive prior review by a qualified individual to identify applicable inspections. Such reviews shall include considering: (1) required mechanical inspections, electrical inspections, instrumentation and control inspections, structural inspections, and inspection ofnon-NDE special processes, (2) appropriate inspection procedures, and (3) appropriate qualification ofinspection personnel.

2. Measures shall also be established which assure that the results ofidentified inspections are evaluated by a qualified individual to verify their adequacy.

3. Personnel performing inspections of modifications and non-routine maintenance shall be qualified in accordance with ANSI N45.2.6-1978, as modified by Regulatory Guide ,

1.58, Revision 1.

12.6 Technical Services

1. Measures shall be established which assure that activities associated with technical services (such as surveillance testing, instrument calibration, laboratory services, etc.)

are inspected when determined appropriate by quality or other qualified personnel.

2.

• Personnel performing inspections of technical services shall be qualified based upon experience, training applicable to area ofinspection and training in inspection methods.

12.7 ReceiptInspection '

Measures shall be established which assure that received items are inspected by personnel l qualified in accordance with ANSI N45.2.6-1978, as modified by Regulatory Guide 1.58, l Revision 1.

12.8 VendorInspection l

Measures shall be established which assure that verifications and process monitoring specified I in appropriate procurement documents for items are performed by personnel qualified in accordance with ANSI N45.2.6-1978, as modified by Regulatory Guide 1.58, Revision 1.

12.9 Fire Protection Inspections

. Measures shall be established which assure that fire protection inspections required by applicable Technical Specifications are performed by personnel qualified in accordance with Appendix C, Section 14.0.

Page 29 of 84

e ,

=

Operational Quality Assurance Plan .

Revision 19 12.10 Radioactive Material Packages

,, 1. Measures shall be established which assure that packages utilized to ship licensed radioactive material off-site are inspected in accordance with the applicable provisions of10CFR71.

2. Personnel performing inspections of radioactive material packages shall be qualified based upon experience, training applicable to area ofinspection and training in inspection methods.

12.11 Emergency Equipment _

l. Measures shall be established which assure that emergency equipment required to implement emergency plans is inspected when determined appropriate by qualified personnel.

2. Personnel performing emergency equipment inspections shall be qualified based upon experience, training applicable to area ofinspection and training in inspection methods.

12.12 Handling Equipment

1. Measures shall be established which assure that plant handling equipment (such as cran'es, lift trucks, fuel handling tools) is inspected when determined appropriate by Generation Quality Services personnel or other qualified personnel. l 15

2. Personnel performing inspections of handling equipment shall be qualified based upon experience, training applicable to area ofinspection and training in inspection methods.

12.13 Nondestructive Examination Measures shall be established which assure that the following examinations are performed by personnel qualified in accordance with the American Society ofNondestructive Testing Recommended Practice No. SNT-TC-1 A.

1. Radiographic Testing (RT).

2. Ultrasonic Testing (UT).

3. Magnetic Particle Testing (MT).

4. Liquid Penetrant Testing (PT).

Page 30 of 84

1

~ I Operati:n 1 Qudity Assurance Plin Revision 19

5. Eddy Current Testing (ET). l

6. Neutron Radiographic Testing (NRT). I

7. Leak Testing (LT).

12.14 Inspection and Examination Procedures i L Required inspections and examinations shall be performed in accordance with appropriate instnictions, procedures, and checklists. Such instructions, procedures, and checklists shall contain a description of objectives, acceptance criteria and prerequisites for performing the inspections or examinations. These procedures shall also specify any special equipment or calibrations required to conduct the inspection or examination. Inspection and examination results shall be documented and evaluated by responsible authority to assure that inspection and examination requirements have been satisfied.

2. Where activities are to be inspected or examined, the activity procedure shall identify hold points in the activity sequence to permit inspection or examined. The activity procedure shall require appropriate approval for the work to continue beyond the designated hold point and identification of those performing the inspection. The procedure or checklist shall require recording the date, identification of those

. performing the inspection or examination, and as-found condition.

1 I

Page 31 of 84

Operational Quality Assurance Plan Revision 19 13.0 Test Control

,13.1 General Requirements

1. Measures shall be established to assure that all testing required to demonstrate that structures, systems and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable documents. Proof tests prior to installation, preoperational tests, and operational tests during nuclear power plant operation, of structures, systems and components shall be included as appropriate.

2. Test procedures shallinclude provisions for assuring that all prerequisites for the given test have been met, that adequate test instrumentation is available and used, and that the test is performed under suitable environmental conditions. Test results shall be documented and evaluated to assure that test requirements have been satisfied.

l 13.2 Surveillance Tests {

l. A surveillance test program shall be established to assure that testing required to q demonstrate that safety related and fire protection related structures, systems, and components will perform satisfactorily in service. Surveillance tests shall be identified andperformed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable documents. The surveillance test program shall include, as a minimum, those surveillance tests specified in applicable Technical Specifications and functionalInservice Inspection testing of pumps and valves. Surveillance requirements for fire detection and protection syste:ns in other areas of the plants shall be developed using appropriate NFPA for guidance.

2. Surveillance test results shall be documented and evaluated to assure that test requirements have been satisfied or deficient items satisfactorily resolved. Functional l

Inservice Inspection tests shall be performed by personnel qualified in accordance with applicable requirements.

13.3 Preoperational and Operational Tests Measures shall be established to assure that appropriate preoperational and operational tests are performed on safety related and fire protection related stmetures, systems and componrats that have been subject to modification or significant maintenance. Such tests shall be performed in accordance with the original design and testing requirements or acceptable alternatives. Test results shall be documented and evaluated to assure that test requirements have been satisfied or deficient items satisfactorily resolved.

Page 32 of 84

! Operctinel Quility Assurance Plin Revision 19 13.4 ProofTests Measures shall be established to assure that appropriate proof tests are specified in procurement documents for safety related and fire protection related replacement material and equipment and that such tests are performed and documented prior to installation. l

'13.5 Special Tests Measures shall be established that assure safety related tests are reviewed and approved as required by 10CFR50.59 and applicable Technical Specifications. Such tests shall be performed in accordance with appropriate procedures. Test results shall be documented and ,

evaluated to assure test requirements have been satisfied.

13.6 PersonnelQualification j i

i Personnel performing required tests shall be qualified based upon experience, training applicable to area of testing and training in testing methods, unless otherwise specified by j applicable codes. {

t I

1 i

1 i

l I

l Page 33 of 84

2.- ,

Operational Quality Assurance Plan  !

Revision 19

.14.0 Control of Measuring and Test Equipment J4.1 GeneralRequirements Measures shall be established to assure that tools, gauges, instmments and other measuring and testing devices used in activities affecting quality are properly controlled, calibrated and adjusted at specified periods to maintain accuracy within necessary limits.

14.2 Installed Plant Instrumentation Measures shall be established to assure that installed safety related plant instrumentation is maintained and calibrated at specified periods to maintain accuracy within necessary limits.

Maintenance and calibration of safety related instrumentation shall be performed in accordance with appropriate procedures and shall be controlled and documented.

14.3 Measuring and Test Instrumentation Measures shall be established to assure that tools (micrometer, calipers, etc.), gauges, instruments and other inspection, measuring, test equipment .and devices used to vedfy conformance to established requirements are maintained and calibrated at specified periods to maintain accuracy within necessary limits. Calibration of such measudng and test equipment shall be controlled and shall be traceable to the National Institute of Standards and Technology or where national standards are not available, the basis of calibration shall be documented.

Page 34 of 84

7_

Operatiozal Q ality Assur=ce Pim i Revision 19 -

15.0 Handling, Storage and Shipping l

,, 15.1 GeneralRequirements

1. Measures shall be established to control the handling, storage, shipping, cleaning and preservation of safety related material and equipment in accordance with work and ,

inspection instructions to prevent damage or deterioration.

2. - When necessary for particular products, special protective environments such as inert gas atmosphere, humidity levels, and temperature levels, shall be specified and identified.

15.2 Storage Facilities Storage facilities shall be provided at each operating nuclear plant for storage of safety related and Sre protection related operating and maintenance supplies, spare parts, replacement parts, replacement equipment, materials and tools. These storage facilities shall assure physical  ;

protection and protection from environmental conditions including temperature and moisture as appropriate. Storage facilities shall be arranged and equipped to facilitate control of the -

stored safety related items.

15.3 Nuclear Fuel Storage Areas shall be provided for storage of nuclear fuel which assure physical protection, subcritical arrangement, adequate cooling, adequate radiation shielding and containment of radioactive material as appropriate for the condition of the stored fuel.

15.4 Radioactive Material Storage

1. Areas shall be provided for storage of radioactive material which assure physical protection, as low as reasonably achievable radiation exposure to personnel, control of the stored material, and containment of radioactive material as appropriate.  !

2. Handling, storage, and shipment of radioactive material shall be controlled based upon the follow ~m g criteria:  ;

a Established safety restrictions concerning the handling, storage, and shipping of j packages for radioactive material shall be followed.

b. Shipments shall not be made unless all tests, certifications, acceptances, and final inspections have been completed.

c. Work instmetions shall be provided for handling, storage, and shipping operations.

Page 35 of 84

4.4 ,

' Operational Quality Assurance Plan . I Revision 19 15.5 Storage Control Stored material, parts and equipment shall be controlled in a manner that assures safe plant operation when and if the items are utilized. Stored safety related and fire protection related items shall be controlled to assure that the item will perform its safety function when utilized.

15.6 MaterialHandling Safety related material, supplies, equipment and parts shall be handled in accordance witt.

procurement documentation and in accordance with appropriate material handling practice:s.

Material handling equipment shall be subject to periodic testing and preventive maintenaace

.which assures its operability. Appropriate operating instructions and procedures shall be provided for handling equipment.

15.7 Shipping and Packaging

1. Shipping and packaging requirements shall be prepared for material, equipment, and components that are to be shipped off-site and returned for use at a nuclear plant to perform a safety related function. Such requirements shall assure that the item's safety related function is not significantly degraded while in transit.

2. Shipping and packaging documents for radioactive material shall be consistent with pertinent requirements of 10CFR71.

l l

l Page 36 of 84

7 1 .,

L Operatiorl Qur.lity Assurnce Pl:n Revision 19 i

16.0 Inspection, Test and Operating Status

,, 16.1. GeneralRequirements l

1. Measures shall be established to indicate, by the use of markings such as stamps, tags,  ;

labels, routing cards, or other suitable means, the status ofinspections and tests i performed upon individual items of the nuclear plant. These measures shall provide for the identification ofitems which have satisfactorily passed required inspections and i tests, where necessary to preclude inadvertent bypassing of such inspections and tests.

2. Measures shall also be established for indicating the operating status of structures, systems and components of the nuclear power plant, such as by tagging valves and switches to prevent inadvertent operation.

16.2 Maintenance Control i

1. Measures shall be established for the control of maintenance to safety related and fire protection related structures, systems and components that assure that:

a. Affected structures, systems and components are removed from service and I secured in a manner consistent with operability and isolation requirements of the Technical Specifications.

b. Repair and modification activities are performed in a manner consistent with its 1 importance to safety. )

c. Upon completion of repairs and modifications the affected structures, systems  :

, and components are inspected and tested to detennine that the required work j was performed satisfactorily and that they will perform their safety function in the required manner.

2. In addition, measures shall be established to control maintenance activities that assure resulting radiation exposure to personnel is maintained as low as reasonably achievable (ALARA) and consistent with pertinent NRC regulations.

)

3. The above measures shall be implemented by utilizing appropriate work authorization processes, work procedures, safety tagging, bypass control, key control and area posting, as appropriate, for the involved activity.

16.3 Test Control

1. Measures shall be established for the control of tests to safety related and fire protection related structures, systems and components that assures that:  ;

i

a. Proposed tests are reviewed and approved as required prior to performance.

Page 37 of 84

..~ ,

Operational Qu'ality Assurance Plan

. Revision 19

. b. The plant is placed in an acceptable status prior to the test, maintained in an -

acceptable status during the test, and returned to its normal status upon 1 J

- completion of the test.

- q

c. Test results are reviewed and approved as appropriate. j

2. The above measures shall be implemented by utilizing appropriate work authorization processes, test procedures, safety tagging, bypass control, and key control, as j '

appropriate, for the involved test.

16.4 Safety Tagging .

A safety tagging program shall be developed and utilized for control of nuclear plant  !

equipment. This program shall contain provisions for uniquely identifying components whose operation is restricted or prohibited based upon safety considerations. Provisions shall be y t

made for review, application, independent verification, removal, and documentation of such -

tagging.

16.5 Key Control Measures shall be established for controlling keys for safety related and fire protection related j switches or key devices important to plant security. These measures shall include restricted

• distributiontnd periodic inventory of such keys or key devices.

16.6 Bypass Control

1. Measures shall be established for controlling the application of devices utilized to f bypass component functions that are important to safety. Such measures shall assure that: ,

i

a. Proposed bypasses to safety related and fire protection related items are ,

reviewed to determine that the plant will be placed in an acceptable status l when the bypass is applied.  !

b. Applied bypasses are independently verified. .f

c. Removal of bypasses from safety related and fire protection related items are  ;

reviewed prior to removal.  ;

d. Application of bypasses to safety related and fire protection related items is j authorized by responsible personnel.  ;

l l

Page 38 of 84

r: y

^

Operati:nr1 Qurlity Assurance PI:n Revision 19

2. The application of safety related and Sre protection related bypasses shall be considered a temporary measure and shall be reviewed periodically.

3. All required activities associated with the application, review, approval and removal shall be documented.

16.7 R'adioactive Material Control Inspection, test, and operating status of equipment and components associated with shipment of radioactive material shall be established based upon the following criteria:

1. Inspection, test, and operating status of packages for radioactive material shall be indicated and controlled by established procedures.

2. Status shall be indicated by tag, label, marking or log entry.

3. Status of non-conforming parts or packages shall be positively maintained by established procedures.

16.8 Reactor Startup and Restart Control Measures shall be established for controlling reactor startups and restans. Such measures shall assure that safety related systems, components and structures have been placed in the required status and reviews have been completed to assure that the cause of any reactor trip (scram) has been investigated and satisfactorily resolved.

Page 39 of 84 -

. \

Operational Quality Assurance Plan  ;

Revision 19 I

17.0 Nonconforming Materials, Parts or Components i

17.1 General Requirements

1. Measures shall be established to control materials, parts, or components which do not conform to requirements in order to prevent their inadvertent use or installation.

These measures shall include, as appropriate, procedures for identification, documentation, segregation, disposition and notification to affected organizations.

2. Nonconformance items shall be reviewed and accepted, rejected, repaired, or reworked in accordance with documented procedures.

i 17.2 ReceiptInspection

1. Measures shall be established which assure that safety related and fire protection '

related material, supplies, equipment, and components are inspected to determine that they conform to specified requirements of pertinent procurement documents upon receipt at the site. The absence of required documentation or discrepant documentation shall constitute nonconformance. l

2. Provisions shall be made for identifying nonconforming items and for segregation of nonconforming items. Nonconforming items shall not be used to fulfill a safety related and fire protection related function until the discrepancy is satisfactorily resolved.

17.3 Maintenance Inspection Equipment, components or parts found nonconforming in a manner that could significantly affect its ability to fulfill its safety related and fire protection related function shall be identified  !

as a nonconforming item and shall be segregated or otherwise controlled to prevent g l i

inadvertent use or installation when physical segregation is not practical. Nonconforming items shall not be used until the discrepancy is satisfactorily resolved. '

17.4 Disposition of N'onconforming Items t

1. Measures shall be established which assure that nonconforming items are disposed of in a manner which prohibits their inadvertent use or installation. Provisions shall be made for reviewing the nonconformance and correcting discrepancies by repair or 1

rework if appropriate.

i

2. The acceptability of such rework or repair of materials, parts, components, systems, l

and structures shall be verified by reinspection and retesting the item as originally I

inspected and tested or by a method which is equivalent to the original inspection and testing method. Inspection, testing, rework, and repair procedures shall be documented.

Page 40 of 84 t

. \

s. ., 1

!- Operational Qu:lity Ass:r=ce Plas .

Revision 19

3. Normally, nonconforming safety related and fire protection related items shall not be j installed prior to satisfactory resolution of outstanding discrepancies. In exceptional cases nonconforming items may be installed provided specific action is taken, which j assures the item is not utilized to fulfill a safety function, prior to resolution of the  ;

discrepancy.. j 17.5 Nonconformance Documentation  !

1. Nonconformance reports shall be initiated for significant deviations from specified  !

requirements. Such reports shall identify the nonconforming item, describe the  !

nonconformance, the disposition of the nonconformance, and the inspection -

requirements. Nonconformances shall be reviewed and approved.

2. Nonconformance reports shall be periodically analyzed to show quality trends and the  !

results of this review shall be reported to the appropriate level of management for review and assessment. ,

17.6 Reporting  ;

. Measures shall be established which assure that defects as defined in 10CFR21 and failures to comply with the Atomic Energy Act of 1954, as amended, or any applicable rule, regulation, ^

order or license of the NRC relating to a substantial safety hazard are reported in accordance with the applicable requirements of 10CFR21.

t i

i I

Page 41 of 84 J

4.- ,

Y

~ Operational Quality Assurance Plan Revision 19 18.0. Corrective Action

,.18.1 General Requirements l

1. Measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, discrepancies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected. In the case of significant  :

conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective action taken to preclude recurrence.

2. The identification of the condition adverse to quality, the cause of the condition, and  !

the corrective action taken shall be documented and reported to appropriate levels of  !

management.

18.2 Operating Occurrences and Events  :

Measures shall be established which assure that operating occurrences and events that could have a significant safety effect are investigated, reviewed, and reported as required by the l' Technical Specifications. Such measures shall assure that appropriate corrective action is taken and that the event or occurrence is reported to responsible levels of management. -

Corrective action includes provisions which preclude recurrence. j 18.3 Adtninistrative ControlDiscrepancies l Measures shall be established which assure that significant discrepancies identified durmg ,

quality assurance program audits are reported to those responsible for the activity and to  !

appropriate levels of management. These measures shall include corrective action designed to  :

preclude recurrence of the discrepancies identified and verification ofimplementation. l i

-i i

)

I J

l l

i Page 42 of 84 i

k, q f .Operati=1 Q ality Assur:nce Plan Revision 19 19.0 Quality Assurance Records

_,, 19.1 General Requirements

1. Sufficient records shall be maintained to furnish evidence of activities affecting quality.

These records shall include at least the following:

a. Operating logs and the results of reviews, inspections, tests, audits, monitoring of work performance and material analysis.

b. The records shall also include closely related data such as qualifications of -

personnel, procedures, and equipment.

c. Inspection and test records shall, as a minimum, identify the inspector or data recorder, the type of observation, the results, the acceptability, and the action taken in connection with any deficiencies noted.

2. Records shall be identifiable and retrievable.

3. Requirements shall be established concerning record retention, such as duration, location, and assigned responsibility which are consistent with applicable regulatory requirements.

19.2 Operating Records Measures shall be established which assure that records as they apply to plant operation are generated and retained as required by the Technical Specifications or other regulatory requirements.

19.3 Plant Modification Records Measures shall be established which assure that adequate records are generated and retained to reconstruct plant modifications that are safety related or fire protection related.

19.4 Plant Maintenance Records Measures shall be established which assure that records pertaining to maintenance ofplant safety related and fire protection related structures, equipment and components are generated and retained.

19.5 Personnel Qualification Records i

Measures shall be established which assure personnel qualification records are generated and retained. )

Page 43 of 84  !

I

I

, Operational Quality Assurance Plan Revision 19 19.6 Procurernent Records Measures shall be established which assure that safety related, fire protection related, or 10CFR71 related procurement documents and associated documents are generated and retained.

19.7 Surveillance Test Records Measures shall be established which assure that records associated with Surveillance Testing, including Inservice Inspections, are generated and retained.

19.8 Audit Reports Measures shall be established which assure records pertaining to audits of quality activities are generated and retained.

19.9 Radioactive Material Control Measures shall be established which assure that records associated with radioactive material control are generated and maintained.

19.10 Drawings, Measures shall be established which assure that records of drawing changes made to plant safety related and fire protection related stmetures, equipment and components are generated and retained.

19.11 Records Management

1. Records management systems shall be established which assure that the required records are collected, stored, and maintained in accordance with ANSI N45.2.9-1974.

Such records shall at least be stored in insulated filing devices (rated 350-1 hour by UL as to fire resistance only) located in areas having combustible loading ofless than 5 lb/sq ft, or duplicate records shall be maintained in remote locations. Specific records shall be identified in implementing or source documents. Identification shall indicate records required by Technical Specifications, committed to standards, and other regulatory documents.

2. Records management systems shall be established which assure that those records used to demonstrate program implementation are collected, stored, and maintained in i accordance with good records management practices. Such systems shall assure that l these records are made available to auditors and inspectors in a timely manner.

Page 44 of 84  ;

r 5 .,

- Operation! Qrlity Assur

nce Pirn Revision 19 i

-20.0 - Audits '

, 20.1 General Requirements  !

A comprehensive system of planned and periodic audits shall be carried out to verify j compliance with all aspects of the Operational Quality Assurance Program and to determine the effectiveness of the program. The audits shall be performed in accordance with written >

procedures or checklists by appropriately trained personnel not having direct responsibility in  :

the areas being audited. Audit results shall be documented and reviewed by management .

having responsibility in the area audited. Follow-up action, including re-audit of discrepant  !

areas, shall be taken where indicated. I 20.2 Required Audits j; Measures shall be established which assure that the provisions of the Operational Quality  :

Assurance Program are audited periodically. In addition, an overall audit shall be performed periodically which determines the adequacy of the program with respect to requirements contained in the Operational Quality Assurance Plan. This overall audit shall be performed by an organization other than that responsible for administration or implementation of the program.

20.3 Audit Schedules '

f

1. Required audits shall be performed each year except that this time period may be j extended to not more than two years provided such extensions arejustified based upon past experience. Special audits may be scheduled on the initiative of Generation Quality Services personnel based upon suspected or known discrepancies or as

" i directed by management. .

e

2. Appropriate audit schedules shall be prepared each year.  !

20.4 Audit Procedures Required audits shall be performed in accordance with appropriate audit procedures.  ;

Checklists may be used as audit procedures or in conjunction with audit procedures. j Procedures shall include auditing requirements at various levels of the Operational Quality .

Assurance Program. {

20.5 Audit Reports i i

1. Reports of the results of each audit shall be prepared. These reports shtllinclude a l description of the area audited, identification ofindividuals responsible for  ;

implementation of the audited provisions and for performance of the audit, l identification of discrepant areas, and recommended corrective action as appropriate.  !

. i Page 45 of 84  ;

i a

j , .

Operational Quality Assurance Plan Revision 19

2. Audit reports shall be distributed to the appropriate management level and to those individuals responsible for implementation of audited provisions.

3. Audit reports and associated nonconformance reports shall be periodically analyzed for quality trends and the results reported to the appropriate level ofmanagement for review and assessment.

20.6 Corrective Action Measures shall be established which assure that discrepancies identified by audits or other means are resolved. These measures shall include notification of the manager responsible for the discrepancy,' recommended corrective action, and verification of satisfactory resolution.-

Discrepancies shall be resolved by the manager responsible for the discrepancy. Line management shall resolve disputed discrepancies.

l l

Page 46 of 84

g-i; Operatio:al Quality Ass rance Plan -

Revision 19. Appendix A APPENDIX A Monticello Structures, Systems, and Components Subject to Appendix B of10CFR50

1. STRUCTURES Reactor Building Plant Control and Cable Spreading Structure Off Gas Stack Intake Structure (Service Water pump area)

Diesel Generator Building Diesel Fuel OilDay Tank Rooms Turbine Building (parts which house, support and/or protect safety related equipment)

Off Gas Compressor and Storage Building (parts which house, support and/or protect safety related equipment)

Emergency Filtration Train (EFT) Building

2. MECHANICAL SYSTEMS AND COMPONENTS '

2.1 Reactor Coolant System Reactor Vessel Reactor Vessel Support Skirt Reactor Vessel Stabilizer  ;

Recirculation System Piping Recirculation System Pumps and Valves l Main Steam Piping (to and including outennost containment isolation valve)

Main Steam Safety ReliefValves l Main Steam Safety Relief Valve Discharge Piping Feedwater Piping (to and including outermost containment isolation valve)

Control Rod Drive Housing Supports 2.2 Reactor VesselInternals l Fuel Assemblies Core Support Structure Jet Pumps Control Rods Liquid Poison Pipe Core Spray Sparger ,

4 Page 47 of 84

x

[

i I

Operational Quality Assurance Plan  !

Revision 19. Appendix A  !

2.3 Control Rod Drive System  ;

ControlRod Drives ,

.ControlRod Drives Accumulators ,

' Scram Discharge Volume Scram Piping [

'2 4

. Standby Liquid Control System i

SLC Tank ,

SLC Pumps  ;

SLC Explosive Valves ,

SLC Piping 2.5 Primary Containment .

Drywell Torus  ;

. Drywell Vent Piping / Vacuum Breakers Torus Ring Header and Downcomers 1 i

Containment Penetrations Containment Piping and Valves (to and including outermost isolation valve) ,

2.6 Secondary Containment RB Ventilation Isolation Dampers .

Standby Gas Treatment Filters and Fans ,

-l 4

2.7 ResidualHeat Removal System RHR Piping, Pumps and Valves .

RHR Heat Exchangers (shell side) l t

2.8 Core Spray System l i

Core Spray Piping, Pumps, and Valves j i

)

i Page 48 of 84

r

.. r. ,

4 Operatirnal Q=lity Assurezce PI:n Revision 19 Appendix A 2.9 High Pressure Coolant Injection System HPCI Steam Piping and Valves Inside Containment (to and including outermost isolation valve)

HPCI Steam Supply and Exhaust Piping and Valves (outside containment)-

HPCI Pump-Turbine HPCIInjection Piping and Valves HPCI Suction Piping 2.10 Reactor Core Isolation Cooling System RCIC Steam Piping and Valves Inside Containment (to and including outermost isolation valve) ,

RCIC Steam Supply and Exhaust Piping and Valves (outside containment)

RCIC Pump-Turbine , ;

RCIC Injection Piping and Valves  !

RCIC Suction Piping  !

2.11 Service Water System l Emergency Service Water Pumps Emergency Service Water Piping and Valves l RHR, Service Water Pumps l RHR Heat Exchanger (tube side) .

RHR Service Water Piping and Valves ,

EFT Emergency Service Water Pumps, Piping, and Valves '

2.12 Reactor Water Cleanup System ,

i RWCU Piping and Valves (to and including outermost isolation valve) l 2,13 Spent Fuel Storage Systems Spent Fuel Pool i l

2.14 Diesel Generator Support System  :

Air Start System from Receivers to Air Start Solenoids Fuel Oil System from Day Tank to Injectors  !

Diesel Coolers and Associated Piping and Valves (water side)

Diesel Fuel Oil  ;

Page 49 of 84 l

i

, ,5 .

Operational Quality Assurance Plan Revision 19 Appendix A 2.15 Heating and Ventilating System I ' Emergency Filtration Train (EFT) for Control Room and EFT Building Combustible Gas Control System SECTION 2 NOTES:

1. Mechanical components included within each mechanical system include hangers .

(up to and including the first anchor supporting a safety related section of piping), j i fittings, flanges, vessels, tanks, etc. as necessary to perform the system safety functions.

l.

1

3. ELECTRICAL SYSTEMS AND COMPONENTS 3.1 4160 Volt Bus 16 Breaker 152-602, 601, 609, 610, Feed Breaker 408 l '

!' RHR Service Water Pump B Motor RHR Service Water Pump D Motor ,

RHR Pump B Motor  :'

RHR Pump D Motor Core Spray Pump B Motor )

480 Volt Load Center 104 No.12 CRD Pump Feed Breaker 152-606 3.2 4160 Volt Bus 15

! Breaker 152-502, 501, 509, 511, Feed Breaker 308 RHR Service Water Pump A Motor RHR Service Water Pump C Motor RHR Pump A Motor RHR Pump C Motor Core Spray Pump A Motor 480 Volt Load Center 103 No.11 CRD Pump Feed Breaker 152-506 3.3 480 Volt Switchgear Load Center 104 480 V MCC 142 (1)(Essential) 480 V MCC 143A (1) i 480 V MCC 143B (1) 480 V MCC 144 (1) {

Page 50 of 84

r: - 1

._,, p.

.t. . Operatioral Quility Assurace PI:n i Revision L9 Appendix A~  ?

3.4 480 Volt Switchgear Load Center 103 480 V MCC 133A (1) l 480 V MCC 133B - (1)'  !

480 V.MCC 134 (1)

• 3,5 Diesel Generator No. I1 (1) 3.6 DieselGeneratorNo,12 (1) 3.7 250 V DC (Division 1) Distribution Panel D31 (1) 3.8 250 V DC (Division 2) Distribution Panel D100 (1).

i

, 3.9 125 V DC Distribution Panel D-11 (1) i 3.10 125 V DC Distribution Panel D-21 -(1)  :

3.11 120/240 Volt AC Instrumentation Distribution Panel (1) l T

SECTION 3 NOTES:

1. . For those electrical systems or components designated with the Note (1) above, quality assurance electrical program requirements are applicable only to those portions of systems as defmed in Section 2 as necessary to perform the system  !

safety function.  !

2. Electrical components included within each electrical system include power source, -

breaker, control circuit, cable, relaying and operating device (motor, solenoid, -l heater, relay, etc.) as necessary to perfonn the system safety function. [

f

3. Certain components are excluded from the quality assurance program requirements if they meet the criteria described in Section 5. i I

Page 51 of 84

Operational Quality Assurance Plan  ;

I Revision 19 Appendix A

4. ~ INSTRUMENTATION SYSTEMS AND COMPONENTS 1

,, 4.1 Reactor Protection System

'4.2 ' Primary Containment Isolation System ,

'4.3 High Pressure Coolant Injection System Initiation and' Isolation 4.4 Reactor Core Isolation Cooling System Initiation and Isolation 4.5 ' Core Spray System Initiation 4.6 Low Pressure Coolant Injection System Initiation 4.7 Automatic Blowdown System 4.8 Neutron Monitoring System (IRM and APRM)

. 4.9 Standby Gas Treatment System Initiation 4.10 SJAE Off Gas Radiation Monitor 4.11 EFT System Initiation and Operation 4.12 Combustible Gas Control System SECTION 4 NOTES:

f

1. For those instrumentation systems designated above, quality assurance l instrumentation program requirements are applicable only to those portions of  !

systems defmed in Section 2 as necessary to perform the system safety function.

2. Instrumentation components included within each instrumentation system include  !

power supply, sensors, relays, wiring and final operating device (solenoid, relay, etc.) as necessary to perform the system safety fbnction.  ;

3. Certain components are excluded from the quality assurance program requirements if they meet the criteria described in Section 5.  !

i Page 52 of 84

r

• . a, ,

t . Operatin:ci Qudity Assurence Pirn Revision 19 Appendix A

5. ELECTRICAL AND INSTRUMENTATION SYSTEM COMPONENT EXCLUSION CAITERIA 5.1 Any component of an electrical system in Section 3 or instrumentation system in Section 4 is excluded from the quality assurance program requirements ifit meets the following criteria:

a. A failure of the component by electrical shorting, open circuiting, grounding or mechanical failure would not render the system incapable of performing its intended safety function.

b. A failure of the fluid pressure boundary of the component would not render the system incapable ofperforming its intended safety function.

5.2 Small spare parts having no traceability, such as commercial off-the-shelfitems, may be purchased as nonsafety-related and then qualified for use in equipment requiring quality assurance. Examples of such items are resistors, capacitors, switches, indicators, coils, wire, connectors, solid state devices and miscellaneous hardware.

I i

i j

l

)

Page 53 of 84  !

p

.) ,'

I Operational Quality Assurance Plan Revision 19 Appendix A

[This page intentionally blank]

l l

i l

Page 54 of 84

f .g. ..

t T. ' '

Operatinal Q:ality Assurc ce Plat Revision 19 Appendix B j APPENDIX B Prairie Island Structures, Systems, and Components Subject to Appendix B of 10CFR50 l

1. REACTOR SYSTEM AND FUEL .

l 1.1 Reactor Vessel and Coolant System Reactor vesre' l Reactor ve G support  :

Reactor vesselinternals l Full length control rod drive mechanism housing j Part length control rod drive mechanism housing l Steam generator (tube side and shell side) l Pressurizer, including instrumentation, piping, and components  !

Reactor coolant hot and cold leg piping, fittings  !

Surge pipe, fittings l Loop bypass line  !

Temperature detector bypass manifold Reactor coolant thermowell Reaotor coolant thermowell boss i Safety valves Reliefvalves j Reactor coolant system boundary valves .

Control rod drive mechanism head adapter plugs  !

Reactor coolant pump Pump casing Main flanges Thermal barrier

- Seal housing

- Pressure retaining bolting l Reactor coolant pump motor l

• Shaft coupling

}

Flywheel ,

Reactor coolant pump internals l RCC thimble plug (rod control clusters)  ;

Primary and secondary sources i Electric modules with safety function j Cable with safety function j Page 55 of 84 1

1

. Operational Quality' Assurance Plan ,

Revision 19 Appendix B -

1.2 Fuel Assemblies  !

Fuel assemblies, sub-assemblies, components and materials, including fuel material li

-2. REACTIVITY CONTROL SYSTEMS Drive mechanisms including: {

+ Control rod cluster drive shaft assembly, including latch assembly i

- Reactor trip breakers l Control rods and rod cluster assemblies

- Control rod guide tube r a Control rod drive housing l

- Electric modules with safety function

- Cable with safety function  ;

i

3. CHEMICAL AND VOI.UME CONTROL SYSTEM i

Regenerative heat exchanger 1 Letdown heat exchanger  :

Reactor coolant filter  !

Volume control tank Positive displacement charging pump and motor  ;

Seal water filter -  :

Letdown orifices and letdown valves t l Excess letdown heat exchanger l Seal water heat exchanger  ;

Boric acid tanks '!

Boric acid transfer pump t Boric acid filter l Reactor coolant pump seal and bypass orifice l Piping, inboard ofisolation valves  !

Electric modules with safety function l Cable with safety function Heat tracing  !

l

4. INCORE INSTRUMENTATION Thimble guide tubes }

Seal table  !

i  :

5. BORON RECYCLE SYSTEM ,

i Recycle holdup tanks, piping and valves associated with gaseous radioactive waste l l

l t

Page 56 of 84 +

i

+

o -

, , . v:;. .

,[_ 4 g-Operational Quality Assurance Plan  :

~ Revision 19 Appendix B  ;

6. - EMERGENCY CORE COOLING SYSTEM j

,, Accumulators f High head safetyinjection pumps Piping, inboard ofisolation valves ,

Motors, electric modules, with safety function l Cable with safety function j

7. CONTAINMENT SPRAY SYSTEM j Refueling water storage tank i Spray additive tank Spray pumps  ;

Spray rings and nozzles  !

Piping and valves  :

Pump motors  :

Electric modules with safety function l Cable with safety function j

8. RESIDUAL HEAT REMOVAL SYSTEM i

'1 Pumps and motors l Heat

• exchanger -[

Piping and valves with safety function  !

Electric modules with safety function j Cable with safety function j

9. SPENT FUEL POOL COOLING SYSTEM  !

Piping and valves whose failure could result in significant release of pool water l

10. CONTAINMENT FAN COOLER SYSTEM Ductwork Fans I Dampers .

Fan coolers Electric modules with safety function  !

l Cable with safety function I

l Page 57 of 84

3 Operational Quality Assurance Plan Revision 19 Appendix B

11. WASTE PROCESSING SYSTEM

,.. Gaseous and liquid waste piping and valves forming part of containment boundary Systems handling gaseous radioactive materials Electric modules with safety function Cable with safety function .

1 NOTE: The Waste Gas Disposal System shall be maintained in accordance with the guidance established in Regulatory Guide 1.143, Revision 1, October 1979. l 18

12. SAMPLING SYSTEMS l Valves and piping from the reactor coolant system up to the second isolation valve outside containment Valves and piping to the first isolation valve from other safety related systems

13. STEAM GENERATOR BLOWDOWN Piping from steam generator to containment isolation valves

14. REACTOR PROTECTION SYSTEM Electrical modules Cable

15. PROCESS RADIATION MONITORS Radiation Monitors, including electric modules and cable with a safety function, associated with the Shield Building, Auxiliary Building, Spent Fuel Pool and Control Room Ventilation Systems

16. CONTAINhENT HYDROGEN CONTROL SYSTEM Piping and valves with safety function Electric modules and cable

17. REACTOR VESSEL SERVICE EQUIPMENT Containment polar crane t

Vessel head handling equipment Crane structural supports f

Crane electrical, cable, controls and instrumentation with safety function i

Page 58 of 84

.1 Operational' Quality Assurence Pirn  !

Revision 19 Appendix B ,

18. REFUELING EQUIPMENT l Spent fuel cask I Auxiliary Building crane Auxiliary Building crane structural supports i Crane electrical, cable controls and instmmentation with safety function i Fuel transfer tube l Spent Fuel Bridge Crane Manipulator Crane 19, FUEL STORAGE j New fuel racks l Spent fuel racks  !

Spent fuel pool structure and enclosure l Spent fuel storage casks l Independent spent fuel storage installation concrete pads l

20. CONTROL ROOM PANELS ,

i Electric modules, with safety function l Cable with safety function l

21. LOCALPANELS ANDRACKS l t

Electric modules with safety function Cable with safety function

22. MAIN STEAM SYSTEM Main steam piping and valves from steam generators up to and including piping restraints  !

downstream of the main steam isolation valves -

Main steam piping and valves from main steam lines to auxiliary feedwater pump turbine l Steam line flow restrictor Safety and relief valves l Piping to first isolation valves and safety and relief valve discharge  ;

Electric modules with safety function  :

Cable with safety function  !

1

23. FEEDWATER SYSTEM Feedwater piping and valves inside containment structure up to and including first isolation valve outside containment structure

]

Electric modules with safety function Cable with safety function Page 59 of 84

Operational Quality Assurance Plan Revision 19 Appendix B

24. AUXILIARY FEEDWATER SYSTEM l

l

,, Piping and valves supplying auxiliary feedwater from and including containment isolation valves to connections with feedwater lines Auxiliary feedwater pumps (turbine and motor-driven)

Piping and valves supplying auxiliary feedwater from the cooling water system Electric modules with safety function Cable with safety function

25. COOLING WATER SYSTEMS Component cooling water systems (essential)

- Piping (except to turbine building and non-essential equipment)

- Heat exchangers, with safety function Pumps Pump motors

. Surge tank

. Valves, isolation

- Valves, other, with safety function f

I . Electric modules with safety function

. Cable with safety function Cooling water systems (essential)

- Piping (except to turbine building and non-essential equipment)

. Diesel engine pumps

- Strainers, with safety function

. Valves, isolation Valves, other, with safety function Screen wash systems, with safety function l Traveling screens, with safety function Electric modules with safety function Cable with safety function Diesel engine pump auxiliaries as follows:

- Diesel oil storage tanks

. Day tanks

. Fuel oil transfer pumps and motors

. Fuel oil piping and valves with a safety function

. Staning air compressors Air receivers

. Staning air piping and valves with a safety function

- Cooling water piping and valves with a safety function

. Electric modules with safety function

- Cable with safety function

. Diesel engine, lubricating oil and jacket cooling systems Diesel fuel oil Page 60 of 84

. . ~ . .

j je" ^

l

.j

[~ ~

. Operational Quality Assurance Plan Revision 19 Appendix B -

y

26. ' INSTRUMENT AIR SYSTEM  !

-i.

Piping and valves associated with containment penetration .

'l

. 27. DIESEL GENERATOR (D1, D2, DS, D6) _

Diesel oil storage tanks Day tanks ,

Pumps and motors, fuel oil transfer Diesel filter j Valves, with safety function  ;

Piping /Suppons except vent and fill piping downstream oflast valve }

Cooling water system pipe and valves [

Diesel generatorjacket cooling water system components with a safety function .

Diesel generator lubricating oil system components with a safety function  :

Air intake and exhaust, and components with a safety function >

Electric modules with safety function Cable with safety function Diesel fuel oil f

28. DIESEL GENERATOR AIR STARTING SYSTEM (D1, D2, D5, D6) l i

Compressor (D1 and D2 only)

Air receivers  !

Piping / Supports and valves from receiver to diesel generator Piping between compressor and receiver (D1 and D2 only) i f

I I

Page 61 of'84

Operational Quality Assurance Plan Revision 19? Appendix B l 29.- ELECTRICAL SYSTEMS  :

,, Switchgear, transformers, motor control centers, load centers, batteries and chargers, and l associated equipment with safety function  !

i NOTE: Point ofinterface with onsite electric power systems (i.e., at point ofinterface .

with Class IE breakers which isolate main Class 1E onsite buses from the offsite power system; and including components and circuitry interfaces that .  ;

affect the proper performance of such interfacing breaker).-

4,160 - 480 V switchgear from engineered safety systems (ESF), including ESF buses 4,160 - 480 V transformers (ESF load centers) [

480 - 120/208 V eansformers (control room and ESF area emergency lighting)  ;

480 V switchgear (ESF load centers) {

480 V motor control and motor control centers 125 V station batteries and racks (control and vital instrumentation power supplies) 125 V de panels and switchgear (vital de power distribution) 120 V ac instrument bus panels (vital instrumentation ac power distribution)  !

Containment penetration assemblies -

Main control board Radiation monitor panel ,

Hot shutdown panel Control

• room air conditioning control panel Post LOCA Hydrogen control panel Emergency lighting Emergency communications Diesel generator and accessories Diesel generator control panels Relay boards and racks Wire and cable raceway system Underground electrical duct bank system Cable system (power, control and instrumentation)

Instrument racks Electrical supports Heat tracing / freeze protection

30. INSTRUMENTATION AND CONTROL SYSTEM COMPONENTS Reactor trip system i Engineered safety features (ESF) actuation system Systems required for safe shutdown  :

Safety related instruments, tubing and fittings Page 62 of 84 l

Operational Quality Assurance Plan Revision 19 Appendix B

31. HEATING, VENTILATION AND AIR CONDITIONING SYSTEMS (HVAC)

,, Control and Relay Room HVAC System Air handling units Fans, ductwork and dampers Filters Chillers and chilled water pumps Auxiliary Building Special Ventilation System Fans, ductwork and dampers Filters Screenhouse Ventilation System Fans and dampers associated with diesel engine ventilation Shield Building Ventilation System Fans, ductwork and dampers Filters Battery Room Special Ventilation System Fans, ductwork and dampers Spent Fuel Pool Special Ventilation System Exhaust fans, ductwork, dampers Exhaust filters DI/D2 Diesel Generator Rooms Cooling System Fans, ductwork and dampers Auxihary Building Normal Ventilation System Ductwork and dampers associated with steam exclusion Turbine Building Ventilation System Ductwork and dampers associated with steam exclusion D5/D6 Building Heating, Ventilation, Cooling and Exhaust Systems with safety functions Electric modules with safety function Cable with safety function i HVAC sensors and monitors having safety function j Page 63 of 84

w_

4 ',0 J

^:

Operational Quality Assurance Plan  ;

Revision 19 Appendix B ~

32. CIVIL STRUCTURES AND FOUNDATIONS q

- Containment and stmetures Containment airlocks Containment isolation (valves, piping, canisters)  !

Containment penetrations l

~ Shield building .!

Auxiliary building l Control room ,

Diesel generator room (D1 and D2)

Radwaste building i Cooling water intake structure Electrical tunnels, with safety function .

Pipe tunnels, with safety function j Shielding structures ,

Turbine Building (housing emergency diesel generator, cooling water pipes, batteries, ,

safeguards switchgear, auxiliary feedwater pumps)

D5/D6 Building

33. OTHER A. Fire protection system piping associated with the safeguards ventilation exhaust filters and containment penetration B. Turbine building crane f Crane structural suppon '

l Crane electrical, cable, controls and instrumentation with safety function l

1 l

Page 64 of 84

7

'. l, t Operati=al Q=lity Ass:rance Plan Revision 19 Appendix C

)

APPENDIX C Nuclear Plant Fire Protection Program ~

I 1.0 Policy Statement 1

Northern States Power Company (NSP) has established a system of Administrative ]

Control Directives (ACDs) that implement the Operational Quality Assurance Plan. This l' system shall be used to implement the requirements of the operating nuclear power plant fire protection program. The basic requirements of the fire protection program are i specified in this appendix to the Operational Quality Assurance Plan.

2.0 Organization j

)

2.1 General Requirements l e

1. NSP shall be responsible for the establishment and implementation of the fire protection program. NSP may delegate to other organizations the work of i establishing and implementing the fire protection program, or any part thereof, but shall retain responsibility for the program. 1 2

• The authority and duties of persons and organizations involved in the fire protection program shall be clearly established and delineated in writing.

3. To assure adherence to the fire protection program, management measures shall be established which provide that the individual or group assigned the responsibility for checking, auditing, inspecting, or otherwise verifying that an activity has been correctly performed is qualified and does not have responsibility for performing or directly supervising the work except that:

l

a. The individual or group assigned the responsibility for auditing is 4 independent of the individual or group directly responsible for performing the specific activity.

9 9

1 Page 65 of 84

.e 4 a Operational Quality Assurance Pirn Revision 19 Appendix C 2.2 Fire Protection Organization Summary The NSP organization is summarized in Section 3.0 of the Operational Quality Assurance Plan. In addition to that summary, the following additional responsibilities shall pertain to the fire protection program.

1. Director Generation Quality Services l6

a. Scheduling and assuring completion ofindependent off-site fire protection '

inspections and audits.

7

2. Monticello and Prairie Island Plant Managers 19

a. Routine inspection of the plant for fire hazards. ,

b. Establishing plant fire brigades.

c. Ensuring that fire brigade members receive required training and physical evaluations,

d. Coordinating fire drills and determining their effectiveness.

p. Establishing cooperation with the local fire department, including joint drills and training sessions to familiarize fire department personnel with plant access routes, layout, equipment, and special hazards.

f. Establishing storage requirements to insure no additional fire hazards are created.

g. Establishing a surveillarce program for fire protection systems and fire fighting equipment.

h. Establishing a system to control nonconforming items.

i. Reviewing required work processes for fire hazards and possible reduction of fire protection system effectiveness.

j. Reviewing modifications to determine if they would cause an unreviewed fire hazard or reduce the effectiveness of the fire protection systems.

k. Establishing a fire salvage program (when required).

1. Reviewing purchase requisitions that are related to fire protection.

Page 66 of 84

F ,. .

v, .  !

s.

'l

[ ti Operatiral Qsality Ass:rance Pirn Revision 19 Appendix C e

m. Developing instructions for fighting fires in specific areas and identifying  !

effects offires in specific areas. j I

" Preparing news release information for NSP's Communications

. n. j Department. t

o. Procurement of equipment for the fire brigades'.  !

~7  ;

p. Establishing a policy for the security actions to be taken by the guard force

. during a fire.  !

f

3. Manager Nuclear Training (Monticello and Prairie Island) 'l19  ;

i

a. Establishing a training program for the fire brigades. '[

2.3 Fire Protection Engineer

1. A fire protection engineer (or engineering consultant) shall be used to provide the i following types of services: i

a. Review of design for a significant modification to a fire protection system.  !

, b. Review of proposed plant modifications which would introduce major j hazards not analyzed in the Fire Hazards Analysis.

~

i

c. Triennial independent fire protection inspections (see Section 14.2).

]

2. The fire protection engineer (or engineering consultant) shall' meet the following -

qualificationsi A graduate of an engineering curriculum of accepted standing who has . i a.

completed not less than six years of engineering attainment indicative of growth in engineering competency and achievement, three ofwhich shall have been in responsible charge of fire protection engineering work, .or

b. A member in the Society ofFire Protection Engineers.

1 i

Page 67 of'84

y- ,

' Operational Quality Assurance Plan l Revision 19 Appendix C .i i

3.0 ' Nuclear Plant Fire Brigades

, 3.1 Monticello

1. - A fire brigade shall be established in accordance with the requirements of  !

10CFR50, Appendix R, Section III.H, and the requirements listed below: l

a. Fire brigade composition may be less than the minimum requirements for a pedod of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate the  :

unexpected absence of fire brigade members. Under this circumstance,  ;

immediate action shall be taken to restore the fire brigade to within the minimum requirements.

3.2 Prairie Island ,

1. A fire brigade of five persons shall be on-site at all times in addition to the  !

minimum shift crew complement needed to safely shut down the unit (s).

f

a. Fire brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate the >

unexpected absence of fire brigade membeu. Under this circumstance immediate action shall be taken to restore the fire brigade to within the

. minimum requirements.

2. Each fire brigade shall have an appointed leader. This leader shall not be the Shift 'l Supervisor (the Unit No.1 Shift Supervisor at Prairie Island).  ;

i

3. All new members of the fire brigades shall have an initial physical examination for strenuous physical activity as experienced in fire fighting. Annual follow-up  ;

physical examinations shall include respiratory protection qualification testing which screens all respirator users (including fire brigade members) for cardiopulmonary deficiencies. Physical examinations shall be conducted by a  :

physician. A program shall be established by NSP's corporate physician to ensure .

that all respirator users, when subject to even the most severe working conditions, i are physically fit to wear a respirator. The program shall include pulse, blood l pressure, and spirometry testing, and a medical history review in which the possibility of past or present heart disease is determined. The program shall be .

administered by nursing personnel who will perform the necessary cardiopulmonary screening function.

i 1

i Page 68 of 84 f

r.'

_ l

- *3 ". *

-0 Operatior! Q=lity Assur=ce Plan Revision 19 Appendix C 4.0 Fire Protection Training 4.1 Monticello and Prairie Island

1. Level I fire protection training shall be general training given to operations and maintenance personnel assigned to nuclear power plants. Following initial training, these topics shall be reviewed at least annually with required personnel. Level I 1 i

shall cover, as a minimum, the following areas:

a. Basic principles of fire chemistry and physics.

b. Fire hazards.

I

1) Common fire hazards. .

2) Combustibles, general.

3) Flammable liquids. ,

t Flammable gases. I 4)

c. Fire detection systems.

d. Types of extinguishing systems.  :

e. Special fire hazards associated with nuclear power plants.

f. Emergency Plan with emphasis on fire emergency.

2. Basic instruction in fire protection shall be given to contractor personnel before l granting them unescorted access to safety related areas of the plant.  !

4.2 Monticello l

1. Fire brigade training shall be conducted in accordance with the requirements of  ;

10CFR50, Append:x R,III.I. )

)

I 1

1 Page 69 of'84 e

o 4 .'

I i

- Operational Quality Assurance Plan Revision 19 ' Appendix C l 4.3 PrairieIsland 1

1. Level II fire protection training shall be given to all fire brigade members. An initial training program with annual retraining shall be conducted. Retraining shall l repeat all Level II subject material over a period of approximately two years.

Level 11 shall include a detailed treatment of the subject matter in Level I. In addition, the following items shall be covered:

a. The identification and location of fire hazards and associated types of fires ,

that could occur in the plant. ,

b. The identification and location of fire fighting equipment in each fire area.

c. Familiarization with layout of the plant including access and egress routes in each area.

d. The proper use of fire fighting equipment. .

f

e. Methods of fighting each type of fire.

Review of the plant fire fighting strategies with specific coverage of each  !

f.

individual's responsibilities. 1

'.g Proper use of communication, lighting, ventilation and emergency breathing equipment.

h. Considerations of radiation and contamination in fire areas.

2. LevelIII training shall be presented to the fire brigade leaders. Initial training with ~

annual retraining shall be provided. Included will be a detailed review ofLevel I and II training and the following additional material:

a. The direction and coordination of fire fighting activities.

b. The proper method of fighting fire inside buildings and confined areas,

c. Evaluation of fire hazards.

. Page 70 of 84

e

', y l L  ; Operatio;al Quality Assur.rce Plan

' Revision 19 Appendix C :

3. Training Documentation ,

Classroom training sessions, practice sessions, and drills for the fire brigade shall -

be documented. The following should be included in the documentation for j

=

persons participating:

a. Name. i

b. Date.

c. Summary of what was done.

d. Evaluation by observer.  !

5.0 Drills and Practice i

5.1 Monticello

1. Fire protection drills and practices shall be conducted in accordance with the requirements of 10CFR50, Appendix R, Section III.I, and the requirements listed below:

• a. A meeting shall be held after each drill to discuss the drill and the need to repeat portions of the training program that are applicable to the type of drill performed.

b. Preplanned strategies, and the proficiency of brigade members and control .

room operators in their use shall be tested during drills.

c. Each year, one drill, conducted with any fire brigade, shall involve the local on-duty fire department.

5.1 Prairie Island

1. Drills l

a. Drills shall be scheduled so that each fire brigade will participate in at least i four drills per year. The following types of drills shall be scheduled:  !

1) Involve local on-duty fire department. This shall be done at least' once a year, with any fire brigade. 3 1

)

~

Page 71 of 84 L

. 'j ,l

.. Operational Quality Assurance Plan Revision 19 Appendix C-I

2) At three year intervals, a randomly ' selected, announced drill shall be critiqued by qualified individuals independent ofNSP's staff.

3) _ Back shift, conducted by the fire brigade leader on duty at the time.

' This shall be scheduled at least once per year for each brigade.

U b. Except as required above, drills may be announced and may involve only the shift fire brigade members (to preclude the disruption of essential plant activities).

c. All drills shall be preplanned and critiqued. A meeting shall be held after each drill to discuss the drill and the need to repeat portions of the training p ogram that are applicable to the type of drill perfonned.

d. To the extent practical, fire brigade members shall use protective equipment, suppression systems, and other equipment used to fight an actual fire during all drills. Preplanned strategies shall be tested during drills as well as the proficiency of brigade members and Control Room operators in their use.

2. ' Practice

a. Practice sessions shall be held at least once every year. These sessions shall involve actually fighting fires which are similar to those which might be encountered in the plant. These sessions shallinclude:

1) Use of fire fighting equipment.

2) Use of breathing equipment under strenuous conditions.

3) Extinguishment of fire.

4) Best method by which to approach each type of fire, to the extent possible.

b. Brigade members missing a practice session shall be rescheduled to attend a later session with another brigade. If this is not possible, they shall be required to review the training material covered during the practice session.

Page 72 of 84

h. <

e. .

)

i I

Operatio:al Quality Assur=ce Pl:n i Revision 19 Appendix C l 6.0 Control of Combustibles and Ignition Sources Monticello

,, 6.1

l. Control of combustibles and ignition sources shall be in accordance with the requirements of 10CFR50, Appendix R, Section III.K, and the requirements listed below:

a. All areas containing safety related equipment or cables shall be surveyed once each working day for fire hazards by a member of the plant staff.

b. Storage of combustible materials shall be permitted only in posted areas or in approved cabinets and containers.

c. Transient combustibles in any safety related area, or area containing safe shutdown equipment, shall be limited to the equivalent of 2 gallons of combustible liquid. Use oflarger amounts of combustible material shall be governed by written procedures which specify augmented fire protection measures.

d. A person designated as a fire watch and equipped to prevent and combat fire shall be assigned to safety related areas where cutting, welding, grinding and open flame work is involved.

e. The fire watch shall remain in the assigned area for 30 minutes after work involving the cutting, welding, grinding, or open flame is completed.

1) When excessive radiation exposure to the fire watch is a concern, alternate fire watch measures may be implemented if these alternate measures address how to detect, prevent and combat a fire in the fire watch area.

f. Where feasible, all movable combustible material below or within 35 feet of cutting, welding, grinding, or open flame work shall be removed, and all immovable combustibles below or within 35 feet shall be protected.

g. Smoking shall be prohibited in all safety related areas, except those specifically designated by the plant management.

Page 73 of'84

p ;

Operational Quality Assurance Plan u  ? Revision 19 Appendix C .

6.2 ' Prairic Island :

1. Permanent and Temporary Storage

a. Measures shall be established to minimize fire hazards in areas containing I safety related equipment or equipment required to safely shut down the reactor (s) which:

i 1) . Govern the handling and limitation of the use of ordinary L combustible materials, combustible and flammable gases and liquids, high efficiency particulate air and charcoa: filters, dry ion exchange resins, or other combustible supplies in safety related areas.

2) Govern the removal from the area of all waste, debris, scrap, oil l.

spills, or other combustibles resulting from the work activity

[ immediately following completion of the activity, or at the end of -

each work shift, whichever comes first.

l 3) Govern the handling of transient fire loads such as combustible and flammable materials during maintenance, modification, or refueling -

operations.

4) Govern the use of specific combustibles in safety related areas.

a) All wood used in safety related areas during maintenance, modification, or refueling operations (such as laydown ,

blocks or scaffolding) shall be treated with a flame retardant.

b) All untreated wood in safety related areas (during operations other than maintenance, modification or refueling) shall be limited to less than 2 cubic feet per area.  ;

c) Equipment or supplies (such as new fuel) shipped in untreated combustible packing containers may be unpacked in safety related areas if required for valid operating reasons. However, all combustible materials shall be removed from the area immediately follow'mg the unpacking.

d) Large amounts of combustible material shall not be left unattended during lunch breaks, shift changes, or other similar periods.

Page 74 of 84

I Operation:1 Qrlity Ass:racce PI:n Revision 19 Appendix C e) Loose combustible packing material such as wood or paper and excelsior shall be placed in metal containers with tight-fitting self-closing metal covers.

v

b. All areas containing safety related equipment or cables shall be surveyed once each working day for fire hazards by a member of the plant staff.

Storage of combustible materials shall be permitted only in posted areas or in approved cabinets and containers. Unnecessary transient combustibles shall not be stored in areas containing safety related equipment or areas containing safe shutdown equipment or other essential auxiliary equipment area (e.g., HVAC equipment room).

c. Transient combustibles in any safety related area or area containing safe shutdown equipment shall be limited to the equivalent of 2 gallons of combustible liquid. Use oflarger amounts of combustible material shall be governed by written procedures which specify augmented fire protection measures.

2. Cutting, Welding, Grinding and Open Flame

a. Cutting, welding, grinding and open flame work in safety related areas shall be administratively controlled. A person designated as fire watch and

. equipped to prevent and combat fire shall be assigned to safety related areas where cutting, welding, grinding and open flame work is involved.

The fire watch shall remain in these assigned areas for 30 minutes after the work involving the cutting, grinding or open flame is completed.

1) When excessive radiation exposure to the fire watch is a concern, alternate fire watch measures may be implemented if these alternate measures address how to detect, prevent and combat a fire in the fire watch area.

b. Where feasible, all movable combustible material below or within 35 feet of cutting, welding, grinding, or open flame work shall be removed and all

, inunovable combustibles below or within 35 feet shall be protected.

c. Smoking shall be prohibited in all safety related areas, except those specifically designated by the plant management.

d. Fire barrier penetration leak testing shall be done with approved and reviewed procedures. Permission to do this leak testing shall be obtained from the Shift Supersisor.

1 Page 75 of 84 )

i l

. h ,; ,

• l Operational Quality Assurance Plan Revision 19 Appendix C.

. 7.0 Fire Fighting Procedures

- 7.1 - Monticello Fire fighting procedures shall be established in accordance with the requirements of 10CFR50, Appendix R, Section III.K.

7.2 Prairie Island

1. Fire fighting procedures or instructions shall be developed to cover the following areas:

a. Discovery of fire including:

1) Notification.

2) Attempts to extinguish fire.

b. Action of Control Room operator including:

1) Announcement.

2) Sounding of fire alarm.

! 3) Who to notify.

c. Selection and delineation of responsibilities of fire brigade members.

d. Coordination of off-site fire department activities.

e. Actions of security guards during a fire emergency.

f. Delineation of responsibilities of other plant personnel.

g. Instructions and preplanned strategies for fighting fires in specific areas of the plant when the generalinstructions are not adequate. These instructions shallinclude:

1) Identification of combustibles in area.

2) Identification of safe shutdown equipment in area and alternate equipment available for performing that function.

3) Fire suppression equipment available in the area.

Page 76 of 84

o~

I L Operatioral Q:ality Ass:ra:ce Plas Revision 19 Appendix C

4) ~ Information showing ventilation control (power sources), access hallways, stairs, and doors.

5) Identification of plant systems that should be managed to reduce

,_ the damage potential from a fire in the area.

f:

6) Identification ofradiological and toxic hazards in the area.

7) Ventilation system lineups to minimize spread of smoke and to remove smoke from the area.

8) Identification of actions which must be coordinated with operations personnel.

f 2. Instructions and preplanned strategies shall be tested during drills.

8.0 Modification Control (Monticello and Prairie Island) 8.1 Review of modifications for possible impact on plant fire protection provisions shall be performed if determined required by a designated member of the plant technical staff. The following guidelines shall be used in making this determination:

1. . Could the modification present a hazard not considered in the Fire Hazards Analysis? Will additional analysis be required?

2. Could the modification have the potential to interfere with installed fire protection equipment or does it modify existing fire protection equipment?

3. Could the fire protection system require modification because of the change?

8.2 If a fire protection review is required, the individual assigned to perform the review shall use the following as a guide:

1. Does the modification reduce the fire protection provisions for safety related or

safe shutdown" equipment?

2. Will it be necessary to do a fire hazards analysis?

3. Does the design present an obstruction to installed fire protection equipment?

4. Will the installation of the equipment temporarily remove a fire protection system from service?

Page 77 of'84

4 ,,, . -

t Operational Quality Assurance Plan Revision 19 Appendix C

5. Does the modification involve thermal stress relieving and, if so, have precautions been taken?

6. Will any fire barriers be affected by the modification?

8.3 A modification shall be allowed to proceed only after satisfactory resolution of these concerns.

9.0 Procurement Control (Monticello and Prairie Island) 9.1 Underwriters Laboratories (UL) and Factory Mutual (FM) directories shall be reviewed to determine if the item is listed as being UL or FM approved. If the item is listed, a manufacturer shall be identified and the item procured in accordance with NSP's procurement process for nuclear plants.

The one exception for not buying an item that is UL or FM listed is ifit is a replacement of original equipment or NSP standard type, then it shall be identified as such and procured from the original supplier or manufacturer. As a minimum, the item or equipment shall, by appropriate testing, meet NFPA standards.

9.2 If the item is not listed by UL or FM, the following process shall be used:

1. An evaluation shall be made to determine the compatibility of the item to the existing system or component, pr

2. If the item has been manufactured for a long period of time, gn.d

a. The item is standardized, ad

b. The item has a satisfactory performance historf, and I

c. Appropriate receipt inspection is identified in the procurement documents, then an evaluation is unnecessary. The fact that the supplier and item  !

meets these requirements shall be documented in the procurement files. I 9.3 Parts of components and equipment that have UL or FM approval as a unit shall be procured as follows:

1. The part shall be manufactured by the original manufacturer of the component or i equipment whenever possible.

2. The model number of the component or equipment shall be identified.

i Page 78 of 84

1

• h=

Operatiozal Qrlity Assur; ce Pia Revision 19 Appendix C

3. The specific part number shall be identified.

4. Documentation from the supplier shall be requested that indicates the part delivered meets the specification of the part used in the original component or equipment. If the part has been changed, the manufacturer shall be asked to indicate any changes in the operation of the component or equipment. In lieu of this documentation, the acceptance of the part shall be based on inspection or testing. ,

9.4 All purchase requisitions pertaining to fire protection systems and equipment shall be reviewed by an individual designated by the Plant Manager.

10.0 Instructions, Procedures, and Drawings (Monticello and Prairie Island) 10.1 The system of Administrative Control Directives (ACDs) shall be used to delineate responsibilities and requirements for the fire protection program.

10.2 Departmental instructions and procedures shall be revised or issued to implement the fire protection program responsibilities and requirements contained in the ACDs.

10.3 Fire protection maintenance, modifications, inspections, tests, administrative controls, drills, and training shall be prescribed by written instmetions, procedures, and drawings.

11.0 Surveillance and Inspection (Monticello and Prairie Island) 11.1 The Technical Specifications specify the surveillance and inspection requirements for the fire protection system. Surveillance shall be scheduled, performed, and documented in accordance with standard directives governing the surveillance testing program.

I1.2 Procedures shall be developed to assure adequate preventive maintenance of fire protection equipment, including fire suppression water system pumps and hydrants.

12.0 Conditions Adverse to Fire Protection (M'onticello and Prairie Island) 12.1 Administrative Control Directives shall establish criteria for housekeeping.

12.2 Work control process procedures shall be used to correct equipment failure, malfunctions, deficiencies, and defective components of fire protection systems.

12.3 As part of the training process, site personnel shall be instructed on how to identify fire hazards and report them to their supervisor.

Page 79 of 84 i

v 4* i

-I Operational Quality Assurance Plan Revision 19 Appendix C 1

13.0 Records (Monticello and Prairie Island) )

l Site and Corporate directives establish nuclear plant records, creation, and retention I requirements. Fire protection records requirements shall be included in the scope of these -

directives.

i 14.0 Audits (Monticello and Prairie Island.) l 14.1 In addition to normal quality assurance audits (at least biennial), an independent fire l protection and loss prevention inspection and audit shall be performed annually at each plant utilizing either qualified off-site NSP personnel or an outside fire protection engineer [

or engineering consultant (annual independent inspection).

14.2 An inspection and audit by an outside qualified fire protection engineer or engineering consultant (see Section 2.3) shall be performed at each plant at least every three years (triennial independent inspection).

14.3 Inspection and audit results shall be reported to levels of management having fire protection program responsibilities in those areas audited or inspected.

C l

l Page 80 of 84

p7

,; (,

f 'Op:rati cci Qu lity Assurance PIIn  ;

Revision 19 Appendix D APPENDIX D

.l Revision 19 Change Summary i

This appendix summarizes the changes made in Revision ~ 19 to the Operational Quality Assurance Plan.

The intent of this appendix is to fulfill the requirements for identifying changes in accordance with 10CFR50.54(a)(3), Conditions of Licenses. This appendix is not a part of the Operational Quality Assurance Plan.

Change Number identifies the change number next to the sideline on the affected pages.  ;

Page identifies the page numbers containing the change.

Reason (R) identifies the reason for the change. ,

Basis (B) identifies the basis for concluding that the revised program incorporating the change continues to satisfy 10CFR50, Appendix B and the quality assurance program description commitments ,

previously accepted by the NRC.

Change Reason (R):

Number Page(s) Basis (B):

I back of R: To improve the structure of the document, coversheet, these pages are identified as being left back of page -i , intentionally blank.

1 8,10,54 B: Not required; editorialitem.

(no sidebars) 2 -i- R: Corrected typo in the title of section 12.0.

B: Not required; editorialitem.

3 -i- R: Revision number updated to 19.

B: Not required; editorialitem.

4 4 R: The word " Firms" was uncapitalized.

B: Not required; editorialitem.  !

1 5 4 R: NSP retracts the exception taken to ANSI l N18.7-1976.

B: This is an improvement to the QA Plan.

Page 81 of 84

p e

4.,,,r

'I Operational Quality. Ass:rrsco PI:n -

Revision 19 : Appendix D -

Change.  : Reason /

Number Page(s) - Basis -

-6 9,12,14,15,66 R: Title change from Director Nuclear Quality to Director Generation Quality Services B: This is a title' change only. It does not reduce previous commitments.

7 9,12,66,67- R': The position of General Manager Nuclear Site was eliminated due to corporate reorganization. Responsibilities assumed by Plant Manager

.B: This is a responsibility assignment change only.

It does not reduce previous commitments.

8 9 R: Title change from Director Support Services to Director Production Services.

B: This is a title change only. It does not reduce previous commitments.

9 9 B: The responsibility for testing laboratory services was reassigned from the President &

, Chief Operating Officer to the Director Production Services.

R: This is a responsibility assignment change only.

It does not reduce previous commitments.

10 9 R: Vice President Public & Governmental Affairs added as a position with QA responsibilities.

B: This is a new position. It does not reduce previous commitments.

11 9 R: Director Environmental & Regulatory Affairs now reports to the Vice President Public &

Governmental Affairs.-

B: This change is based on the corporate

, reorganization. It does not reduce previous -

commitments.

Page 82 of 84

m  :

J- ,

..p 4

3 Operatio:al Quzlity Assurance P! n Revision 19 Appendix D l l

Change Reason /

Number Page(s) Basis 12 9,12 R: The position of President & Chief Operating Officer was eliminated. The direct reports of this position, President NSP Electric and Vice President Human Resources, are now shown in Figure 1 as management positions with the operational quality assurance responsibilities previously assigned to the President & Chief Operating Officer.

B: This is a change based on the corporate reorganization. It does not reduce previous commitments.

13 12 R: Removed reference to specific positions directing the Vice President Nuclear Generation to formulate and implement an Operational Quality Assurance Program with the elimination of the position ofPresident &

Chief Operating Officer. Rather, the ,

management positions responsible for this

, direction is referenced in generic terms (as NSP senior management) to accommodate organizational and responsibility changes.

Responsible NSP senior management is accurately reflected in Figure 1.

B: This is an editorial decision to reflect the empowering senior management positions in a generic manner. It does not reduceprevious commitments.

14 12 R: NSP is in the process of restructuring its Directives and Im,tructions. When complete (scheduled completion in 1995), Directives will be corporate luel documents and Instructions will be site level documents. The relationship between the, two documents remains the same.

This change recognizes that at some point in 1995 there will not be corporate level Instructions nor will there be site level Directives.

B: This is a process change only. It does not  ;

reduce previous commitments. I Page 83 of 84

7 - 2 y ..

~y, t- +

- Operational Quality Assurance Plan -

- Revision 19 Appendix D i

. Change - .

- Reason /

Number Page(s) Basis  ;

15 14,30,45 R: Title change from Nuclear Quality Department to Generation Quality Services. l B: This is a title change only. It does not reduce '!

previous commitments.  ;

e 16 28 R: Corrected reference from 10CFR50.55 to 10CFR50.55a.

B: This is a correction to a reference source only.

It does not reduce previous commitmems.

17 40 R: Clarification as to actions where physical segregation is not practical. I B: Change is consistent with current commitments to ANSIN45.2-1971, section 16, and ANSI 18.7-1972, section 5.2.14. As such, it does  !

not reduce previous commitments.

18 58 'R: Eliminated extraneous comma after" October."

B: Not required; editorialitem.

19 66,67 R: Section renumbered old sections 2.2-3 and 'l 2.2-4 as sections 2.2-2 and 2.2-3 respectively, i due to elimination of old section 2.2-2.

Not required; editorialitem. I B:

.i 2- l I

I Page 84 of 84

.